Proposed tech specs reflecting revs to Section 6.0, "Administrative ...

ATTACHMENT A

EXISTING SPECIFICATIONS UNIT 2

9212210215 921216 PDR ADOCK 05000361 P PDR

* -7

(18) Initial Test Program (Section 14. SER)

SCL shall conduct the post-fuel loading initial test program (set.forth in Section 14 of the San Onofre Units 2 and 3 Final Safety Analysis Report. as amenaed) without making any major modifications to this program unless such modifications have been identified and have received prior WRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of the Final Safety Analysis Report. as amended, as being essential.

b. Modification of test objectives.,methoos. or acceptance criteria for any test identified in Section 14 of the Final Safety Analysis Report, as amenaea, as being essential.

c. Performance of any test at a power level different tnan that described in the test procedure.

d. Failure to complete any tests incluoed in the described program (plannea or scheduled for power levels up to the authorized power level).

(19) NUREb-0737 Conditions (Section 22)

Each of the following conditions shall be completea to the satisfaction of the NRC. Each item references the related subpart of Section 22 of the SER and/or its supplements.

a. Shift Technical Advisor (I.A.1.1. SSER 01)

SCE shall provice a fully trained on-shift technical advisor to the shift supervisor (watch engineer).

b. Shift Manning (I.A.1.3. SSER 01. SSER #5)

SCE shall develop and implement administrative procedures to limit the working hours of individuals of the nuclear power plant operating staff who are responsible for manipulating plant controls or for adjusting on-line systems and equipment affecting plant safety which would have an immediate impact on public health anc safety.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However. in the event that unforesEen problems require substantial amounts of overtime to be used. the following guidelines shall be followed:

EEB 17 in

-8

1. An individual shall not be permitted to work more than 16 hours straight (excluding shift turnover time).

2. An individual shall not be permitted to-work more than 16 hours in any 24-hour pe-riod, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any seven day period (all excluding shiftturnover time).

3. A break of at least eight hours shall be allowed between work periods (including shift turnover time).

4. The use of overtime shall be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the station manager, his deputy, the operations manager, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the station manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

c. Indecendent Safety Engineerino GrouD (1.8.1.2, SSER 1)

SCE shall have an on-site independent safety engineering group.

d. Procedures for Transients and Accidents (1.C.1, SSER #1,

By May 1, 1982, SCE shall provide emergency procedure guidelines. Emergency procedures based on guidelines approved by the NRC shall be implemented prior to startup following the first refueling outage.

e. Procedures for Verifying Correct Performance of Operatino Activities U.C.6, S5ER *I)

Prior to fuel loading, SCE shall implement a system for verifying the correct performance of operating activities, and shall keep the system in effect thereafter.

f. Control Room Design Review (I.D.1, SSER 01)

Prior to exceeding five (5) percent power, SCE shall:

1. Prioritize the control room annunciator windows.

FEB 17 196

-13

0. Exemptions to certain requirements of Appendices G, H and 3 to 10 CFR

Part^^50 are described in the Office of Nuclear Reactor Regulation's

Safety Evaluation Report. These exemptions are authorized by law and

will not endanger life or property or the common defense and security and are otherwise in the public interest. Thqrefore, these exemptions are

hereby granted. The facility will operate, to the extent authorized herein, in conformity with, the applicatio, -as amend.e,..the. provisions of the Act, and the regulations of the Commission.

E. SCE shall fully implement and maintain in effect all provisions of the

Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to

provisions of the Miscellaneous Amendments and Search Requirements

revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "San Onofre

Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan,u with revisions submitted through April 22, 1988; "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and

Qualification Plan," with revisions submitted through October 22, 1986; and "San Onofre Nuclear Gcnerating Station, Units 1, 2, and 3, Safeguards Contingency Plan," with revisions submitted through December 29, 1987.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F. This license is subject to the following additional condition for the protection of the environment:

Before engaging in activities that may result in a significant adverse

environmental impact that was not evaluated or that is significantly greater -than that evaluated in the Final Environmental Statement, SCE

shall provide a written notification of such activities to the NRC Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities.

* On September 29, 1983, the Safeguards Contingency Plan was made a separate, companion document to the Physical Security Plan pursuant to the authority of 10 CFR 50.54.

AMENDMENT NO. 67

INDEX

DEFINITIONS

SECTION PAGE

1.0 DEFINITIONS

1.1 ACTION... 1-1 1.2 AXIAL SHAPE INDEX........................................... 1-1 1.3 AZIMUTHAL POWER TILT....................................... 1-1 1.4 CHANNEL CALIBRATION......................................... 1-1 1.5 CHANNEL CHECK................................................ 1-1 1.6 CHANNEL FUNCTIONAL TEST..................................... 1-2 1.7 CONTAINMENT INTEGRITY....................................... 1-2 1.8 CONTROLLED LEAKAGE.......................................... 1-2 1.9 CORE ALTERATION............................................. 1-2 1.10 DOSE EQUIVALENT I-131....................................... 1-3 1.11 r-AVERAGE DISINTEGRATION ENERGY....... 1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME................ 1-3 1.13 FREQUENCY NOTATION.......................................... 1-3 1.14 GASEOUS RADWASTE TREATMENT SYSTEM........................... 1-3 1.15 IDENTIFIED LEAKAGE.................... 1-3 1.16 OFFSITE DOSE CALCULATION MANUAL (00CM)...................... 1-4 1.17 OPERABLE - OPERABILITY......................................1-4 1.18 OPERATIONAL MODE-MODE....................................... 1-4 1.19 PHYSICS TESTS.............................................. 1-4 1.20 PLANAR RADIAL PEAKING FACTOR - F........................... 1-4 xy . . . . . . . . . . . . . 1.21 PRESSURE BOUNDARY LEAKAGE................................... 1-4 1.22 PROCESS CONTROL PROGRAM (PCP)............................... 1-4 1.23 PURGE-PURGING............................................... 1-5 1.24 RATED THERMAL POWER......................................... 1-5 1.25 REACTOR TRIP SYSTEM RESPONSE TIME........................... 1-5 1.26 REPORTABLE OCCURRENCE....................................... 1-5 1.27 SHUTDOWN MARGIN............................................. 1-5 1.28 SOFTWARE........................ ..................... :..... 1-5 1.29 SOLIDIFICATION -- DELETED 1.30 SOURCE CHECK...............................................1-5 1.31 STAGGERED TEST BASIS........................................ 1-6 1.32 THERMAL POWER............................................... 1-6 1.33 UNIDENTIFIED LEAKAGE....................................1-6 1.34 VENTILATION EXHAUST TREATMENT SYSTEM.........................1-6 1.35 VENTING................................................... 1-6

SAN ONOFRE-UNIT 2 I AMENDMENT NO. 83

INDEX

ADMINISTRATIVE CONTROLS

SECTION PAGE

6.1 RESPONSIBILITY. .61

6.2 ORGANIZATION

6.2.1 OFFSITE...............................................6-1

6.2.2 UNIT STAFF............................................. 6-1

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP............. .... 6-5

6.2.4 SHIFT TECHNICAL ADVISOR................................. 6-5

6.3 UNIT STAFF QUALIFICATIONS.........................5

6.4 TRAINING..................................... 6-6

6.5 REVIEW AND AUDIT

6.5.1 ONSITE REVIEW COMMITTEE

FUNCTION............................................. 6-6 COMPOSITION.......................................... 6-6 ALTERNATES........................................... 6-6 MEETING FREQUENCY.................................... 6-7

QUORUM............................................... 6-7 RESPONSIBILITIES..................................... 6-7 AUTHORITY........................................... 6-8 RECORDS.............................................. 6-8

6.5.2 TECHNICAL REVIEW AND CONTROL............................ 6-8

6.5.3 NUCLEAR SAFETY GROUP

FUNCTION................................................ 6-9 COMPOSITION............................................. 6-10 CONSULTANTS............................................. 6-10

REVIEW.................................................. 6-10

AUDITS.................................................. 6-11

SAN ONOFRE-UNIT 2 XVI AMENDMENT NO. 83

INDEX


SECTION PAGE

AUTHORITY............................................... 6-12

RECORDS................................................. 6-12

6.6 REPORTABLE OCCURRENCE ACTION............................ 6-13

6.7 SAFETY LIMIT VIOLATION...................................... 6-13

6.8 PROCEDURES AND PROGRAMS..................................... 6-13

6.9 REPORTING REQUIREMENTS

6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES............... 6-15b

STARTUP REPORT...................................... 6-15b

ANNUAL REPORTS...................................... 6-16

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT... 6-17

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT....... 6-17

MONTHLY OPERATING REPORT............................. 6-17

REPORTABLE OCCURRENCES............................... 6-18

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP............ 6-18

THIRTY DAY WRITTEN REPORTS........................... 6-20

HAZARDOUS CARGO TRAFFIC REPORT....................... 6-20

6.9.2 SPECIAL REPORTS........................................ 6-20

6.10 RECORD RETENTION....................................... 6-20

6.11 RADIATION PROTECTION PROGRAM.................... .. 6-22

6.12 HIGH RADIATION AREA ..................................... 6-22

6.13 PROCESS CONTROL PROGRAM (PCP)...................... 6-23

6.14 OFFSITE DOSE CALCULATION MANUAL.............................. 6-24

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS --DELETED

SAN ONOFRE-UNIT 2 XVII AMENDMENT NO. 83

INDEX

LIST OF TABLES

TABLE PAGE

4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.............................. 3/4 7-8

3.7-5 SAFETY-RELATED SPRAY AND/OR SPRINKLER SYSTEMS............ 3/4 7-31

3.7-6 FIRE HOSE STATIONS....................................... 3/4 7-33

4.8-1 DIESEL GENERATOR TEST SCHEDULE........................... 3/4 8-7

4.8-2 BATTERY SURVEILLANCE REQUIREMENTS........................ 3/4 8-11

3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES....................................... 3/4 8-18

3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES........................................... 3/4 8-32

3.10-1 RADIATION MONITORING/SAMPLING EXCEPTION -- DELETED

4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM -- DELETED

4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM -- DELETED

.3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -- DELETED

3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES -- DELETED

4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) -- DELETED

B 3/4.4-1REACTOR VESSEL TOUGHNESS................................. B 3/4 4-8

5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS................. 5-8

6.2-1 MINIMUM SHIFT CREW COMPOSITION........................... 6-4

SAN ONOFRE-UNIT 2 XX AMENDMENT NO.831

INDEX

LIST OF FIGURES

FIGURES PAGE

3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURES AS A FUNCTION OF STORED BORIC ACID CONCENTRATION......... 3/4 1-13

3.1-2 CEA INSERTION LIMITS.................... 3/4 1-24

3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON COLSS............... 3/4 2-7 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION

CALCULATORS (COLSS OUT OF SERVICE)...................... 3/4 2-8 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING...................... 3/4 3-40

4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA.................. 3/4 4-15a

3.4-1 DOSE EQUIVALENT 1-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT ...................................... 3/4 4-26

3.4-2 RCS HEATUP PRESSURE/TEMPERATURE LIMITATIONS FOR 4-8 EFPY ........................................ 3/4 4-29

3.4-3 RCS COOLDOWN PRESSURE/TEMPERATURE LIMITATIONS FOR 4-8 EFPY... ..................................... .. 3/4 4-30

3.7-1 MINIMUM REQUIRED FEEDWATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO DATE............ 3/4 7-6A

5.1-1 EXCLUSION AREA...........I .......................... 5-2

5.1-2 LOW POPULATION ZONE......................... ......... 5-3

5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS..................... 5-4

5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS....... .......... .... 5-5

5.6-1 UNITS 2 & 3 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS........ .......................... 5-12

5.6-2 UNIT 1 FUEL*MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS.................... .............. 5-13

5.6-3 FUEL STORAGE PATTERNS FOR REGION II RACKS................ 5-14

5.6-4 FUEL STORAGE PATTERNS FOR REGION II RACKS RECONSTITUTION STATION.............................. 5-15

6.2-1 OFFSITE ORGANIZATION.............. .... .................. 6-2

6.2-2 UNIT ORGANIZATION................................... .6-3

6.2-3 CONTROL ROOM AREA.................................... 6-4a

SAN ONOFRE*UNIT 2 XXI AMENDMENT NO. 87

DEFINITIONS

PURGE -PURGING

1.23 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER

1.24 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3390 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME

1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE OCCURRENCE

1.26 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9.1.12 and 6.9.1.13.

SHUTDOWN MARGIN

1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming (1) all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn, and (2) no change in part length control element assembly position.

SOFTWARE

1.28 The digital computer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation and procedures.

1.29 DELETED

SOURCE CHECK

1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

SAN ONOFRE-UNIT 2 1-5 AMENDMENT NO. 83

SECTION 6.0


9e


6.1 RESPONSIBILITY

6.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the Control Room Area, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION

OFFSITE

6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR.

b. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President, Nuclear Engineering, Safety, and Licensing and the Vice President and Site Manager shall have corporate responsibility for overall plant nuclear safety. The Vice President and Site Manager shall take any measures needed to ensure acceptable performance of the staff in operating and maintaining the plant to ensure nuclear safety. The Vice President, Nuclear Engineering, Safety and Licensing shall take any measures needed to ensure acceptable performance of the staff in providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

SAN ONOFRE-UNIT 2 6-1 AMENDMENT No. 68


UNIT STAFF

6.2.2 a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room area identified as such on Table 6.2-1. c. A health physics technician shall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

e. A site Fire Bgigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Supervisor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

f. Reserved.

g. The Plant Superintendent (at time of appointment), Shift Superintendents and Control Room Supervisors shall hold a senior reactor operator license. The Control Operators and Assistant Control Operators shall hold a reactor operator license.

The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

SAN ONOFRE-UNIT 2 6-la AMENDMENT NO. 68.

(This page intentionally blank)


Table 6.2-1

MINIMUM SHIFT CREW COMPOSITION

ITH UNIT 3 IN MODE 5 OR 6 OR DE-FUELED

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION

MODES 1, 2, 3 & 4 MODES 5 & 6

1a 1a SS lal SRO I None RO 2 AO 2 2 STA 1 None

wITH UNIT 3 IN MODE 1, 2, 3 or 4


MODES 1, 2, 3 &4 MODES 5 & 6

a 1a L5 la la 50 1. None RO 2 1 AO 1 STA 1a None

a~ndividual may fill the same position on Unit 3 One of the two required individuals may fill tne same position on Unit 3

53 - Shift Supervisor with a Senior Reactor Operators License on Un.its 2 and 3

SRO - Individual with a Senior Reactor Operators License on Units 2 and 3

RO - Individual with a Reactor Operators License on Units 2 and 3 A' Auxiliary Operator

- S.it Technical Acvisor

:e-t for the Shift Suervisor, the Shift Crew Composition may be one less tnan the minimum requirements of Table 6.2-1 for a period of time not to exceed

2 nours in order to accommodate unexpected absence of on-duty shift crew memoers provided immediate action is taken to restore the Shift Crew Czmosition to within the minimum requirements of Table 6.2-1. This provision coes

not permit any shift crew position to be unmanned upon shift change cue to an oncoming shift crewan being late or absent.

During any absence of the Shift Supervisor from the Control Room Area snown in

:F r .2-3 while the unit is in MODE 1, 2, 3 or 4, an individual (otner tzan

:ne S3ift Technical Acvisor) with a valid SRC license shall be designraad to assume the Control Room com.and function. During any aesence of the Shi t. Su:ervior from tne Control Room Area srown in Figure 6.2-3 while tie unit is

in MCOE 5 or 5, an -individual with a valid SO or RO license shall be essgnatec

:: assume tne Control Room command function.

SAN NE - 2 6-4 Amendnen: No. 1

C3

'U UUUUU UUUUUUUUJ

- -- 1 .1 1 T1 -n n il

Control Room

Unit 2 Unit 3.

~E=

SUPV Office

figure 6.2-3

CONTROL ROOM AREA

5A 0.01E NUCLEAR GENERATING STATION UNIT 2

08 I2~LSee


6.2.3 INDEPENDENT SAFETY ENGINEERING-GROUP (ISEG)

FUNCTION

6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information which may indicate areas for improving plant safety.

COMPOSITION

6.2.3.2 The ISEG shall be composed of at least five dedicated full-time engineers. Each shall have a Bachelor's Degree in Engineering or Physical Science or equivalent and at least two years professional level experience in his field. Off-duty qualified Shift Technical Advisors may be used to fulfill this requirement.

RESPONSIBILITIES

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification* that these activities are performed correctly and that human errors are reduced as much as practical. AUTHORITY

6.2.3.4 The ISEG shall make detailed recommendation. for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to offsite organization management. RECORDS

6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to offsite organization management.

