Proposed Tech Specs re implementation of Generic Ltr 89-01 ...
79
. _ _ _ _ _ _ Attachment 1 ULNRC- 20 70 , PROPOSED TECHNICAL SPECIFICATION CHANGES Pages: 1-4 3/4 12-5. Insert A 3/4 12-6 1-6 3/4 12-7 3/4 3-63 3/4 12-8 3/4 3-64 3/4 12-9 3/4 3-65 3/4 12-10 3/4 3-66 3/4 12-11 3/4 3-67 3/4 12-12 3/4 3-68 3/4 12-13 3/4 3-69 3/4 12-14 3/4 3-70 B 3/4 3-5 3/4 3-71 B 3/4 3-6 3/4 3-72 B 3/4 11-1 3/4' 3-73 B 3/4 11-2 3/4 3-74 B 3/4 11-3 3/4 3-75 B 3/4 11-4 Insert AA B 3/4 11-5 3/4 11-l' B 3/4 11-6 3/4 11-2 B 3/4 11-7 3/4 11-3 B 3/4 12-1 3/4 11-4 B 3/4 12-2 3