6.2.4 SHIFT TECHNICAL ADVISOR

The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit. The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents. 6.3 UNIT STAFF QUALIFICATIONS

6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

A

Not responsible for sign-off function.

SAN ONOFRE-UNIT 2 6-5 AMENDMENr No. 68


6.4 TRAINING

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training and shall meet or exceed the requirements and recommendations of Sections 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental

requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.


6.5.1 ONSITE REVIEW COMMITTEE (OSRC)

FUNCTION

6.5.1.1 The Onsite Review Committee shall function to advise the Station

Manager on all matters related to nuclear safety.

COMPOSITION

6.5.1.2 The Onsite Review Committee shall be composed of the:

Chairman: Station Manager Member: Deputy Station Manager Member: Manager, Operations

Member: Manager, Technical Member: Plant Superintendent SONGS Unit 2 3 Member: Supervisor of I&C Member: Manager, Health Physics Member: Supervisor of Chemistry Member: Manager, Maintenance Member: Supervising Engineer (NSSS, NSSS Support,

Computer, or STA) Member: San Diego Gas & 3ectric Representative,

Senior Engineer

ALTERNATES

6.5.1.3 All alternate members shall be appointed in writing by the OSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSRC activities at any one time.

BS degree in Engineering or Physical Science plus at least four years

professional level experience in his field. At least one of the four years

experience shall be nuclear power plant experience.

SAN ONOFRE-UNIT 2 6-6 A endmentNo. 4

JUL 1 6 92 V

. ADMINISTRATIVE CONTROLS

MEETING FREQUENCY

6.5.1.4 The OSRC shall meet at least once per calendar month and as convened by the OSRC Chairman or his designated alternate.

QUORUM

6.5.1.5 The minimum quorum of the OSRC necessary for the performance of the OSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES

6.5.1.6 The Onsite Review Committee shall be responsible for:

a. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).

b. Review of events requiring 24-hour written notification to the Comission.

c. Review of unit operations to detect potential nuclear safety hazards.

d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the NSG.

e. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last OSRC meeting.



AUTHORITY

6.5.1.7 The Onsite Review Committee (OSRC) shall:

a. Render determinations in writing with regard to whether or not items considered under 6.5.1.6(a) above constitute unreviewed safety questions.

b. Provide written notification within 24 hours to the Manager of Nuclear

Operations and NSG of disagreement between the OSRC and the .Station

Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS

6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities

performed under the responsibility and authority provisions of these technical

specifications. Copies shall be provided to the Nuclear Safety Group.

6.5.2 TECHNICAL REVIEW AND CONTROL

ACTIVITIES

6.5.2.1 The Station Manager shall assure that each procedure and program

required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual/organization. Each

such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes thereto,

but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.

6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall

be prepared by a qualified individual/organization. The preparation of each

proposed Technical Specifications change shall be reviewed by an individual/

group other than the individual/group -which prepared the proposed change, but who may be from the same organization as the individual/group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the Station Manager.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/

organization. Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems

and components shall be approved prior to implementation by the Station Manager;

or by the Manager, Technical as previously designated by the Station Manager.

SAN ONOFRE-UNIT 2 6-8 Amendment No. 4

JUL 1 6


ACTIVITIES (Continued)

6.5.2.4 Individuals responsible for reviews performed in.accordance with 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed .by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, the Manager, Technical, the Manager, Operations, the Manager, Maintenance, the Deputy Station Manager or the Manager, Health Physics as previously designated by the Station Manager.

6.5.2.6 The station security program, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the NSG.

6.5.2.7 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the NSG.

6.5.2.8 The Station Manager shall assure the performance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager of Nuclear Operations and to the NSG.

6.5.2.9 The Station Manager shall assure the performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

6.5.2.10 Reports documenting each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Nuclear Safety Group.

6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION

6.5.3.1 The Nuclear Safety Group shall function to provide independent review and audit of designated activities in the areas of:


JH!


FUNCTION (Continued)

a. nuclear power plant operations

b. nuclear engineering

C. chemistry and radlochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices

COMPOSITION

6.5.3.2 NSG shall consist of a Supervisor and at least three staff specialists. The Supervisor shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of six years of professional level managerial experience in the power field. Each staff specialist shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of five years of professional level experience in the field of his specialty.

The NSG shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.2.1. Such specialists shall meet the same qualification requirements as the NSG members.

CONSULTANTS

6.5.3.3 Consultants shall be utilized as determined by the NSG Supervisor to provide expert advice to the NSG.

REVIEW

6.5.3.4 The NSG shall review:

a. The safety evaluations for 1) changes to procedures required by SpecIfication 6.8, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify tnat such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.


Jt' I j8

Ag: .rST.ATIVE CONTROLS

d. Proposed changes to Technical Specifications or this Operating License.

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions

having nuclear safety significance.

f. Significant cerating abnormalities or deviations from normal and

expected performance of unit equipment that affect nuclear safety.

g. Events requiring 24 hour written notification to the Commission.

h. All recognized indications of an unanticipated deficiency in some

aspect of design or operation of structures, systems, or components that could affect nuclear safety.

i. Reports and meetings minutes of the Onsite Review Committee.

AUOITS

6.5.3.5 Audits of unit activities shall be performed under the ccgnizance of

the N5G. These audits shall encompass:

a . The conformance of unit operation tb provisions contained within the

Technical Specifications and applicable license conditions at least

once per 12 months.

b. The performance, training and qualifications of the entire unit staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in

unit equipment, structures, systems or method of operation that

affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50,

at least once per 24 months.

e. Any other area of unit operation considered appropriate by the Nuclear Safety Group or Manager of Nuclear Operations.

f. The Fire Protection Program and implementing procedures at least

once per 24 months.

g. An independent fire protection and loss prevention inspection and

audit shall be performed annually utilizing either qualified offsi*t

licensee personnel or an outside fire protection firm.

h. An inspection and audit of the fire protectiorn and loss preventicn

program shall be performed by an outside qualified fire c:nsultZnt at intervals no greater than 3 years.

KV 16 IQA'

SANI CNCFRE-U?4IT 2 6-11 A! 4E' , T N. 0


AUTHORITY

6.5.3.6 The NSG shall report to and advise the offsite organization management on those areas of responsibility specified in Sections 6.5.3.4 and 6.5.3.5.

RECORDS

6.5.3.7 Records of NSG activities shall be prepared and maintained. Report of reviews and audits shall be distributed monthly to the Station Manager and to the management positions responsible for the areas audited.

SAN ONOFRE*UNIT 2 6-12 AMENDMENT No. 68


6.6 REPORTABLE OCCURRENCE ACTION

6.6.1 The following, actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviewed by the OSRC and submitted to the NSG and the Manager of Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION

6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager of Nuclear Operations and the NSG Chairman shall be notified within 24 hours.

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the OSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

c. The Safety Limit Violation Report shall be submitted to the Commission, the Manager of Nuclear Operations and the NSG within 14 days of the violation.

d. Critical operation of the unit shall not be resumed until authorizedby the Commission.

6.8 PROCEDURES AND PROGRAMS

6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

SAN ONOFRE-UNIT 2 6-13

FEB 17 1982


g. PROCESS CONTROL PROGRAM implementation.*

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15 Rev. 1, February 1979.

j. Modification of Core Protection Calculator (CPC) Addressable Constants. These procedures should include provisions to assure that sufficient margin is maintained in CPC Type I addressable constants to avoid excessive operator interaction with the CPCs during reactor operation.

NOTE: Modifications to the CPC software (including changes of algorithms and fuel cycle specific data) shall be performed in accordance with the most recent version of "CPC Protection Algorithm Software Change Procedure," CEN-39(A)-P that has been determined to be applicable to the facility. Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the Station Manager; or by (1) the Deputy Station Manager, (2) the Manager, Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager, Health Physics as previously designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed and approved by the Station Manager; or by (1) the Deputy Station Manager, (2) the Manager, Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager, Health Physics as previously designated by the Station Manager; within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a. Primary Coolant Sources Outside Containment

A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the high pressure safety injection recirculation, the shutdown cooling system, the reactor coolant sampling system (post-accident sampling piping only), the containment spray system, the radioactive waste gas system (post-accident sampling return



piping only) and the liquid radwaste system (post-accident sampling return piping only). The program shall include the following:

(i) Preventive maintenance and periodic visual inspection requirements, and

(ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

*See Specification 6.13.1

SAN ONOFRE-UNIT 2 6-14a AMENDMENT NO. 47


b. In-Plant Radiation Monitoring

A program* which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program* shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and

(iii) Provisions for maintenance of sampling and analysis equipment.

c. Secondary Water Chemistry

A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and control points for these variables,

(ii) Identification of the procedures used to measure the values of the critical variables,

(iii) Identification of process sampling points, including monitoring, the discharge of the condensate pumps for evidence of condenser in-leakage,

(iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control

point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the

interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Post-Accident Sampling

A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program* shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

e. Radioactive Effluent Controls Program

A program shall be provided conforming with 10 CFR 50.36a for the control of radoactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program

*Not required to be implemented until -September 1, 1983.


A0MINISTRATIVE CONTROLS

Radioactive Effluent Controls Program (Continued)

limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the 00CM;

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B,*Table II, Column 2;

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the 00CM;

4) Limitations on the annual and.quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50;

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, respectively, in accordance with the methodology and parameters in the 00CM at least every 31 days;

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyondthe SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20 Appendix B, Table II, Column 1.

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50.

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodlne-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR

Part 50.

SAN ONOFRE-UNIT 2 6-15a AMENDMENT NO. 8 3


10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Radiological Environmental Monitoring Program

A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the 00CM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring,.sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the 00CM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.


ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC Regional Administrator unless otherwise noted. STARTUP REPORT

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

SAN ONOFRE-UNIT 2 6-15b AMENDMENT NO. 83


6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS*

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted-prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated manrem exposure according to work and job functions,** e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments" to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

Reports required on an annual basis shall include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7. The following information shall be included in these reports: (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceed and results of one analysis after the radioiodine.activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function time for the duration of the specific activity above the steady-state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.



ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the 00CM and (2) Sections IV.8.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

6.9.1.7 DELETED

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be sumbitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the 00CM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.8.1 of Appendix I to 10 CFRI Part 50. 6.9.1.9 DELETED

MONTHLY OPERATING REPORT

6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change(s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted in accordance with 6.5.2.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SAN ONOFRE-UNIT 2 6-17 AMENDMENT NO.83


REPORTABLE OCCURRENCES

6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP

6.9.1.12 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the NRC Regional Administrator, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.

b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the Limiting Condition for Operation established in the Technical Specifications.

c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.



d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the Technical Specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% ak/k; or occurrence of any unplanned criticality.

e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR.

f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

g. Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifications.

h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

i. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

j. Offsite releases of radioactive materials in liquid and gaseous effluents that exceed the limits of Specifications 3.11.1.1 or 3.11.2.1.

k. Exceeding the limits in Specification 3.11.1.4 or 3.11.2.6 for the storage of radioactive materials in the listed tanks. The written follow-up report shall include a schedule and a description of activities planned and/or taken to reduce the contents to.within the specified limits.

1. Failure of one or more pressurizer safety valves.



THIRTY DAY WRITTEN REPORTS

6.9.1.13 The types of events listed below shall be the subject of written reports to the NRC Regional Administrator within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b. Conditions leading to operation in a degraded mode permitted by a Limiting Condition for Operation or plant shutdown required by a Limiting Condition for Operation.

c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d. Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.

HAZARDOUS CARGO TRAFFIC REPORT

6.9.1.14 Hazardous cargo traffic on Interstate 5 (1-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

SPECIAL REPORTS

6.9.2 Special reports shall be submitted to the NRC Regional Administrator within the time period specified for each report.

6.10 RECORD RETENTION

In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.



6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records .shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the unit staff.



h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA Manual. j. Records of reviews performed for changes made to procedures or

equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the OSRC and the NSG. 1. Records of the service lives of all snubbers within the scope of

Technical Specification 3/4.7.6 including the date at which the service life commences and associated installation and maintenance records.

m. Records of secondary water sampling and water quality. n. Records of reviews performed for changes made to the OFFSITE DOSE

CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA

6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

xHealth Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.



c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP)

6.13.1 The PCP shall be approved by the Commission prior to implementation.#

6.13.2 Licensee initiated changes to the PCP:

1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n.

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s);

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

c. Documentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.2.

2. Shall become effective upon review and acceptance pursuant to 6.5.2.

"xMeasurement made at 18" from source of radioactivity. #The PCP shall be submitted and approved prior to shipment of "wet" solid radioactive waste.



6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the 00CM:



b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.


2. Shall become effective upon review and acceptance pursuant to 6.5.2.

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the 00CM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.


THIS PAGE INTENTIONALLY LEFT BLANK


7.0 SPECIAL TEST PROGRAM

7.1 For conducting the natural circulation test program' the following Technical Specifications are exempt:

Technical Specifications Test Test Test

Section Description Bi B2 B3

3.4.1.2 Reactor Coolant System (1)(2) X X - Hot Standby

3.4.1.3 Reactor Coolant System (1)(2)(3) X - Hot Shutdown

3.7.1.3 Condensate Storage Tank X X X

NOTES: 1. No operations are permitted that would cause dilution of the Reactor Coolant System boron concentration.

2. Core outlet temperature is maintained at least 10oF below satura

tion temperature. 3. A Reactor Coolant pump shall not be started with one or more of

the Reactor Coolant System cold leg temperatures less than or

equal to 235 F unless the secondary water temperature of each steam generator is less than 100 F above each of the Reactor Coolant System cold leg temperatures.

* "Natural Circulation Test Program, San Onofre Nuclear Generating Station Unit 2, Safety Evaluation," CEN-201(S), April 1982.

JUL 25 8M SAN ONOFRE - UNIT 2 AMENDMENT NO. 20

7-1

ATTACHMENT B

EXISTING SPECIFICATIONS UNIT 3

Low Power

-12

E. SCE shall fully implement and maintain in effect all provisions of the Conission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan," with revisions submitted through April 22, 1988; "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and Qualification Plan," with revisions submitted through October 22, 1986; and "San Onofre Nuclear Generating Station, Units 1, 2, and 3, Safeguards Contingency Plan," with revisions submitted through December 29, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.


Before engaging in activities that may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evaluated in the Final Environmental Statement, SCE shall provide a written notification of such activities to the NRC Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities.

G. SCE shall report any violations of the requirements contained in Section 2, items C(l), C(3) through C(11), C(13) through C(22), E, and F of this license within 24 hours by telephone and confirm by telegram, mailgram, or facsimile transmission to the NRC Regional Administrator, Region-V, or his designee, no later than the first working day following the violation, with a written followup report within fourteen (14) days.


AMENDMENT NO. 58

INDEX

DEFINITIONS

SECTION PAGE

1.0 DEFINITIONS

1.1 ACTIONC..........................** **..................... 1-1 1.2 AXIAL SHAPE INDEX........................................... 1-1 1.3 AZIMUTHAL POWER TILT........................................ 1-1 1.4 CHANNEL CALIBRATION........ ............................. 1-1 1.5 CHANNEL CHECK.............. ............................ 1-1 1.6 CHANNEL FUNCTIONAL TEST....... ...................... 1-2 1.7 CONTAINMENT INTEGRITY..... .............................. 1-2 1.8 CONTROLLED LEAKAGE............ ............................ 1-2 1.9 CORE ALTERATION............................................. 1-2 1.10 DOSE EQUIVALENT 1-131....................................... 1-3 1.11 E-AVERAGE DISINTEGRATION ENERGY............................. 1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME.................... 1-3 1.13 FREQUENCY NOTATION...................................... 1-3 1.14 GASEOUS RADWASTE TREATMENT SYSTEM......................... 1-3 1.15 IDENTIFIED LEAKAGE.......................................... 1-3 1.16 OFFSITE DOSE CALCULATION MANUAL (00CM)...................... 1-4 1.17 OPERABLE - OPERABILITY...................................... 1-4 1.18 OPERATIONAL MODE - MODE..................................... 1-4 1.19 PHYSICS TESTS.............. ............................ 1-4 1.20 PLANAR RADIAL PEAKING FACTOR - F ......................... 1-4 1.21 PRESSURE BOUNDARY LEAKAGE................................... 1-4 1.22 PROCESS CONTROL PROGRAM (PCP)............................... 1-4 1.23 PURGE - PURGING............................................. 1-5 1.24 RATED THERMAL POWER..................................... 1-5 1.25 REACTOR TRIP SYSTEM RESPONSE TIME......................... 1-5 1.26 REPORTABLE OCCURRENCE.......................................... 1-5 1.27 SHUTDOWN MARGIN..... ...... . **** ** ..... .................. 1-5 1.28 SOFTWARE........... ................ 1-5 1.29 SOLIDIFICATION -* DELETED 1.30 SUC HC ....... 1.31 STAGGER TEST ASIS ....... 1-6 1.32 TEf ..... o 1.33 UIDETIFIED LEAKAGE ...... .......................................... 1-6 1. 34 VENTILATION EXHAUST TREATMENT SYSTEM .... 1-6 1.35 VE............... . 1-6

S....................... O1- 7

SAN ONOFRE-*UNIT 3 I AMENDMENT NO. 73

INDEX


SECTION PAGE

6.1 RESPONSIBILITY.................................... ....... 6-1

6.2 ORGANIZATION

6.2.1 OFFSITE.............................................. 6-1

6.2.2 UNIT STAFF........................................... 6-1

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP.................... .6-7

6.2.4 SHIFT TECHNICAL ADVISOR................................ 6-7

6.3 UNIT STAFF QUALIFICATIONS................................... 6-7

6.4 TRAINING.................................................. 6-8



FUNCTION.......................................... 6-8

COMPOSITION.......................................... 6-8

ALTERNATES....... .............................. .. 6-8 MEETING FREQUENCY........................... .... 6-9 QUORUM........ ............ ..................... .. 6-9

RESPONSIBILITIES............. .............. .... 6-9 AUTHORITY......................................... 6-9

RECORDS. .............. .......................... 6-10

6.5.2 TECHNICAL REVIEW AND CONTROL............................ 6-10


FUNCTION.......................................... 6-11

COMPOSITION. ....................................... 6-12

CONSULTANTS.......................................... 6-12

REVIEW............................................... 6-12

AUDITS................... ......................... 6-13

SAN ONOFRE-UNIT 3 XV NOV j

INDEX ADMINISTRATIVE CONTROLS

SECTION. PAGE

AUTHORITY.............................. 6-13 RECORDS.............................................. 6-13

6.6 REPORTABLE OCCURRENCE ACTION................................. 6-14

6.7 SAFETY LIMIT VIOLATION.................................. 6-14

6.8 PROCEDURES AND PROGRAMS............. .................. ... 6-14


6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.............. 6-18 STARTUP REPORT....................................... 6-18 ANNUAL REPORTS....................................... 6-19 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT... 6-20 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT....... 6-20 MONTHLY OPERATING REPORT........................... 6-20 REPORTABLE OCCURRENCES.................. ........... 6-21 PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP............ 6-21 THIRTY DAY WRITTEN REPORTS......................... 6-22 HAZARDOUS CARGO TRAFFIC REPORT...................... 6-23

6.9.2 SPECIAL REPORTS..................................... 6-23

6.10 RECORD RETENTION.............................................. 6-23

6.11 RADIATION PROTECTION PROGRAM ..................... . .. 6-24

6.12 HIGH RAIATION AREA, .......................................... 6-24

6.13 PROCESS CONTROL PROGRAM (PCP) ............................... 6-26

6.14 OFFSITE DOSE CALCULATION MANUAL........................... 6-26

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ** DELETED

SAN ONOFRE - UNIT 3 xvI AMENDMENT No. 73

INDEX

LIST OF FIGURES

FIGURE PAGE

3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION........ 3/4 1-13

3.1-2 CEA INSERTION LIMITS VS FRACTION OF ALLOWABLE THERMAL POWER.............................................. 3/4 1-24

3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON COLSS.............. 3/4 2-7

3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE)..................... 3/4 2-8

3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING...................... 3/4 3-40

4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA.................. 3/4 4-16

3.4-1 DOSE EQUIVALENT 1-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/GRAM DOSE EQUIVALENT 1-131.................... ........... 3/4 4-27

3.4-2 HEATUP RCS PRESSURE/TEMPERATURE LIMITATIONS FOR 0-5 YEARS.......................................... 3/4 4-30

3.4-3 COOLDOWN RCS PRESSURE/TEMPERATURE LIMITATIONS FOR 0-5 YEARS....................... ................... 3/4 4-30a

3.4-4 RCS PRESSURE/TEMPERATURE LIMITATIONS FOR 4-8 EFPY....... 3/4 4-31

3.4-5 RCS PRESSURE/TEMPERATURE LIMITS MAXIMUM ALLOWABLE COOLDOWN RATES (4-8 EFPY)............................. 3/4 4-31a

3.7-1 MINIMUM REQUIRED FEEDWATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO DATE......................... 3/4 7-7

5.1-1 EXCLUSION AREA....................... 5-2

5.1-2 LOW.POPULATION ZONE.............................. 5-3

5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS..................o 5-4

5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS...................... 5-5

5.6-1 UNITS 2 AND 3 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS.... ............... o ... 5-12

5.6-2 UNIT 1 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS....... ... ............ 5-13

5.6-3 FUEL STORAGE PATTERNS FOR REGION II RACKS........ ...... 5-14

SAN ONOFRE - UNIT 3 XVII AMENDMENT NO. 77

LIST OF FIGURES

FIGURE PAGE

5.6-4 FUEL STORAGE PATTERNS FOR REGION II RACKS RECONSTITUTION STATION............................... 5-15

6.2-1 OFFSITE ORGANIZATION.................................... 6-3

6.2-2 UNIT ORGANIZATION............ *....................... 6-4 6.2-3 CONTROL ROOM AREA................................... 6-6

SN W

SAN ONOFRE - UN4IT XVIIa AMENDMENT NO. 77

LIST OF TABLES

TABLE PAGE

4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.......................................... 3/4 7-9

3.7-5 SAFETY-RELATED SPRAY AND/OR SPRINKLER SYSTEMS............. 3/4 7-32

3.7-6 FIRE HOSE STATIONS........................................ 3/4 7-34

4.8-1 DIESEL GENERATOR TEST SCHEDULE......................... 3/4 8-7

4.8-2 BATTERY SURVEILLANCE REQUIREMENTS....................... 3/4 8-11

3.8-1 CONTAINMENT PENETRATIONt CONDUCTOR OVERCURRENT PROTECTIVE DEVICES..... ..... ................................ 3/4 8-18

3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES PERMANENTLY BYPASSED.............................. 3/4 8-32

4.11-1 RADIOACTIVE LIQUID SAMPLING AND ANALYSIS PROGRAM -- DELETED

4.11-2 RADIOACTIVE GASEOUS ASTE SAMPLING AND ANALYSIS PROGRAM -DELETED

3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -- DELETED

3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES -- DELETED

4.12-1 MAXIMUM VALVES FOR THE LOWER LIMITS OF DETECTION -- DELETED

83/4.4-1 REACTOR VESSEL TOUGHNESS.................................. 83/4 4-8

5.7-1 COMPONENT CYCLIC OR TRANSIENT LI ITS ....................... 5-8

6.2*1 MINIMNE SHIFT CREW COMPOSITION ............................. 6-5

SAN ONFRE UNIT 3 XX ANDMENT NO. 73

DEFINITIONS

PURGE - PURGING

1.23 PUKRE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER




REPORTABLE OCCURRENCE

1.26 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9.1.12 and 6.9.1.13.

SHUTDOWN MARGIN

1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming (1) all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fuily withdrawn, and (2) no change in part length control element assembly position.

SOFTWARE

1.28 The digital computer SOFTWARE for the reactor protection system shall be the program codes including'their associated data, documentation and procedures.

1.29 DELETED

SOURCE CEI

1.30 A 500 CH CK shall be the qualitative assessment of channel response when the dhInel snser is exposed to a radioactive source.

SAN ONFRE - UNIT 3 1-5 AMN2OENTNO. 73

SECTION 6.0



6.1 RESPONSIBILITY

6.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the Control Room Area, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION

OFFSITE


a. Lines of authority, responsibility, and comunication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR. b. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. c. The Vice President, Nuclear Engineering, Safety, and Licensing and the Vice President and Site Manager shall have corporate responsibility for overall plant nuclear safety. The Vice President and Site % r shall take any measures needed to ensure acceptable performWof the staff in operating and maintaining the plant to ensure ditii safety. The Vice President, Nuclear Engineering, Safety and Me-u ing shall take any measures needed to ensure acceptable performance of the staff in providing technical support to the plant to ensure nuclear safety.




UNITSTAFF

6.2-2 The Unit organization shall be as shown in Figure 6.2-2 and: a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room area identified as such on Table 6.2-1. c. Aehealth physics technician shall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited.to Fuel Handling who has no other concurrent responsibilities during this operation.

e. A-site Fire Bgigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Supervisor and the 2 other members of the minimum shift crew necessary . for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.


SAN ONOFRE-UNIT 3 6-la ApMMENT No. 57


UNIT STAFF (Continued)

f. Administrative procedures shall be developed.and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

1) An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time.

2) An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any 7-day period, all excluding shift turnover time.

3) A break of at least eight hours should be allowed between work periods, including shift turnover time.

4) Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Station Manager, his deputy, the Manager, Operations or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

9 .Ah Plant Superintendent (at time of appointment), the Assistant 4)gd Superintendent, Shift Superintendents and Control Room 4(prvisors shall hold a senior reactor operator license. The Centrol Operators and Assistant Control Operators shall hold a reactor operator license.



SAN ONOFRE-UNIT 3 6-3 AuENDENT No. 5 7

.. ,(This-pagt inten-tiofal.1y blank)

*A NFEUI. - MMETN.5

Table 6.2-1


WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED


MODES 1, 2, 3 4 MDES 5 & 6

SS Ia la sno .1 None R 2 AO 2 2 STA 1 None

40 IT UNIT 2 INMODES 1, 2 3 OR 4


MODES 1, 2, 3 &4 MODES 5 & 6

SS 1 1a

SRO a None RO 2 1 AD 2 b

STA l None

a/ Individual may fill the same position on Unit 2

b/ One of the two required individuals may fill the same position on Unit 2.

SS - Shift Supervisor with a Senior Reactor Operators License on Units 2 and 3

SRO - Individual with a Senior Reactor Operators License on Units 2 and 3 RO - Individual with a Reactor Operators License on Units 2 and 3 AO - Auxiliary Operator STA * Shift Technical Advisor

-Except few the Shift Supervisor, the Shift Crew Composition may be one less than the mladow requirements of Table 6.2-1 for a period of time not to exceed 2 "., to accommodate unexpected absence of on-duty shift crew mebersimmediate action is taken to restore the Shift Crew Composition to thaa the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control-Rogm- Area shown in Figure 6.2-3 while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Ce'ntrol Room command function. During any absence of the Shift Supervisor from the Control Room Area shown in Figure 6.2-3 while the unit is in MODE 5 or 67 an individual with a valid SRO.or RO license shall be designated to assume the Control Room command function.

SAN ONDFRE-UNIT 3 6-5

30 -4

I II

1

g I 1111111T

Control Roo

77tm Uit 2 Uni t 3

f ftce

Figure 6.2-3

CONTROL ROON AREA

SAN ONOFRE NUCLEAR GENERATING STATION - UNIT 3


6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) FUNCTION


COMPOSITION


RESPONSIBILITIES

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification* that these activities are performed correctly and that human errors are reduced as much as practical. AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to offsite organization management. RECORDS

6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to offsite organization management. 6.2.4 SHIFT TECHNICAL ADVISOR

The Shift Technical Advisor shall provide technical support to the Shift Supervisor to the areas of thermal hydraulics, reactor engineering and plant analysis wt regard to the safe operation of the unit. The Shift Technical Advisor sheamwee a Bachelor's Degree or equivalent in a scientific or engineering (fatpline with specific training in plant design and in the response aWs slysis of the plant for transients and accidents. 6.3 UNIT STAFF QUALIFICATIONS


Not responsible for sign-off function.



6.4 TRAINING.

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training and shall meet or exceed the requirements and recomendations of Sections 5.5 of

-ANSI N18.1-1971 and Appendix NA" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.



FUNCTION

6.5.1.1 The Onsite Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.

COMPOSITION


Chairman: Station Manager Member: Deputy-Station Manager Member: Manager, Operations Member: Manager, Technical Member: Plant Superintendent SONGS Units 2 and 3 Member: Supervisor of I&C Member: Manager, Health Physics Member: Supervisor of Chemistry Member: Manager, Maintenance Member: Supervising Engineer (NSSS, NSSS Support,

Computer, or STA) Member: San Diego gas &(e ctric Representative,

Senior Engineer

6.5.1.3 al-4-ternate meers shall be appointed in writing by the OSRC Chairmen serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSRC activities at any one time.

degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of the four years experience shall be nuclear power plant experience.

SAN OMOFRE-UNIT 3 6-8


MEETING FREQUENCY


QUORUM


RESPONSIBILITIES


a. Investigation of all violations of the Technical Specifications tncluding the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).

b. Review of events requiring 24-hour written notification to the Commission.


d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the NSG.


AUTHORITY


a. Render determinations in writing with regard to whether or not items ceasidered under 6.5.1.6(a) above constitute unreviewed safety questions.

b. e&vide written notification within 24 hours to the Manager of Nuclear UVpaations and NSG of disagreement between the OSRC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.



RECORDS

6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Nuclear Safety Group.


ACTIVITIES

6.5.2.1 The Station Manager shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual/organization. Each such procedure, and changes thereto,.shall be reviewed by an individual/group

nothe than the individual/group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.

6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall be prepared by a qualified individual/organization. The preparation of each proposed Technical Specifications change shall be reviewed by an individual/ group other than the individual/group which prepared the proposed change, but who may be from the same organization as the individual/group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by. the Station Manager.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/ organization.. Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Manager.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1. 6.5.2.2 and 6.5.2.3 shall be members of the station supervisory staff, wesly designated by the Station Manager to perform such reviews. Each es shall include a determination of whether or not additional, cross lnary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, the Manager, Technical, the Manager,-Operations, the Manager, Maintenance, the Deputy Station Manager or the Manager, Health Physics as previously designated by the Station Manager.

6.5.2.6 The station security program, and implementing procedures, shall be reviewed at least-once per 12 months. Recommended changes shall be approved by the Station Manager and transmitted to the anager of Nuclear Operations and to the NSG.

NOV 1 5 1982 SAN ONOFRE-UNIT 3 6-10



6.5.2.7 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months. Recomended changes shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the NSG.

6.5.2.8 The Station Manager shall assure the performance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and eforwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager of Nuclear Operations and to the NSG.

6.5.2.9 The Station Manager shall asSure the performance of a review by a qualified individual/arganization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

6.5.2.10 Reports documenting each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Nuclear Safety Group.


FUNCTION




c.. chemistry and radiochemistry

d. mtallurg

e.Attrumntation and control

f.. ' elogical safety


h. quality assurance practices.

NOV 1 5 1982

SAN ONOFRE-UNIT 3 6-11


COMPOSITTIot

6.5.3.2 NSG shall consist of a Supervisor and at least three staff specialists. The Supervisor shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of 6 years of professional level managerial experience in the power field. Each staff specialist shall have a Bachelor's Degree in Engineering or Physical Science and a minim of 5 years of professional level experience in the field of his specialty.

The NSG shall use specialists from other technical organizations to augment its--expertise in the disciptines of 6.5.2.1. Such specialists shall meet the same qualification requirements as the NSG members.

CONSULTANTS 6.5.3.3 Consultants. shall be util ized as determined by the NSG Supervisor to provide expert advice to the NSG.

REVIEW 6.5.3.4 The NSG shall review:

a. The safety evaluations for 1) changes to procedures required by Specification 6.8, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions, did not constitute an unreviewed safety question.




e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormlities or deviations from normal and eq~ected performance of unit equipment that affect nuclear safety.

g. Events requiring 24 hour written notification to the Commission.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

I. Reports and meetings minutes of the Onsite Review Committee.

NOV 1 5 1982 SAN ONOFRE-UNIT 3 6-12


AUDITS

6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG. These audits shall encompass:

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.


c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program- to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. Any other area of unit operation considered appropriate by the Nuclear Safety Group or Manager of Nuclear Operations.

f. The Fire Protection Program and implementing procedures at least once per 24 months.

g. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm. h. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

AUTHORITY

6.5.3.6 The NSG shalT report to and advise offsite organization management on those areas of responsibility specified in Sections 6.5.3.4 and 6.5.3.5. RECORDS

6.5.3.7 of NSG activities shall be prepared and maintained. Report of revieWs auits shall be distributed monthly to the Station Manager and to the managiment positions responsible for the areas audited.

SAN ONOFRE-UNIT 3 6-13 AMENOMENT NO. 57


6.6 REPORTABLE OCCURRENCE ACTION.

6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviewed by the OSRC and submitted to the NSG and the Manager of Nuclear Operations.



a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager of Nuclear Operations and the NSG Chairman shall be notified within 24 hours.


c. The Safety Limit Violation Report shall be submitted to the Commission, the Manager of Nuclear Operations and the NSG within 14 days of the violation.

d. Critical operation of the unit shall not be resumed until authorized by the Commission.



a The applicable procedures recomended in Appendix "A" of Regulatory Avide 1.33, Revision 2, February 1978.

b. Aefueling operations.

c. Surveillance-end-test activities of safety related equipment.




S N F6 5 19 2 SAN ONOFRE-UNIT 3 6-14-



g. PROCESS CONTROL PROGRAM implementation.*


i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15 Rev. 1, February 1979.



6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the Station Manager; or by (1) the Deputy Station Manager, (2) the Manager, Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager, Health Physics as previously.designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed and approved by the Station Manager; or by (1) the Deputy Station Manager, (2) the Manager, Operations, (3) the Manager, Maintenance, (4) the Manager, Technical,

.w (5) the Manager, Health Physics as previously designated by the Station Manager; within 14 days of implementation.

6.8.4 T following progras shall be established, implemented, and maintained: a. Primary Coolant Sources Outside Containment

A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a




serious transient or accident to as low as practical levels. The systems include the high pressure safety injection recirculation, the shutdown cooling system, the reactor coolant sampling system (post-accident sampling piping only), the containment spray system, the radioactive waste gas system (post-accident sampling return piping only) and the liquid radwaste system (post-accident sampling return piping only). The program shall include the following:

(i) Preventive maintenance and periodic visual inspection requirements, and.


*See Specification 6.13.1

SAN ONOFRE-UNIT .3 6-15a AMENDMENT NO. 36



A.program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and




(i) Identification of a sampling schedule for the critical variables and control points for these variables,:

(ii) Identification of the procedures used to measure the values of the critical variables,

(iii) Identification of process sampling points, including monitoring. the discharge of the condensate pumps for evidence of condenser' in-leakage,

(iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control

point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the

interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.


A programs which will ensure the capability to obtain and analyze reactor coolant, radioactive todines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The proqram* shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

e. -1=oactive Effluent Controls Program

kprogram shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by operating procedures, and (3)

*Not required to be implemented until September 1, 1983.




shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the 00CM;

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix 8, Table II, Column 2;

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the 00CK;

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50;

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, respectively, in accordance with the methodology and parameters in the 00CM at least every 31 days;

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conform to Appendix I to 10 CFR Part 50;

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix 8, Table II, Column 1.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit toAeent beyond the SITE BOUNDARY conforming to Appendix I to IW~CFR Part 50,

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,






A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the 00CM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring,. sampling, analysis, and reporting of radiation and radionucltdes in the environment in accordance with the methodology and parameters in the 00CM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modificatibns to the monitoring program are made if required by the results of this census, and



ROUTINE REPORTS AND REPORTASLE OCCURRENCES

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC Regional Administrator unless otherwise noted.

STARU

6.9.1.1 ry report of plant startup and power escalation testing shall be submi following (1) receipt of an operating license, (2) amendment to the licenst involving a-planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.



6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program.and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.


ANNUAL REPORTS*

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated manrem exposure according to work and job functions," e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. Inthe aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

Reports required on an annual basis shall include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 1-4.7. The following information shall be included in these reports: (1) Reac gener history starting 48 hours prior to the first sample in which the limi exceeded; (2) Results of the last isotopic analysis for radioiodine permed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiolodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Cleanup system flow history starting

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station. This tabulation supplements the requirements of 120.407 of 10 CFR Part 20.

SAN ON0FRE-UNIT 3 6-19 AMENOMENT NO. 73


48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT'

6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the 00CM and (2) Sections IV.B.2, IV.8.3, and IV.C of Appendix I to 10 CFR Part 50.

&.9.1.7 - DELETED


6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the 00CM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.8.1 of Appendix I to 10 CFR Part 50.

6.9.1.9 -- DELETED


6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of ResourceiManagement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no .later than the 15th of each month following the calendar month covered by the report.

Any cha t1 the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly ing Report within 90 days in which the change(s) was made effective. 1ion, a report of any major changes to the radioactive waste treatment systems shall-be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted in accordance with 6.5.2.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.




6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, includingtcorrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP

6.9.1.12 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Regional Administrator of the Regional Office or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup. report shall include, as a minimum, a completed copy of a. licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Failure of the reactor protection system or other systems subject to' limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technical specifications or.failure to complete the required protective function.

b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the Limiting Condition for Operation established in the Technical Specifications.

c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

d. Reactivity anomalies involving disagreement with the predicted value. of reactivity balance under steady-state conditions during power operation greater than or equal to 15 AW/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified

Technical Specifications; short-ter reactivity increases correspond to a reactor period of less than 5 seconds or, if Ctical, an unplanned reactivity insertion of more than 0.5% Ak/k;

or occurrence of any unplanned criticality. e. Failure or malfunction of one or more components which prevents or

could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR.

f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements

- of systems required to cope with accidents analyzed in the SAR.



g. Conditions arising from natural or man-made events- that,-as--a-di-rect result of the event, require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifications.

h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

i. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or discovery during unit life.of conditions not specifically considered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

j. Offsite releases of radioactive materials in liquid and gaseous effluents that exceed the limits of Specifications 3.11.1.1 or 3. 11. 2. 1.

k. Exceeding the limits in Specification 3.11.1.4 or 3.11.2.6 for the storage of radioactive.materials in the listed tanks. The written follow-up report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

1. Failure of one or more pressurizer safety valves.

THIRTY DAY WRITTEN REPORTS

6.9.1.13 The types of events listed below shall be the subject of written reports to the NRC Regional Administrator within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report fore. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. - r protection system or engineered safety feature instrument ngs which are found to be less conservative than those estab

by the Technical Specifications but which do not prevent the fillment of the functional requirements of affected systems.

b. Conditions leading to operation in a degraded mode permitted by a Limiting Condition for Operation or plant shutdown required by a Limiting Condition for Operation.

c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

SAN ONOFRE-UNIT 3 6-22 AMENOMENT NO. 73


d. Abnormal degradation of systems other than those specified in 6.9.1.1Zc above designed to contain radioactive material resulting from the fission process.



SPECIAL REPORTS

6.9.2 Special reports shall be submitted to the NRC Regional Administrator within the time period specified for each report.






c. All REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e. foards of changes mede to the procedures required by ptification 6.8.1.

f. *ards of radioactive shipments.



6.10.2 The following records shall be retained for the duration of the Unit Operating License:











i. Records of Quality Assurance activities required by the QA Manual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the OSRC and the NSG.

1. Records of the service lives of all snubbers within the scope of Technical Specification 3/4.7.6 including the date at which the service life commences and associated installation and maintenance records.

m. Records of secondary water sampling and water quality.

n. Records of reviews performed for changes made to the OFFSITE DOSE (TI MANUAL and the PROCESS CONTROL PROGRAM.

6.11 PROTECTION PROGRAM

Procedures for personnel-radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.


6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the

SAN ONOFRE-UNIT 3 6-24 AMENDMENT No. 73


intensity of radiation is greater than 100 mres/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requirfng issuance of a Radiation Exposure Permit (REP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:



c. An individual qualified in radiation protection procedures who is equipped wtth a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose.greater than 1000 mreu shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified is radiation protection procedures to provide positive exposure control ~-the activities within the area.

*Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.

**Measurement made at 18" from source of radioactivity.

SAN ONOFRE-UNIT 3 6-25 AMENDuENT No. 73



6.13.1 The PCP shall be approved by the Commission prior to implementation.# 6.13.2 Licensee initiated changes to the PCP:



b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.


2. Shall become effective upont review and acceptance pursuant to 6.5.2.

6.14 OFFSITE DOSE CALCULATION MANUAL (00CM)

6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the 00CM:



b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix. I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.


2. Shall become effective upon review and acceptance pursuant to 6.5.2. 3. 1 be Submitted to the Commission in the form of a complete,

lZwe copy of the entire 00CM as a part of or concurrent with the 1 Radioactive Effluent Release Report for the period of the

in which any change to the 00CH was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS. DELETED

#The PCP shall be submitted and approved prior to shipment of "wet" solid radioactive waste.

SAN ONOFRE-UNIT 3 6-26 AMENOMENT No. 73

ATTACHMENT C

PROPOSED SPECIFICATIONS UNIT 2

Low Power

-7

(18) Initial Test Program (Section 14, SER)

SCE shall conduct the post-fuel loading initial test program (set forth in Section 14 of the San Onofre Units 2 and 3 Final Safety Analysis Report, as amended) without making any major modifications to this program unless such modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of the Final Safety Analysis Report, as amended, as being essential.

b. Modification of test objectives, methods, or acceptance criteria for any test identified in Section 14 of the Final Safety Analysis Report, as amended, as being essential.

c. Performance of any test at a power level different than that described in the test procedure.

d. Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized power level).

(19) NUREG-0737 Conditions (Section 22)

Each of the following conditions shall be completed to the satisfaction of the NRC. Each item references the related subpart of Section 22 of the SER and/or its supplements.

a. DELETED

b. Shift Manning (I.A.1.3. SSER #1. SSER #5)

SCE shall develop and implement administrative procedures to limit the working hours of individuals of the nuclear power plant operating staff who are responsible for manipulating plant controls or for adjusting on-line systems and equipment affecting plant safety which would have an immediate impact on public health and safety.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

Corrected Page Low Power

-8

1. An individual shall not be permitted to work more than 16 hours straight (excluding.shift turnover time).

2. An individual shall not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any seven day period (all excluding shift turnover time).

3. A break of at least eight hours shall be allowed between work periods (including shift turnover time).

4. The use of overtime shall be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the station manager, his deputy, the operations manager, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the station manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

c. DELETED

d. Procedures for Transients and Accidents (I.C.1, SSER #1, SSER #2. SSER #5)

By May 1, 1982, SCE shall provide emergency procedure guidelines. Emergency procedures based on guidelines approved by the NRC shall be implemented prior to startup following the first refueling outage.

e. Procedures for Verifying Correct Performance of Operating Activities (I.C.6, SSER #1)

Prior to fuel loading, SCE shall implement a system for verifying the correct performance of operating activities, and shall keep the system in effect thereafter.

f. Control Room Design Review (I.D.1, SSER #1)

Prior to exceeding five (5) percent power, SCE shall:

1. Prioritize the control room annunciator windows.

Low Power

-13

D. Exemptions to certain requirements of Appendices G, H and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission.

E. SCE shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans including their latest r.evisions, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan," with rcvsies-submitted through Aprl 22-, 1988 "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and Qualification Plan," with risiens-submitted through Oetebe- 22, 1986; and "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Safeguards Contingency Plan.," with -Powsions submitted through December 29, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.




AMENDMENT NO.

INDEX

DEFINITIONS SECTION PAGE

1.0 DEFINITIONS

1.1 ACTION...............................................................1-1 1.2 AXIAL SHAPE INDEX....................................................1-1 1.3 AZIMUTHAL POWER TILT.................................................1-1 1.4 CHANNEL CALIBRATION..................................................1-1 1.5 CHANNEL CHECK........................................................1-1 1.6 CHANNEL FUNCTIONAL TEST..............................................1-2 1.7 CONTAINMENT INTEGRITY................................................1-2 1.8 CONTROLLED LEAKAGE...................................................1-2 1.9 CORE ALTERATION......................................................1-2 1.10 DOSE EQUIVALENT 1-131................................................1-3 1.11 E-AVERAGE DISINTEGRATION ENERGY......................................1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME.............................1-3 1.13 FREQUENCY NOTATION...................................................1-3 1.14 GASEOUS RADWASTE TREATMENT SYSTEM....................................1-3 1.15 IDENTIFIED LEAKAGE...................................................1-3 1.16 OFFSITE DOSE CALCULATION MANUAL (ODCM)...............................1-4 1.17 OPERABLE - OPERABILITY.... ...................................... 1-4

1.18 OPERATIONAL MODE - MODE..............................................1-4 1.19 PHYSICS TESTS................ .................................. 1-4 1.20 PLANAR RADIAL PEAKING FACTOR - F ....... ..........-......... 4 1.21 PRESSURE BOUNDARY LEAKAGE.......................................1-4 1.22 PROCESS CONTROL PROGRAM (PCP)................................ ........ 1-4 1.23 PURGE-PURGING........................................................1-5 1.24 RATED THERMAL POWER..................1-5 1.25 REACTOR TRIP SYSTEM RESPONSE TIME.................................1-5 1.26 REPORTABLE OGCURRENG EVENT.......................... ............ 1-5 1.27 SHUTDOWN MARGIN................................................1-5 1.28 SOFTWARE........................................................1-5 1.29 SOLIDIFICATION -- DELETED

1.30 SOURCE CHECK... ....................................... ...... 1-5 1.31 STAGGERED TEST BASIS..... ....................................... 1-6

1.32 THERMAL POWER........ ......... 1................................1M6

1.33 UNIDENTIFIED LEAKAGE.............................................1-6 1.34 VENTILATION EXHAUST TREATMENT SYSTEM..............................1-6 1.35 VENTING ........................................................ 1-6

SAN ONOFRE - UNIT 2 T AMENDMENT NO.

INDEX


SECTION PAGE

6.1 RESPONSIBILITY .............................................. 6-1

6.2 ORGANIZATION

6.2.1 OFFSITE ANDON ITE......AT . . . ........................ 6-1

6.2.2 UNIT STAFF ................................................. 6-1 Z 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP ........................ 6-...

6.2.4 SHIFT TECHNICAL ADVISOR....................................6-8

6.3 UNIT STAFF QUALIFICATIONS ..................................... 6-..

6.4 TRAINING ............... ......................................



FUNCTION.................................................. 6

COMPOSITION .............................................. 6- .9

ALTERNATES .............................. ................ 6-&'9

MEETING FREQUENCY ........................................ 6-7 10

QUORUM ................................................... 6-710

RESPONSIBILITIES ......................................... 6-7 1

AUTHORITY ................................................ 6-8 10

RECORDS .................................................. 6- . 11

6.5.2 TECHNICAL REVIEW AND CONTROL ................................. 6-8 11 6.5.3 NUCLEAR SAFETY GROUP

FUNCTION .................................................

COMPOSITION .............................................. 6--0 13

CONSULTANTS .............................................. 6--014

REVIEW ................................................... 6-1- 14

AUDITS ................................................... 6-11-15

SAN ONOFRE-UNIT 2 XVI AMENDMENT NO.

INDEX


SECTION PAGE

AUTHORITY...6-1..........................................6.2 15

RECORDS............ 6-1. 1

6.6 REPORTABLE URRENGE ACTION........... ............ 6-. 16

6.7 SAFETY LIMIT VIOLATION...........6-1 15

6.8 PROCEDURES AND PROGRAMS.......6-...16....................6- ...


6.9.1 ROUTINE REPORTS AND-REORBLE OCCURRENCES...........6........6-164" 21

STARTUP REPORT...1.......

ANNUAL REPORTS.. ....................................... 1 22 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT........ 6-1- 23 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT........... 6-1. 23

MONTHLY OPERATING REPORT...6-17.23

6.. PCEDREORAE P OCRE.......................................6 6-1 ..24

PROMP NOTIICATON WIH WRTTEN OLLOUP.............6.1

6.10ECODRTYNTYONR................................6- 2

6.9.1 OHAZAERDOS CARGOETRAFFIC EREPORT.............. ............ 6- 24

6.9.2 SCIAL REPORT...........................................622

6.10UA REODREENTOS............................................ 6-2 4

6.11 RADIATION PROTECTION PROGRAM.................................6-2226

6.12 HIGH RADIATION AREA........................................... 6-226

6.13 PROCESS CONTROL PROGRAM (PCP)................................ 6-2327

6.14 OFFSITE DOSE CALCULATION MANUAL...............................6-428

65NROH N TFRAIONCT WRSTEN -INTT.TTMT A D N

SAN1 NREATO PROUNI T IO RGA XVII....AMENDMENT.......NO.

INDEX

LIST OF TABLES

TABLE PAGE

4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...............................3/4 7-8

.SNUBE ISUAL INSPETIZON INTERVAL.. *... . . 3/4 7-16a

3.7-5 SAFETY-RELATED SPRAY AND/OR SPRINKLER SYSTEMS.............3/4 7-31

3.7-6 FIRE HOSE STATIONS....................................3/4 7-33

4.8-1 DIESEL GENERATOR TEST SCHEDULE.........................3/4 8-7

4.8-2 BATTERY SURVEILLANCE REQUIREMENTS......................3/4 8-11

3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES....................................3/4 8-18

3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS'DEVICES.......................................3/4 8-32

O3.10 1 RADIATION MONITORING,'SAMPLING EXCEPTIONS DELETED

4.11 1 RADIOACTIVE LIQUID WASTESAMPLING AND ANALYS-S PROGRAM DELETED

4.11 2 RADIOACTIVE GASEOU ASE SAMPLING AND ANALYSI PROGRAM DELETED

3.12 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DELETE

3.12 2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES DELETED

4.12 1 MAXIMUM VALUES FOR THE LOWER-LIMITS OF DETECTION (LLD) DELETE

B 3/4.4-1 REACTOR VESSEL TOUGHNESS................................ B 3/4 4-8

5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS....................5-8

6.2-1 MINIMUM SHIFT CREW COMPOSITION.........................6-45

SAN ONOFRE-UNIT 2 XX AMENDMENT NO.

INDEX

LIST OF FIGURES

FIGURES PAGE

3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURES AS A FUNCTION OF STORED BORIC ACID CONCENTRATION........... 3/4 1-13

3.1-2 CEA INSERTION LIMITS.................................... 3/4 1-24

3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON COLSS.................. 3/4 2-7

3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE) ........................ 3/4 2-8

3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING......................... 3/4 3-40

4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA.................... 3/4 4-15a

3.4-1 DOSE EQUIVALENT 1-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT.......................................... 3/4 4-26

3.4-2 RCS HEATUP PRESSURE/TEMPERATURE LIMITATIONS FOR 4-8 EFPY............................................ 3/4 4-29

3.4-3 RCS COOLDOWN PRESSURE/TEMPERATURE LIMITATIONS FOR 4-8 EFPY............................................... 3/4 4-30

3.7-1 MINIMUM REQUIRED FEEDWATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO DATE............... 3/4 7-6A

5.1-1 EXCLUSION AREA .......................................... 5-2

5.1-2 LOW POPULATION ZONE..................................... 5-3

5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS....................... 5-4

5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS........................ 5-5

SAN ONOFRE-UNIT 2 XXI AMENDMENT NO.

5.6-1 UNITS 2 & 3 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION III RACKS--.....................5-12

5.6-2 UNIT 1 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT. FOR REGION II RACKS.... . ......... .......... 5-13

5.6-3 FUEL STORAGE PATTERNS FOR REGION II RACKS............ 5-14

5.6-4 FUEL STORAGE PATTERNS FOR REGION II RACKS RECONSTITUTION STATION. .............. 5

6.2 1 OFFITE ORG lZ.TION . .. 2

6.2-3 CONTROL ROOM AREA....... ....................... 6-4a 7

SAN ON0FRE-UJNIT 2 XXII AMEDMENT NO~

DEFINITIONS

PURGE - PURGING


RATED THERMAL POWER



1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall .be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE OCCURRENCE EVENT

1.26 A REPORTABLE OCCURRENGEtEN shall be any of those conditions specified in Speeif4at-n- 6.9.1S.12net 5073 to 10 CFR. Part 50.

SHUTDOWN MARGIN

1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present conditiOn assuming (1) all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn, an.d (2) no change in part length control element assembly position.

SOFTWARE


1.29 DELETED

SOURCE CHECK


SAN ONOFRE-UNIT 2 1-5 AMENDMENT NO.

SECTION 6.0



6.1 RESPONSIBILITY

6.1.1 The Station Manager Vice President and site Manaerr iuclear Gnation Site shall be responsible for overall unit operation and maintenance of Units.2

nd 3 at Sa~ Qake Nuclear Generating Site, *nd all site support fuorctios. e shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift-Sepervisee Superintendent (or during his absenee from the Gentroel Room Area, a dezinatd individual) shall be responsible for the GentFe1 ieem ultinat* command fewetien d cision authority for al unit activitis and operations whch affect the safety of the plant, sIte personnel. an/ ... the. gnal public. A management directive to this effect, signed by the.Vice. President opnNudl ar Operationz;nd i I .Gene ation Site shall be reissued to all site/station personnel on an annual basis.

6 .. The Control Room Supervisor (or during his absence from th eeCotrol Room Area1, a designated individual vith a valid SRO license) shall be responsible for the Control Ro.m com.and function. The Control toom Sup r huld a.ly be la the Contro Rooma and shallI be within the Control Room Area defi ned by.

6.2 ORGANIZATION

OFFSITE AND ON4SITE ORGANIZATroN



- b. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The ($i5 Vice President, NuclerEngieering,-Safety,-and Licensing and th Vi1ce President and Site Manager,. Nuclear Generation Site shall have corporate responsibility for overall plant nuclear safety. The Vice President and Site Manager. Nuclear Generation Site shall take any measures needed to ensure acceptable performance of the staff in operating and maintaining the plant to ensure nuclear safety. The Senior Vice President,-Nuclear-Engineering,-Safety-and-L4censing shall take any measures needed to ensure acceptable performance of the staff in providing technical support to the plant to ensure nuclear safety.

SAN ON0FRE-UNIT 2 6-1 AMENDMENT NO.



UNIT STAFF


b. At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room area identified as such on Table 6.2-1.

c. A health physics technician' shall be on site when fuel is in the reactor.


e. A site Fire Brigade of at least 5 members shall be maintained on site at all times.' The Fire Brigade shall not include the Shift Supe.*i-s Superintendent and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

f. Reserved.

NOTE: T.IS SPACE I RESERVED FOR UPCOMING CAGES TO SECTION 6....2.


SAN ONOFRE-UNIT 2 6-41a2 AMENDMENT NO.

(This pagl intcntionally bManIT

SAN ONOFRE UNIT 2 6 3 AMENDMENT NO. 68

(Thit pge intCntionaliy blanM

SAN ONOFRE UNIT 26 2 AMENDMENT NO. 63


WWNITAFF (Continued)

NOTtt THIS SPACE IS RESERVED FOR UPCOMING CHANGES TO SECTIOI 6L2 4 2S

SAK ONOFRE-UNIT 2 3AMENOM4ER N


UNITi::R SERV(tntE~e

g. The Plant Superintendent (at time-of appointment), t Ae Ass.i..tant..

P......t Su....i.t......t.Oper.ti.....Shift Superintende"nts""**" " an Cnrol I Room. Spervisors shal hol a senior fteactor operator t license.

The Control Operators and Assistant Control Operators. s hai ll" hold a fteactor eqpeatr: ii1 ce n se orSno eacto Qprtot -iense

... ONO RE- tI ........... WT NO...f

Table 6.2-1




MODES 1. 2. 3 & 4 MODES 5 & 6

SS 1a 1V SU0CRS 1 None RO COIACO 2 1 AO PEQ 2 2 STA 1 None

WITH UNIT 3 IN MODE 1. 2. 3 or 4


MODES 1. 2. 3 & 4 MODES 5 & 6

SS la la SG CR*s 1a None RO CO/ACO 2b AN.PEO 2b 1 STA la None

a Individual may fill the same position on Unit 3. b One of the two required individuals may fill the same position on Unit 3

SS - Shift Supervyse Superintendent with a Senior Reactor Operator s license on San Onofre Units2and 3

SRO CRS - IRiideda-l Cointrol Roseu Supervisor with a Senior Reactor Operator's

..icense on San Onfre Units and 3

CO/ACO- Ind4i-v44ii&l contro operator/Asistant control operator with a Reactor ...... .Operatos l icense or a Senior Reactor Operators license on S Units 2 and 3

AG NPED - Auxil.ry-Operator Nuclear Plat Equipment operator (Reactor Operator

license not required)

STA - Shift Technical Advisor

. SAN ON0FRE-UNIT 2 6--4-S AMENDMENT NO.

AD?44I STRATI E CONTROLS

OMII4NUM SHIFT CREW (OPSTO (Continued)

Except for the Shift Speri"ise~ Super'intendent, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the S-ift~ Control Room Supervisor from the Control Room Area shown in Figure 6.2-3 while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function. During any absence of the Shi.t Control Room Supervisor from the Control Room Area shown in Figure 6.2-3 while the unit is in MODE 5 or 6, an individual with a valid SRO or RO license shall be designated to assume the Control Room command function.

.... .. ... .. ........... .. .... ..6 -........

V)

C

U~uH U U U U U U

rn

-I__I _____O_1

CONTROL ROOM

UNIT 2 NIT 3

II co0 0 0DE

Supt. UNIT 2 Office UNIT 3

Computer Room Turbine Lab Computer Room

rOn

Support Office

Figure 6.2-3: alI

CONTROL ROOM AREA

I> SAN ONOFRE GENERATING STATION - UNITS 2 & 3

blchen Lockers

M Lunch Rm.


6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION


COMPOSITION


RESPONSIBILITIES

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification* that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY

6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to offsite organization management.

RECORDS


6.2.4. SHIFT TECHNICAL ADVISOR

The Shift Technical Advisor shall provide technical support to the Shift Supern4se in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit. The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents.

6.3 UNIT STAFF QUALIFICATIONS


* Not responsible for sign-off function.

SAN ONOFRE-UNIT 2 6-6- 8 AMENDMENT NO.


6.4 TRAINING

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training and shall meet or exceed the requirements and recommendations of Sections 5.5 of ANSI N18.1-1971 and Appendik "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.

5.. A training program for the Fire brigadie shall be maintained by the direction of the danager. Site Eegn Preard.s..dshall meet or exceed the requi rements of National Fire Proteton Association .Stan~dard No. 27-I17.



FUNCTION


COMPOSITION . 6.5.1.2 The Onsite Review Committee shall be composed of the:

Chairman: Stto Mage Member: Dpt tto aae Member: MaaeOetin Member: Mngr ehia Member: PatSprnedn OG nt Member: SuevsroIC Member: MaaeHat Phsc Member:.................Che is

.Member:. ....

Member: Mngr aneac

Member:to Managerevsn Enier(SNS uprt

Maer, e-.~Tenclea.yte~E~ erig icr

Syst ~ ~ ~ ~ ~ ..... ..ier n.o .~~rto

Member: Plant Spe int.edetSONG Uernt tv 2no

6.5.13 AllIT atRnateW CMME (shalb ppitdiwiigbyte R

Charma toseve n atperiorr bais;hwvr&C oeta woatrae

shall1Th partiite asevoing Cmmbttesh inunC ctivi te atvanyoe Sttie. (1)anag er e Engern ot Physic S n ps at la r sy

exp1. Teieni RveCmite shall be nucleard powe plntexerene

SANp NF UT6er, - a ChemistryO

Memer: Manager, MTenanc

Membr: lan Suprinendnt SNGSUnis 2& 3

MeanagSuersuprvsn Enine (NSI-S-epoe Gempr:eanaer -ea-ltA Nuyscrs tsEnierglctca

Mme: Suyse EnieerKing orePowerynra n Member: SanaDiego as & El *ect RepresentaiveSenio

Memer ig nEngineer, SS Spprt

Chima osev o epory asis however, no.. mors**e than two alternates'*

shall participate as voting members in OSRC activities at any one time.

SBS degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of the four years experience shall be nuclear power plant experience.

SAN ONOFRE-UNIT 2 6--9AMENDMENT NO.


MEETING FREQUENCY


QUORUM


RESPONSIBILITIES



b. Review of eventsR all EPOTABLE EVENTS. -4quirin 24-heur-ritten noat if iceatin to thA- ~ m~o


d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the NSG Supervis.. r.


AUTHORITY


a. Render determinations in writing with regard to whether or not items considered under 6.5.1.6j.a} above constitute unreviewed safety questions.

b. Provide written notification within 24 hours to the Managro- f Nuelear Opeva~t--e Vice President and Site ManagerNuc.ear Generation site and the NSG Supervisor of disagreementbetween the.OSRC and the Station Manager; however, the Stat4en ManagesVice.President and Site Manager, Nuclear Generation Site shall have responsibil1ty'for resolution of such disagreemiens pursuant to 6.1.1 above.

SAN ONOFRE-UNIT 2 6-7-10 AMENDMENT NO.


RECORDS

6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these 4Technical specifications. Copies shall be provided to the Nuclear Safety Group


ACTIVITIES

6.5.2.1 The Stat4en Manager Vice President and Site Manager. Nuclear Gen.eration Site shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual/organization. Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto. Documentation of these activities shall be provi ded to the NS56 Supervisor. 6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall be . prepared by a qualified individual/organization. The preparation of each proposed Technical Specifications change shall be reviewed by an individual/ group other than the individual/group which prepared the proposed change, but who may be from the same organization as the individual/group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the Station Manager. Dcumentation of these activities shall be provi ded to the Vice President and Site Manager, Nuclear Gener'ation Site and to

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/ organization. Each such modification shall be reviewed byan individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Staties Maftageir Vice' President and Site Manager, NuclIear Generati on Site. Documentati on of these adtiviti es shallI be provi ded to the Vice President and Site Manager, Nuclear Generation Site and to the N5G Supervisor.

SAN ONOFRE-UNIT 2 6-8-H11il AMENDMENT NO.



6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the stat4on superv4sery nuclea divi stoo nmanagement staff, previously designated by the Stati eManager Vice President and Site ManaMer, Nuclear Geeration Site to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary and a vrification that the proposed actions do not constitute an unreviewed safety question. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, the Manager, Teekal, the -Manager, Operatiens, the Managcr, Maintenancc, thc Deputy Station Manager or the Manager, Wealth Phyzic or ebers of the nuclear division manaement staff as previously designated by the S4t4tion Hapnag Vice President and Site Manager, N4uclear Generation Site. Documentation of these activi ties shiallI be provided to the Vice Presi dent and Site Manager, Nuclear Generation Site and to the NSS Supervlisor.

6.5.2.6 The sta-i-es Site sSecurity pvegrm Plan, and implementing procedures, shall be reviewed at Teast once per 12 months. Recommended changes to the Site Security Plaw shall be approved by the Statin tanagcr Vice Presidenvt and Site

Managr, Nclear Generation Site and transmitted to-the-Manager-of-Nuelear Operatiefsaed.to the NSG Supervi sor; implementing procedures shal1 b~e prepared,

..nd.. app.. ovin accordance with Specification 6..

6.5.2.7 The s~t-e44eStte eEmergency Plan, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes to the Site Emergency Plan shall be approved by the kStionManager Vice President and $ite Manage'r,

.... cl....a.. Geration Site and transmitted to-the-Managcr-e4-Nuc.r-Operatis-nd to the NSG Supervisor; implementi ng procedures shall be prepared and approved in accordance with Specification 6 8.

6.5.2.8 The Station Manager shall assure the performance of a review by a qualified individual/organization of every unontrolled or unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager-ef-Nuclear-Operatiens Vice Presidnt and $1ite Manager, Nuclear Generation site; to the Statio~n Manager,.and to the NSG ESupervistO.

SAN ON0FRE-UNIT 2 6-9-12 AMENDMENT NO.f



6.5.2.9 The Station Manager shall assure the performance of a review by a qualified individual/organization and say designate the approval of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems. ou.entation. f these activities sh.a b. provided to the

Vic President and Site Managjer, Nuclear Gene.ratio~n Sites to the Station anager, and to the .SG Superviser.

6.5.2.10 Reports deementing Documentation f each of the activities performed under Specifications 6.5.7.1 through 6.5.2.9 shall be maintained I" accordance with Specification .1-opies-shall be previded to the -nageS-of

Nuciar pcratieonz 4nd thc Nuc aSfety Group


FUNCTION




c. chemistry and radiochemistry

d. metallurgy





COMPOSITION

6.5.3.2 The NSG shall consist of a Supervisor and at least three staff specialist. The Supervisor shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of sh-* 6 years of professional level managerial experience in the power field. Each staff specialist shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of f4-ie5 years of professional level experience in the field of his specialty.

The NSG shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.24.1. Such specialists shall meet the same qualification requirements as the NSG'members.

SAN ONOFRE-UNIT 2 6-1-0 13 AMENDMENT NO.


CONSULTANTS


REVIEW


a. The safety evaluations for 1) changes to procedures required by Specification 6.8, equipment or systems and 2) tests or experiments completed under the provision" of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.





f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g. AUA ) EPRALE IE..EN.TS. Eycnts requiring 24 hour written notifleatien to


i. Reports and meetings-minutes of the Onsite Review Committee.

SAN ONOFRE-UNIT 2 6-11- 14 AMENDMENT NO.


AUDITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG. These audits shall encompass:




d. The performance of activities required by the Opeational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. Any other area of unit operation considered appropriate by the Nuclear Safety Group Supervisor or NtanhaeVer of Nuelear O Presi dent and Site Manager, Nuce ar Generathi Site,


g. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.

h. An inspection and audit of thefire protection and loss prevention program shall be performed by a-outs!.de.qualified outside fire consultant at intervals no greater than .-yea.s 36 months.

AUTHORITY


RECORDS

6.5.3.7 Records of NSG activities shall be prepared and maintained. Report of reviews and audits shall be distributed monthly to the Statioe Manager Vice Presietand.Site.Manager Nuclear GenerationSite and to the management positions responsible for the areas audited.

SAN ONOFRE-UNIT 2 6--2 15 AMENDMENT NO.


6.6 REPORTABLE OGGURRENGEVENT ACTION

6.6.1 The following actions shall be taken for REPORTABLE GGURRENGE& EVENTS:

a. The Commission shall be notified andLes a report submitted pursuant to the requirements of Specificatisn 6.9.: Stio 0 1 CF Part SO, and

b. Each REPORTABLE GGGURRENGE requiring-24 heur netificat4 n to the Gefmm4-sieR EVENT shall be reviewed by the OSRC and the results f this review'shall be submitted to the Vice President and Site Mana&ger, ul Ga...........tionsite and to the ..SG Sipervisor.-nd-the-anager-of



a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager of Nuelear Qpernat-i-efVce President and Sito Manger, Nucleat Generation Site and the NSG Gh-U6m...'uperhat shall be notified within 24 hours.


c. The Safety Limit Violation Report shall be submitted to the Commission, the Manager of Nuelear Operations Vice Pr'esident and Site Manag'er', Nuclear Generation Site and the NSGSupervisorwithin14 days of the violtin



6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced"below:


SAN ONOFRE - UNIT 2 6-13 AMENDMENT NO.







g. PROCESS CONTROL PROGRAM implementation.-=


i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15 Revis*ion 1, February 1979.



6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the ice Preident ad Site.aager, Nuc.er .enerti on Site; orbyth Manager or.... by... .......... S-* .. the Station

Physt-es the responsibleucrivision Manager; or by theirdignees as previously designated by the S.tat4-eR-$aniageP Vice President and Site Manager, NuceTWW Generation Site prior to implementation and shall be reviewed periodically as set forth in administrative procedures.



b. The change is approved by two members of the p..a.. u.clear divisio management staff exercising responsibility in the specific area and unit ......... ..nif Us d by the change, at least one of whom hoTdsa7Senior.

Reactor Operatorrs gicense on the unit affected.

SAN ON0FRE-UNIT 2 .6-14 17 AMENDMENT NO.


c. The change is documented, reviewed and a pproved by the Statin llanagcr; or b 1 (1 t he Deputy Station-Managcr, (2 h ngr pcrations, (3)

thcMangW, Maintcnancc, (4) the' Manager Tchil or (5) th Manager, Health-Physies respo ble nucla* r division* mangeen staff as pev4ews4y designated by the.Stat- Managert accordance wth 5. above within 14 days of implementation.



A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the high pressure safety injection recirculation, the shutdown cooling system, the reactor coolant sampling system (postaccident sampling piping only), the containment spray system, the radioactive waste gas system (post-accident sampling return piping only) and the liquid radwaste system (post-accident sampling return piping only). The program shall include the following:




A program*-which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) Training of personnel,

(ii) Procedures for monitoring, and


A S Specification 6.13.1A E

SAN ONOFRE-UNIT 2 6-44:.x. 1XAMNMET.O

AUMINISlKAllVE CUNIKULS



(i) Identification of a sampling schedule for the critical variab4es parameters and control points for these variables parameters,

(ii) Identification of the procedures used to measure the values of the critical variables" pat rs,

(iii) Identification of process sampling points, including monitering the dizchargc of the eondensate pumps for eyidence of condenser

(iv) Procedures for the recording and management of data,

(v) Procedures defining corrective actions for all off-control point chemistry conditions, and

(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Post Accident Sampling

A programtwhich will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The programrnshall include:

(i) Triigo ersnnel,

(ii) Procedures for samping and analysis, and

(iii)I Provisions for maintenan~ce of sampl ing and anal&ysis equi pmenlt


A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

SAN ON0FRE-UNIT 2 6-6191il AMENDMENT NO.



1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2;

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM;


5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, respectively, in accordance with the methodology and parameters in the ODCM at least every 31 days;

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50;

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1;

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50;

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50;


SAN ONOFRE-UNIT 2 6-5 2M1 AMENDMENT NO.



A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the~methodology and parameters in the ODCM,




ROUTINE REPORTS AND REPORTABLE GGURRENCES

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U. 5. Nuclear~ Reulatory Comiss ~ion,3 Attenti on: Document Control1 Desk, ashiMngton, D.. C. 205554 with a copy to the NIRG Regional Administrator of the Reginal Office of the NC, unless otherwise noted.

STARTUP REPORT

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9..1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based o n other commitments shall be included in this report.

SAN ONOFRE-UNIT 2 6-156 21 AMENDMENT NO.


ST.U .T P(Continued)

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test-program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS*

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The intial rcport shall be submitted prior to March 1 of the year fellewing inital criticality,

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated manrem exposure according to work and job functions , e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

Reports required on an annual basis shall include the results of specific activity analysis in which the primary coolant exceeded the limits ofSpecification 3.4.7. The following information shall be included in these reports: (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while t#0 limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than th limit. Each result should include date and time of sampling and the radiofdine concentrations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

A single submittal may be made for a multiple unit station. -The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of §20.407 of 10 CFR Part 20.

SAN ONOFRE-UNIT 2 6-16 2? AMENDMENT NO.



6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

6.9.1.7 DELETED


6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The report shall also include a summary of the quantities of solid radioactive waste shipped from the unit directly to the disposal si te adthe quanti ties of sol id radioactive waste shipped froe the unit's initermediary processor to the disposa site.i The material provided shall be (1) consistent with the objectives.outlined in the 00CM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of . Appendix I to 10 CFR Part 50.

6.9.1.9 DELETED


6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the preSsurizer safety valves, shall be submitted on a monthly basis to the Directeor-9O4ie-ef-Reseweec Mantaeet- U.S. Nuclear Regulatory Commission, Attention:~ Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

An siange tobttal maSbe OSE fo CLUaO muAll unitb stati.The subittal

shouldc cIne thosdsetions oto tany ar cmnge to luisa the t aton

however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SAN ONOFRE-UNIT 2 6-1-i 23l AMENDMENT NO.

. ADMINISRATI.'E- CONTROLS


6.9.1.11 The REPORTABLE OCCURRENCES of Specification: 6.9.1.12 and 6.9.1.13 below, including corrcctiye action: and mcasure: to prcvent rccuF~Rrze, shallb Fcported to the NRC. Supplcmental report: may b e rcequircd to fuilly dcscribc final resolution of ocemurrcne. In caq-c oef c-Arrztcd or supplcmental rcports- -a licensce cvcnt rcport shall be completed and reference shall be made to the

orgi ! report date.

PROMPT NOTIFICATION WITH WRTN 6FOLLUP

6.9.1.12 The type: of evznts li :ted bel ow shall be reported within 24 hour: by telephone and confirmed by telegraph, mailgram. or facsimile :transmi::ion to. the NRC Regional Administrator, or hi:I de nte no later than the first workin day following the event, with a written foell~owup report within 14 days. The wri4tten followup report shall inc-lu'de, a: a miim, a cmpleted copy of a licensee event report form. Informfation proie on t-he liensee event report form shall be supplemented, a: needed, by addiion.a1.l naaiv e material to provide complete explanation of the circumstance: surrounding the event.

a. Failure of the reactor protectien system or other systems subject t limiting safety system settings to initiate the require protective function by the time a monitored parameter ece the :ctPGint speeified a: the limiting safety system setting in the technical specification: or- failure to complete the required proteetive function. Sb. Operation of the unit or affected system: when any parameter or operation subject to a limiting condition for operation i: le::s conservative than the least Po~rai epet of the Limiting Condition for Operation established in the Technical Specification:.

c. Abnormal degradation di::overed in fuel cladding, reactor coolant pressure boundary, orpiay containment.

SAN ONOFRE UNIT 2 6 18 AMENDMENT NO.

. ADMINISTRATIVE CONTROLS

d. Rcactivity anon'alies involving disagreement with the predictcd value of rcactivity balancc undcr steady state conditOns duFrng powcr opcratin grcatcr than or equal to 1% Ak,'k a calculatcd rcactivity balancc indicating a SHUTDOWN MARGIN less conscrvatiye than spccificd in the Tcchnical Spccificatikns; sher c ractivity inercases tha-t corspond to a reactor pcrio-do ca-lss than 5 seconds or, ifsubcritical, an unplaimncd rceactivity nscrtion of ,corc than 0.5% Wkk or occurrenec of any unpland critiality.

e. Failure or malfunction of onc or marc eemponcnts which pr ents orf could ppcvcnt, by itself, the fulfillmcnt of t-he fucioa equircwmentS Of systemis) used to copc with accidcntS analyzcd in the SAR.

f. PerSOnnel crror or proccdural inadequaey which prcvcntS or could prevent, by itsclf, the fulfillment of the functioal requirementS of systems required to copc with accidents analyzed in the SAR.r

g.Coditon aing from natural or man made cvcnts that, as a diret result of the een re uruit shutdown, operation of safety systems, or other protective measures required by Technical Speific~ationS.

h. Errors discovered in the tranSient or accident anal yscs er in the wmtheds used for SUch analyse: as. described in the, safety analy5s

report or in the bases for the Teel...ical Specification that haye or could have permitted reactor operatio ma annr less consr45Pativel than assumed in the analyses.

i. Pcrefolance of structures, systems, or component: that ruieremedial action or corectivemauc to prevent operation in a wManner less conservative than as:sumed in the aeeident analyse: in the safety analysis report or Technical Speification: bases; or discovery during unit life Of conditionS not specifically eonSidered in the safety analysis report or Technical Specificatons that reurermedial actio or correctivc measures to prevent the existence or dvlpent of an unsafe conditio.

j.Offsite releases of radioactive materials in liquid and gaseous effluents that exceed the limits of Specificatios 3.11.1.1 oer 3.11.2.1

k. Exeeeding the limits in Specification 3.11.1.4 or 3.11.2.6 for the storage of radioactive materials in the listed tanks. The wri4tten follow up report shall include a schedule and a description of acti vites planned and/or taken to reduce the contents to Within the

specified limits.

1. Failure Of one or mere pressurizer safety valves.

SAN ONOFRE UNIT 2 6 19 AMENDMENT NO. 83


ZTHIRTY DAY WRITTRA REPO RTS

6.9.1.14 The types of crt licted blow shall b th e ubjcct of writtlwa repor te onto NRC R egienal Admitstrater wtoh thirty day of Admrnc ro th e nt. Th writtn rport hall uilude, t . ni, a competed gl pyatf a 44censcc cvcnt report form. Information providcd On the liccnsee cent rcport form shall be t upplm cntced, an needtd, by additisnal gnarDatvC. mater5al to poytido templctc Replanaation of th e iumstaRe:goun Offdig the e RCnt.

ath Reater prectiyied fytcm er e rafty fature ntumcnt setting: which arc found te be less conservati vc than thesc cstablished by the Technical Speeification: but which do not prevent the fulfillmnent of the funticnal req crd r eemnt e of affected uyit s T 1

b. Conditins leading to operation in a degraded mode permitted by a Limiting onditi for Operat n eor plant bhutdon r ad by a Limitpin Cnditie fr Operation.

S . Oberved Inadequaie: in the implemetation of adinistratie or procedural control: which threaten to cause reduc~tion of degre o redundancy provided in rcaeter protection: e:o enieered safety feature systems.

dAbnorcial degradation of :yq-tePm: other than these :pecified in 6.9.1.12.e above designed to contain radioactive material rcesltin fromi the fi::ion proe::.



SPECIAL REPORTS

6.9.2 Specal Reports shall be submitted to the U .tul~ ei~tr

FeealRgua ion thwolwnieorssalb eaie o tla t he

minimum period indicated.

SAN ONOFRE-UNIT 2 6 - 24.iii4 AMENDMENT NO.


.EO0. TN.N(Contin.ed) 6.10.1 The following records shall be retained for at least five years:



c. All REPORTABLE OGGURR ENGS EETS submitted to the Commission.

d. Records of surveillance activities -" inspections and calibrations required by these Technical Specifitations.













h. Records of inservice inspections performed pursuant to these Technical Specifications.

SAN ONOFRE-UNIT 2 6-24125:: AMENDMENT NO.


o.TfCotinued) i. Records of Quality Assurance activities required by the QA Manual n

Thlded in Specifiation 6A.101


k. Records of WM meetings e4f-4he-GPG and the NSG 10 11:.

1. Records of the service lives of all snubbers within the scope of Technical Specification 3/4.7.6 including the date at-which the service life commences and associated installation and maintenance records.


n. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS-CONTROL PROGRAM.


Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.


6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:



c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.

SAN ONOFRE-UNIT 2 6-22 28::!!! AMENDMENT NO.

ADMINISTRATIVE CONTROLS . ~ HIGH RADIATION4 AREA (Continued)

6.12.2 Tn addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superv-see Superinteni4de on duty and/or health physics supervision. Doors shall remaihlocked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted. and unless a health physics tech.nician is in con.ti.uus attendanc a flashing light shal be activated as a warning device. In lieu of the stay time specification of the REP, direct or remote (such as use of closed-circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.


6.13.1 The PCP shall be approved by the Commission prior to implementation.


1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.22n. This docuentation shall contain:


b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations5 ; and


2. Shall become effective upon review and aeeeptanes approval pursuant to 6.5.2 by the Stato. .aager.

Measurement made at 18" from source of radioactivity.

* The PCP shall be submitted and approved prior to shipment of "wet" solid radioactive waste.

SAN ONOFRE-UNIT 2 6-2g 2-::7: AMENDMENT NO.




6.14.2 Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2"n. This documentation shall

contain:~ a. Sufficient information to support the change together with the

appropriate analyses or evaluations justifying the change(s);

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.; an


2. Shall become effective upon review and aeeep ase approval pursuant to 6.5.2 by the Station nager

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

SAN ONOFRE-UNIT 2 6428 . AMENDMENT NO.

THIS PAGE INTENTIONALLY LEFT BLANK

SAN ONOFRE UNIT 2 6 25 AME-NDQME-N NO. 83

7.0 SPECIAL TEST PROGRAM

7.1 Fo nducting the natural cculation test -fowing Tectinial Speeificationz arc emempt:

TeeI-c-.a1 Seeeifca tions Test Te:t Te:t

Section Dccripton 01 B2 B3

3.4.1.2 Reactor C olant 3 T

3.m.1.3 Rcactrn Coolant Syrter 1' u2 xr Hot Shutdo'wn

3.7.1.3 Gondcnzatc Storage Tank xA

NOTESi 1. No opcrationz are permitted whtould eausc dilution of the Rcactor Coolant System boron concentration.

2. Core outlet temperature is maintained at least 1OoF below saturation temfpeatue-r

3. A Reactor Coolant pump shall not be started with one or more ofth Reactor Coolant System cold leg temperatures less than or equal to 235OF unless the secondary water temperature of each steam generator is less than 10064 aboye eaeh of the Reactor Coolant System eold le~g temperatues.~

i "Natural Circulation Test Program, San Onofre Nuclear Generating

SAN ONOFRE UNIT 2 7 1 AMENDMENT NO.

ATTACHMENT D

PROPOSED SPECIFICATIONS UNIT 3

Low Power

-12

E. SCE shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans ic.ludi.ng ther latet rvisions, which contain Safeguards Information proteted under 10 CFR 73.21, are entitled: "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan," with Pcision- submitted through April 22T 19889 "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and Qualification Plan," w4th rc'. wrios-ubmitted threugh Geteber- 22, 986; and "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Safeguards Contingency Plant," with Fesisions-submitted through December 29, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.



G. SCE shall report any violations of the requirements contained in Section 2, items C(1), C(3) through C(11), C(13) through C(22), E, and F of this license within 24 hours by telephone and confirm by telegram, mailgram, or facsimile transmission to the NRC Regional Administrator, Region V, or his designee, no later than the first working day following the violation, with a written followup report within fourteen (14) days.


AMENDMENT NO.

INDEX

DEFINITIONS

SECTION PAGE

1.0 DEFINITIONS

1.1 ACTION...................................................... 1-1

1.2 AXIAL SHAPE INDEX........................................... 1-1

1.3 AZIMUTHAL POWER TILT........................................ 1-1

1.4 CHANNEL CALIBRATION......................................... 1-1

1.5 CHANNEL CHECK............................................... 1-1

1.6 CHANNEL FUNCTIONAL TEST..................................... 1-2

1.7 CONTAINMENT INTEGRITY....................................... 1-2

1.8 CONTROLLED LEAKAGE.......................................... 1-2

1.9 CORE ALTERATION.............................................. 1-2 1.10 DOSE EQUIVALENT 1-131....................................... 1-3

1.11 E-AVERAGE DISINTEGRATION ENERGY.............................1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME................... 1-3

1.13 FREQUENCY NOTATION......................................... 1-3

1.14 GASEOUS RADWASTE TREATMENT SYSTEM........................... 1-3 1.15 IDENTIFIED LEAKAGE......................................... 1-3

1.16 OFFSITE DOSE CALCULATION MANUAL (ODCM) ...................... 1-4 1.17 OPERABLE - OPERABILITY...................................... 1-4

1.18 OPERATIONAL-MODE - MODE................................... 1-4

1.19 PHYSICS TESTS............................................ 1-4

1.20 PLANAR RADIAL PEAKING FACTOR - Fxy.......................... 1-4.

1.21 PRESSURE BOUNDARY LEAKAGE................................. 1-4

1.22 PROCESS CONTROL PROGRAM (PCP).............................. 1-4

1.23 PURGE - PURGING............................................ 1-5

1.24 RATED THERMAL POWER............................... ......... 1-5

1.25 REACTOR TRIP SYSTEM RESPONSE TIME........................... 1-5

1.26 REPORTABLE URRNGEE T................................ 1-5

1.27 SHUTDOWN MARGIN........................................... 1-5

1.28 SOFTWARE................................................. 1-5 1.29 SOLIDIFICATION --DELETED 1.30 SOURCE CHECK........ .. 1-5

1.31 STAGGERED TEST BASIS....................................... 1-6 1.32 THERMAL POWER............................................. 1-6

1.33 UNIDENTIFIED LEAKAGE....................................... 1-6

1.34 VENTILATION EXHAUST TREATMENT SYSTEM............... ........ 1-6

1.35 VENTING....................................... ............ 1-6

SAN ONOFRE-UNIT 3 I AMENDMENT NO.

INDEX


SECTION PAGE

6.1 RESPONSIBILITY ............................................. 6-1

6.2 ORGANIZATION

6.2.1 OFFSITE ANDONSITEDRGAN.ZATON .............................. 6-1

6.2.2 UNIT STAFF ......... ......................................... 6-1 .

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP ......................... 6-78

6.2.4 SHIFT TECHNICAL ADVISOR ................................... 6-798

6.3 UNIT STAFF QUALIFICATIONS ....................................... 6-7 8

6.4 TRAINING ........................................................ 6-4 9



FUNCTION.................................. ..........

COMPOSITION ........................................... 6-89

ALTERNATES ............................................ 6- 9

MEETING FREQUENCY ..................................... 6-910

QUORUM ............................................... 6-9 10

RESPONSIBILITIES ...................................... 6-9 10

AUTHORITY .............................................6-9 10 RECORDS .... ......................................... 6-.0 11

6.5.2 TECHNICAL REVIEW AND CONTROL ............................... 6-4. 11


FUNCTION 6 ............................................. 6 13

COMPOSITION ......................... .................. 6-12 13

CONSULTANTS ........................................... 6- 14

REVIEW .... .......................................... 6-1- 14

AUDITS ................................... ............ 6-13 15

SAN ONOFRE-UNIT 3 XV AMENDMENT NO.

INDEX

LIST OF FIGURES

FIGURE PAGE

5.6-4 FUEL STORAGE PATTERNS FOR REGION II RACKS RECONSTITUTION STATION ......................... ........... 5-15

6.2 1 OFF61TE ORGANIZATION .....................6 3

6.2 2 UNIT ORGANIZATION ....................... 6 4

6.2-3 CONTROL ROOM AREA .................... ..................... 6-6 7

SAN ONOFRE-UNIT 3 XVIIa AMENDMENT NO.

INDEX


SECTION PAGE

AUTHORITY................................................6-1 15

RECORDS... .............................................. 6-1- 15

6.6 REPORTABLE OGURRENGE (y4J ACTION............................ 6-44 14

6.7 SAFETY LIMIT VIOLATION...................................... 6-14 16

6.8 PROCEDURES AND PROGRAMS............................ ......... 6-14.1


6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES................... 6- 2

STARTUP REPORT........................................ 6-48 1.

ANNUAL REPORTS....................................... 6-14922

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT........ 6-0 23

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT........... 6-20 23

MONTHLY OPERATING REPORT...............................6- 23

REPORTABLE OCCURRENCES..................................61

PROMPT NOTIFICATION WITH WRTENFLLOWUP ..... ;........... 621

THIRTY DAY WRITTEN REPORTS..............................6 22

HAZARDOUS CARGO TRAFFIC REPORT.......................... 6-2 24

6.9.2 SPECIAL REPORTS.......................................... 6-23 24

6.10 RECORD RETENTION............................................ 6-224

6.11 RADIATION PROTECTION PROGRAM................................. 6-242

6.12 HIGH RADIATION AREA....... ......... ........................ 26

6.13 PROCESS CONTROL PROGRAM (PCP) ................................ 6-6 .27

6.14 OFFSITE DOSE CALCULATION MANUAL................................. 6-26 28

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS DELETED


INDEX LIST OF TABLES

TABLE PAGE

4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.......................................... 3/4 7-9

4-2SUBBER VISUAL ISPCTIO NTRL. ... 3/4 7-7a

3.7-5 SAFETY-RELATED SPRAY AND/OR SPRINKLER SYSTEMS............3/4 7-32

3.7-6 FIREHOSESTATIONS.................................... 3/4 7-34

4.8-1 DIESEL GENERATOR TEST SCHEDULE...........................3/4 8-7

4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.......................3/4 8-11

3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.............................................. 3/4 8-18

3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS. DEVICES PERMANENTLY BYPASSED.............................. 3/4 8-32

4.11 1 RDIOACTIVE LIQUID SAMPLING AND ANALYSIS PROG4-M DELETED 1.11 2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

DELETED

3.12 1 RADIOLGIA ENVIRONMENTA MOITRNG PROGRAM DELETED

3.12 2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATOSI ENVIRONMENTAL SAMPLES DELETED

4.12 1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION DELETED

B3/4.4-1 REACTOR VESSEL TOUGHNESS................................ B3/4 4-8

5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................... 5-8

6.2-1 MINIMUM SHIFT CREW COMPOSITION.......................... 6-5

SAN ONOFRE-UNIT 3 xx AMENDMENT NO.

DEFINITIONS

PURGE - PURGING


RATED THERMAL POWER




REPORTABLE OGURRENCE ......

1.26 A REPORTABLE OCCURREE A s hall be any of those conditions specified in Speeifleations 6.9.1.12 and 6.. .13 Scto .50. t 1CFR. .....

SHUTDOWN MARGIN 1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming (1) all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest. reactivity worth which is assumed to be fully withdrawn, and (2) no change in part length control element assembly position.

SOFTWARE


1.29 DELETED

SOURCE CHECK



SECTION 6.0



6.1 RESPONSIBILITY

6.1.1 The Statie Manager Vice President and Site Manager, Nuclear Generation Site shall be responsible for .verall unit operation and saintenanCe of Units 2 and 3 at San Onofte Nuclear Generating Site, and. al site support functions. Hfe shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift-Sepevi4seF Superintendent (or-during-hi-absese from thc Control-Rome.asr-aWak ....aed-individual) shall be responsible for the Genteel Reem ultimate command e decision authority for al.unit activi.ties an operations which affect~ the safety of the plant. site personnel and/or the general publc. A management directive to this effect, signed by the Vice President of-Nedlearperationsite shall be reissued to all tastation personnel on an annual "basis.

641.3 The Control Room Superv isor (or during hi s absence from the Control Room Area, a designated individual with a valid SR0 licene shllbe repsible for the Control Room com.and function. The Control Room.upris shd normally be in the Control Room .nd shal be within the Control...mArea defined by Figure 642-34

6.2 ORGANIZATION

O OFFSITE AND ONSITE ORGANIZATION



b. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Senior Vice President, Nueicar-Engincering,-Safety,-and-bieenstag and the Vice President and Site Manager, Nuclear Generation Site shall have corporate responsibility for overall plant nuclear safety. The Vice President and Site Manager, Nuclear Generation site shall take any measures needed to ensure acceptable performance of the staff in operating and maintaining the plant to ensure nuclear safety. The SenorVice President,-Nuclear-Engineering,-Safety-and-bisensing shall take any measures needed to ensure acceptable performance of the staff in providing technical support to the plant to ensure nuclear safety.




UNIT STAFF The Unit erganization shall be as shown in Figure 6.242 and:


b. At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room area identified as such on Table 6.2-1.

c. A health physics technician' shall be on site when fuel is in the reactor.


e. A site Fire Brigade of at least 5 members shall be maintained on site at all times." The Fire Brigade shall not include the Shift Superviso 'Su and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

ROTEt T.IS SPACE TS RESERVED FOR UPCONING CHANGES TO SECTIOR 6.2.2f.


SAN ONOFRE-UNIT 3 6-4& 2 AMENDMENT NO.


UNIT STAEF (Continued)

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

1) An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time.

2) An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any 7-day period, all excluding shift turnover time.

3) A break of at least eight hours should be allowed between work periods, including shift turnover time.

4) Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Station Manager, his deputy, the Manager, Operations or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

....OT .THIS SPACE IS RSERVEDOR. UPCOMI.G C.ANG.ES TO SECTION .2..f..


(ThiE pagT Mntcntionally blanD

SAN ONOFRE UNIT 3 6 3 AMENDME NT NO. 57

(This pag int tN InallyEblanI

QA NFRE UNIT 3 6 4 AMENDMENT NO. 57


UNI STAF (Continuedi)

NOTE: THIS SPACE IS RE$ERVED FOR UPCOMING CHANGES TO SECTION 6..51

g. The Plant Superintendent (at time of appointment), the Assistant Plant Superintendent*pertions, Shift Superintendents and Control Room Supervisors shall hold a sSenior teactor edperatoriS. license. The Control Operators and Assistant Control Operators shal hold a sPeactor e0perator t s license o. Senior. Reacto Operator's license.

.N FRE4UNIT 3 6-4 AMENDENT NO0

Table 6.2-1




MODES 1. 2. 3 & 4 MODES 5 & 6

SS la 1a SIRO CRS 1 None RO COACO 2 1 AO E 2 2 STA 1 None

WITH UNIT 2 IN MODES 1. 2. 3 or 4


MODES 1. 2. 3 & 4 MODES 5 & 6

SS la la SRO CS 18 None RO CO/AC 21 AO NPEO 12b STA la None

aL8 Individual may fill the same position on Unit 2. bLb One of the two required individuals may fill the same position on Unit 2.

SS - Shift Suipervinse 06 Superntendent with a Senior Reactor Operator 's icense on San Gofre Units 2 and 3.

SRG CRS - Indi44ides- Con"trol Rooan Supervisor with a Senior Reactor Operator:s

blicense on Sanofre Units 2 and 3. R G .... .......

00/AC--4+44.a Control Operator/A.si.tant Co..trol Operator with a Reactor Operator's klicense or a Senior Reactor Operator's license on San Onofre Units 2 and 3.

AG NPE0 -Auxiliary-Operator Nuclear Plant Equipment Operator (RectorOperatr'

STA - Shift Technical Advisor



Except for the Shift Super ise Superntendent, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Control Room Supervisor from the Control Room Area shown in Figure 6.2-3 whilethe unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function. During any absence of the Sht4 Control Room Supervisor from the Control Room Area shown in Figure 6.2-3 whiTe the unit is in MODE 5 or 6, an individual with a valid SRO or RO license shall be designated to assume the Control Room command function.

SAN GNFRE-UIT l3 6- MNDM4ENT NO.

-- U LuHUUUUL U U UU unn Cl)l 1111 IIIIIII I0I0I lflll

CONTROL ROOM

UNIT 2 UNIT 3

r Shift Supt.

UNIT 2 Office UNIT 3

Comnputer Room Turbine Lab Computer Roor

Op Support Office

Figure. 6.2-3. n 00 CONTROL ROOM AREAStrg

> SAN ONOFRE GENERATING STATION - UNITS 2 & 3

m CDKliche Lockers

m ~Lunch Rm.

C)


6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION


COMPOSITION


RESPONSIBILITIES

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification* that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to offsite organization management.

RECORDS


6.2.4 SHIFT TECHNICAL ADVISOR

The Shift Technical Advisor shall provide technical support to the Shift Superis perintendet in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit. The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents.

6.3 UNIT STAFF QUALIFICATIONS


* Not responsible for sign-off function.

SAN ONOFRE-UNIT 3 6-X 8 AMENDMENT NO.


6.4 TRAINING

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training and shall meet or exceed the requirements and recommendations of Sections 5.5 of ANSI N18.1-1971 and Append I-"A"-ef 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.

6.. A training program for the Fire brigade shall be maintained by the direction of the Manager, Site Emergency Preparednbess and shUl meet or exceed the requi rements of National Fire Protection Association Standard No. 27-1975. 6.5 REVIEW AND AUDIT


FUNCTION


COMPOSITION


Chairman: SttoMage Member: Dpt tto aae Member: MaaeOetin Member: Mngr ehia Member: PatSprnedn OG nt n Member: SuevsroIC Member: MaaeHat Phsc Member: *pw--e-- aae 1 Chmsr Member: Mngr aneac

Member:to Managerevin Enier NSNSSuprt Cmpt,

e p u t y S t..a t o n M a n a e r ........... ... ...

Mange.r, gOp e eeration) Member: Plant Spe inteetrSONG U~pnit tve 2no

d.~Eg neer 110

Charma toseve n atprryo bais;r hemryomr hntoatrae

shal prtiipae avoing meupervsi in neerC acivtis atEa-nyotme pt

(1) B degre inEngineering, or Psica Sceneat satlesiouryer

6.5.1.3sioaleel mexerienceallbesappointedtinewritine of the oryar

I experience shall be nuclear power plant experience.



MEETING FREQUENCY


QUORUM


RESPONSIBILITIES



b. Review of all REPO"TABLE EVENTS. events requiing-24-hour written noti ficto totcCom o


d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the NSG Supervso.


AUTHORITY


a. Render determinations in writing with regard to whether or not items considered under 6.5.1.6{,a) above constitute unreviewed safety questions.

b. Provide written notification within 24 hours to the Manager of Nuelear Ope4eies-Vice Preident anid Site Managers ucear Generation Site and the NSG Supervisor ofdisagreeient between the OSRC and the Station Manager; however, the Stat4en Manager Vice.President and Site Manager, Nuclear Generation Site shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

SAN ONOFRE-UNIT 3 6-9 10. AMENDMENT NO.


RECORDS

6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these tTechnical :Specifications. Copies shall be provided to the Nuclear Safety Group


ACTIVITIES

6.5.2.1 The Statioe-Manager-Vice President and Site Manager uclear Generation $ite shall assure that each procedure and pr~pgram required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual/organization. Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto. .ocumentation of thes. activities halle provided to the 856S Supervisor.

6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall be prepared by a qualified individual/organization. The preparation of each proposed Technical Specifications change shall be reviewed by an individual/ group other than the individual/group which prepared the proposed change, but who may be from the same organization as the individual/group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the Station Manager. Documentation of these activities sha11 be roviided to the Vice President and Site.Mnager, Nucear Generation.Site nd to

the S. Supervisor...

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual! organization. Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Mage. Vic. Pesident and Si te Managers Nuclear Generati on Site. Documentation of these Pctivities shall bierov.ded to the Vie Presidetand site stne, Nuclear Generation Site and to the iSG Supervisor..

SAN nNOFRE.UNTT 3 6-1-Q 11 AMENDMENT NO.



6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the statioensupervisory nuclear divisoin management staff, previously designated by the Station-Manager Vice Pres ident and Site Manager tuclear Geeration $ite to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary, an4 a verification that tbe PToposed actions do not constitute an ureview.ed safety question..If deemed necessary, such review shal be performed by the appropriate .designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, the Manager, Teekeheal, the Manager, Operation, the

or members of the nuc.ear division management staff as previously designated by the.statio-Mantagef Vice President and Site Manager~, fiuclear.Generation Site. Doumetation of theeactivi ties sha.lbe provided to the Vic Presden and Site Manager, Nuclear Gienerati on Site and to th NSS5 Supervi sor.

6.5.2.6 The stati~site sSecurity proeda Plan, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes to the Site Security Plea shall be approved by the Station-Manager Vice Presdent and Site Manager, tNuclear.£Generation Site and transmitted to-the-Manager-of-huclear.

*Ope.ratisas-sed to the.NSG Supervisor; implementing.poceure shall be pepared Iand approved in accordance with Specification 6.8.

6.5.2.7 The stati4- t t eEmergency pPlan, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes to.the Site Eerge.c Plan shall be approved by the Stationanager Vice President and Site Manager, Nuclear Generation Site and transmitted to-tthchaager o Nuccar.eO-peretiens-and to the NSG Supervisor; implementi ng procedur'es shall be pr'epared and.approedj in accordance wi th Specifcation 6.84

6.5.2.8 The Station Manager shall assure the performance of a review by a qualified individual/organization of every uncontroled or unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager-of-Nuclear-Operatisns Vice Piresi4gt and Site Manager, Nuclear Gieneration site; to the Station

Manager, and to the N4SG Supervisor.

SAN ONOFRE-UNIT 3 6-4-0 12 AMENDMENT NO.



6.5.2.9 The Station Manager shall assure the performance of a review by a qualified individual/organization and .ay designat. the approval of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems. ocmttion of these tivities sh.l be provided to the Vice President and Site~ Manager, flucear Generatio Site; to the Statio. Manager, andt th...S. Sup.visor.

6.5.2.10 Reports deeumentg D mntation of each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained accordace with Speification 6.1X. Gepies shall be proevided to the-Manager of We IWrcain n h i Safety Group


FUNCTION




c. chemistry and radiochemistry

d. metallurgy





COMPOSITION

6.5.3.2 The NSG shall consist of a Supervisor and at least three staff specialift. The Supervisor shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of 6 years of professional level managerial experience in the power field. Each staff specialist shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of 5 years of professional level experience in the field of his specialty.

The NSG shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.93.1. Such specialists shall meet the same qualification requirements as the NSG members.



CONSULTANTS


REVIEW


a. The safety evaluations for 1) changes to procedures required by Specification 6.8, equipment or systems and 2) tests or experiments completed under the provision" of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.





f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g. Al REPORTABLE EVENTS. Events requiring 24 hour written netification to


i. Reports and meetings-minutes of the Onsite Review Committee.

SAN ONOFRE-UNIT 3 6-- 1 AMENDMENT NO.


AUDITS

6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG. These audits shall encompass:




d. The performance of activities required by the Operatieal Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. Any other area of unit operation considered appropriate by the Nuclear Safety Group SG W sor or tanager-of- ustear-Operatiews the Vic President and Site Manager,.uclear Generation Si.te.


g. An independent fire protection and loss .prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.

h. An inspection and audit of the fire protection and loss prevention program shall be performed by an-eutside a qualified outide fire consultant at intervals no greater than &-yearsV36 o..

AUTHORITY


RECORDS

6.5.3.7 Records of NSG activities shall be prepared and maintained. Report of reviews and audits shall be distributed monthly to the Statien Manager Vice Presiet and Site Manager, Nuclear Generation Site and to the management positions responsible for the areas audited.



6.6 REPORTABLE OCGURRENGEVENT ACTION

6.6.1 The following actions shall be taken for REPORTABLE GURRENE& EVE.TS.:

a. The Commission shall be notified and 4e* a report submitted pursuant to the requirements of Spee4ficatin 6.9."S'ction 5 0.7 0 C Part 50 fnd

b. Each REPORTABLE OGGURRENGE -4quiring 214hour neicatien to the Geem isP4em V.ET shall be reviewed by the OSRC and theresultsofthis review shall be submitted to the Vice President and site Manager, Nuczlear Generation Site an to the NSG Supervisor. and-the-Manager-of ..cc a ....... t................



a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager of Nuelear Operatie ice President .d Site Manager, uclea. G eration Site and the NSG Ch-ma Spe.rs r shall be notified within 24 hours.


c. The Safety Limit Violation Report shall be submitted to the Commission, the Managr- of Nuelear Operations Vice President and Site Manaer, Nuclear Generatio Site and the NSG Supervisor within 14 days of the





SAN ONOFRE-UNIT 3 6--4 15 AMENDMENT NO.


PRO...URES..ND.PROGR..S (Continud)






g. PROCESS CONTROL PROGRAM implementation.-


i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15"" Revisio 1, February 1979.



6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the Vice Presidentt and.Sitean rucerGertnSteorbthSain Manager; or by ... . ....................... th Station

Phys-es the Manager or) byei des ge s as previously designated byOthe Stie-Magef.Vic P idn .$ite Manager, NuclearGe.eration Site prior to implementation and shall be reviewed periodicaTty as set forth in administrative procedures.



b. The change is approved by two members of the p..a.. clea..divisio management staff exercising responsibility in the specific area and uniit or units addressed by the change, at least one of whom holds a Senior Reactor.par nicense on the unit affected.

SAN ONOFRE-UNIT 3 6-4s 17 AMENDMENT NO.


PRCDRS MPORN (Continued)

c. The change is documented, reviewed and a pproved by the Station tanagcr; or. by (1) the Dcputy Station Man-aer (2) thc Managr Ocat in, (ar

the anagr, MaintcnAAcc, (4.) the Manager. Tcchnical, r(5 h Manager, Health Physies rsosible suclear divionaMemnt staff as pevieus4y designated by-the-Station-Managert in ccordance with 6.842 above within 14 days of implementation.



A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the high pressure safety injection recirculation, the shutdown cooling system, the reactor coolant sampling system (postaccident sampling piping only), the containment spray system, the radioactive waste gas system (post-accident sampling return piping only) and the liquid radwaste system (post-accident sampling return piping only). The program shall include the following:




A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) Training of personnel,

(ii) Procedures for monitoring, and


Se Specification 6.13.1

SAN ONOFRE-UNIT 3 6-4&aM1 AMENDMENT NO.




(i) Identification of a sampling schedule for the critical vabiahles parameters and control points for these vaf4ables parameters,

(ii) Identification of the procedures used to measure the values of the critical vsaviables parameter,

(iii) Identification of process sampling points, including menitoring the dizcharge of the condcnzate pumps for cyidence of condcnscr 4R leakage7

(iv) Procedures for the recording and management of data,

(v) Procedures defining corrective actions for all off-control point chemistry conditions, and

(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.


A programWwhich will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program*-shall include: e

(.) Traiing. of pernnl .

(ii) Procedures for ampling and aa lysisandi

(iii) Provisions for maintenance of sampling and hlyi equipmenit.


A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

SAN ONOFRE - UIIT 3 6--6 AMENDMENT NO.


Radioactive-Effluent Controls Program (Continued)

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2;

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM;


5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, respectively, in accordance with the methodology and parameters in the ODCM at least every 31 days;

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50;

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1;

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50;

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50;





A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The

program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,




ROUTINE REPORTS AND REPORTABLE OCCURRENCES

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U. S.

Nula Rgt ort*y Comision,.Attention: Document Conitroli esk; Mahington U. C. 20555, with~ a coyto the NRG Regional Administrator of th. ReIoa

Office of theNRC,. unTess otherwise noted.

STARTUP REPORT

6.9.1.1 A sunmmary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be

* described. Any additional specific details required in license conditions based

on other commnitments shall be included in this report.

SAN nNfOF11NTT 3 6-4g& 21 AMENDMENT NO.


STATUPREPRT Continued)


ANNUAL REPORTS*

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The inital report shall be submittcd prior to Parch I of thc year following

inital criticality.,

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated manrem exposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

Reports required on an annual basis shall include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7. The following information shall be included in these reports: (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radio'odine concentrations; (3) Cleanup system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

* A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of §20.407 of 10 CFR Part 20.




6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before.May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

6.9.1.7 DELETED


6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and selid waste released from the unit. The report shall altso includ a...m.ry of the qu titis of solid radiactive wste shipped free the.unit directly to the disposal site an~d the quantities of solid radioactive wast shipped from the uinit's.intermediary processor' to the disposal site. The . material provided shaTTibe.(1).consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

6.9.1.9 DELETED


6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the prssad1eit safety valves, shall be submitted on a monthly basis to the Direetor,-Office-of-Resoures Manaement,- U.S. Nuclear Regulatory Commission, Attention ocmntCnto Desks, Washington, D.C. 20555, with a copy to the Regional.Administrator of the Renal Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

Monthly.... OrtigRot ithn0 da 0 in wich th4hncz a ~d

* A single submittal may be made for a multiple unit station. The submittal

should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SN ONR-UNIT 3 6-20 23. AMENDMENT NO.

.L *

'I *

Ci*

e+:*

i O

*

I*

. * ,

0 0 1* *1* U * * I r

t r


d.Abnomal dcgradation of systems ether than these speeifled in 6.91.1.cabove dczigned to contain radioactive material resultin



SPECIAL REPORTS

6.9.2 Special Reports shall be submitted to the U. S. Nuclear Regulatory Comisio, Attetion: Document Conitrol Desk, W.shington,~ D. C~. 0555, wi th a

coyto the-NRG Regional Administrator of the Reggenalt Office of the NRC within the time period specified for each report.



SAN ONOFE-UIT 3 6-27- 2 AMENDMENT NO.


RECO AREIHION(continued)



b. Records and logs of principal maintenance activities, inspections, repair and replacement of pri-ncipal items of equipment related to nuclear safety.

c. All REPORTABLE QGGURRENGE& EVERTS submitted to the Commission.

d. Records of surveillance activities I inspections and calibrations required by these Technical Specifications.
















i. Records of Quality Assurance activities required by the QA Manual


k. Records of 0RC meetings ef-the-QSRG and the NSG reports.

1. Records of the service lives of all snubbers within the scope of Technical Specification 3/4.7.6 including the date at which the service

life commences and associated installation and maintenance records.


n. Records of reviews performed for changes made to the OFFSITE DOSE

CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.


Procedures for personnel radiation protection shall be prepared consistent with

the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered

to for all operations involving personnel radiation exposure.


6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be

barricaded and conspicuously posted as a high radiation area and entrance

thereto shall be controlled by requiring issuance of a Radiation Exposure Permit

(REP)*. Any individual or group of individuals permitted to enter such areas

shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation

dose rate in the area.

b. A radiation monitoring device which continuously integrates the

radiation dose rate in the area and alarms when a preset integrated dose

is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and

personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is

equipped with a radiation dose rate monitoring device who is responsible

for providing positive control over the activities within the area and

shall perform periodic radiation surveillance at the frequency specified

by the facility Health Physicist in the Radiation Exposure Permit.

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise

*following approved plant radiation protection procedures for entry into high radiation areas.



HIGHRADITIONAREA(Continued)

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift S.pe rse..Sper.ntendet on duty and/or health physics supervision. Doors shall remain Tocked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and *nless ahealth physics technician is in continuous attendance a flashing Tight shall be activated as a warning device. In lieu of the.stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.


6.13.1 The PCP shall be approved by the Commission prior to implementation.#


1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n. This docuentatio shall

contain: a. Sufficient information to support the change together with the

appropriate analyses or evaluations justifying the change(s);

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations-v and4


2. Shall become effective upon review and aeeep tanee- approval pursuant to 6.5.2 by the Station Manager.

** Measurement made at 18" from source of radioactivity.

* The PCP shall be submitted and approved prior to shipment of "wet" solid radioactive waste.



6.14 OFFSITE DOSE CALCULATION MANUAL (00CM)



1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n. This d .cu ...tation shal


b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations-r; and


2. Shall become effective upon review and 0eeepanei approval pursuant to 6.5.2 by the Station er.

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire 00CM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 MAJOR CHANGES TO RADIOACTI2E ASTE TREATMENT SYSTEMS DEL

.A ..fRE 1 ............... ....EN .

ENCLOSURE 2

CHANGES TO TECHNICAL SPECIFICATIONS 6.9.1.8 AND 6.14 WHICH INCLUDE THOSE CHANGES PREVIOUSLY REQUESTED IN AMENDMENT APPLICATION NOS. 122 AND 106

(PCN-419) DATED NOVEMBER 18, 1992, AND THOSE THAT ARE BEING REQUESTED IN AMENDMENT APPLICATION NOS. 124 AND 108 (PCN-364)

FOR UNITS 2 AND 3, RESPECTIVELY.

INDEX


SECTION PAGE

AUTHORITY....... ........................................ 6-43 15

RECORDS................... .............................- 1 15

6.6 REPORTABLE CQURRRGE ACTION...........................6- 15

6.7 SAFETY LIMIT VIOLATION........... .......................... 6- .. 16

6.8 PROCEDURES AND PROGRAMS... .................................- 11


6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.................. 6-466 21

STARTUP REPORT.......................... ............ 6

ANNUAL REPORTS.... ..................................

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT........6-1-123

SEM1ANNUAl ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT..... 6-4-723

MONTHLY OPERATING REPORT..............................6-123

REPRTBL OCC-URRENCES............................... 61

PROMIPT NOTIFICATION WITH WRITTEN FOLLOWUP ................ 61

THIRTY DAY WRITTEN REPORTS.............................. 6 .20

HAZARDOUS CARGO TRAFFIC REPORT......................... 6-0.24

6.9.2 SPECIAL REPORTS....................... ................... 6-20 24

6.10 RECORD RETENTION ....................................... 6-2024

6.11 RADIATION PROTECTION PROGRAM...............................-2 26

6.12 HIGH RADIATION AREA...... ................................

6.13 PROCESS CONTROL PROGRAM (PCP) ............................... 6-327

6.14 OFFSITE DOSE CALCULATION MANUAL............................. 6-428

6.15 MAJOR CHANGES TO RADOACTIVEDATE TREATNONT

SYSTEMS DELETED

.SAN ONOFRE - UNIT 2 XVII AMENDMENT NO.




6.9.1.7 DELETED

SE4ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 The Semiannual Radioactive Effluent Release Report coverin the operation of the unit during the previous 6 month: of operation ca endar year shall be submitted with4n 60 days after January 1 and l ibefore .ay. of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and sel4d waste released from the unit. The report shallI also include a summary of the quantities of solid radioactive waste shi pped f rom the untit directly to the di sposal site and the~ quant ities.6 of solid radioactive waste shipped from the unit's i ntermedi ary processor to the' disposal site. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR . 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

6.9.1.9 DELETED


6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressarizer safety valves, shall be submitted on a monthly basis to the Director,-O44icc of 4Namree rFu MantagemeM-t- U.S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

A*

*A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall

* specify the releases of radioactive material from each unit.

SAN ONOFRE-UNIT 2 6-1 23lll AMENDMENT NO. j~





1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2,n. Thi documentation shall


b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculationsI and j.


2. Shall become effective upon review and aeeeptanee approvaI pursuant to 6.5.2 by the Statio M .anager. .

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Seaeuae Pt Annual Radioactive Effluent Release Report for the period of the report 41 in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.


INDEX


SECTION PAGE

AUTHORITY...............................................6-43 15

RECORDS.................................................6-43 15

6.6 REPORTABLE GGGURRENGE, ACTION................................. 6- 4-16

6.7 SAFETY LIMIT VIOLATION.............................................. 6-44 16

6.8 PROCEDURES AND PROGRAMS........... ........................ 6-4 16


6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.......................6-1821

STARTUP REPORT.................. ..................... 6-482

ANNUAL REPORTS........................................ 6-49 Z2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT........ 6-20 23

SEMIANNUAL ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT..... 6-20 23

MONTHLY OPERATING REPORT..............................6-30 2

REPORTABLE OCCURRENCES ................................. 6 21

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP ....... ,.........6-21

THIRTY DAY WRITTEN REPORTS .............................. 6 22 X

HAZARDOUS CARGO TRAFFIC REPORT............................ 6-2-24

6.9.2 SPECIAL REPORTS............................................... 6-324

6.10 RECORD RETENTION......... .................................. 6-23 24

6.11 RADIATION PROTECTION PROGRAM.................. ....... 6-24 26

6.12 HIGH RADIATION AREA................. .........................- 2426

6.13 PROCESS CONTROL PROGRAM (PCP) ................................... 6-2627

6.14 OFFSITE DOSE CALCULATION MANUAL.................................6-26 28

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS DEL





6.9.1.7 DELETED

SEMIAN k ANNUA L RADIOACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 The Semiannua4 Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 meths of-operateo calendar yeAr shall be submitted w4th4i 60 days after Jny- 1and Juy 1 before MIay 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and -olid waste released from the .* unit. Th repotsha.l also include a suary of the quantities of soid radioactive waste shipped from the unit directly to the disposal site and the quantities.of.~ soi radieactive waste shipped from the.unit's in~ter'mediary processor to the disposal site..The material provided shall be (1) consistent

* with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

6.9.1.9 DELETED


6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer safety valves, shall be submitted on a monthly basis to the Diector,-0....e-of-Reore .. Ma0a.emeft, U.S. Nuclear Regulatory Commission, Attentio. o control fl sk, Washington, D.C. 20555, with a copy to the Regional Administrator of the Reginal Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

6o sub mitin report oin to atins thtae coang tow ade nsa

effctuing. documdditiono al reoth fallny aorcne to the r..***..'"*"-. Ot adioy atves,~t I srarn yt~ hall be submitted on ahmthchlonthlysOportteng Reportforth

*aae t A .sigl umtla be ader formtiple uistio. t

0submitta W sh udcminetn DC205,wthos setosaar copyo to altnisa

the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.






1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.!n. This documentation pal/ shall contai:


b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; and


2. Shall become effective upon review and seeeptane aE pursuant to 6.5.2 by the Station nager.

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Anrnual Radioactive Effluent Release Report for the F period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 MASA CANGES TO ACTIVE WASTE TREATMENT SYSTEMS DELE D ETO

0.............. ,::. ... .... .. . ............3. ............N T.N. .

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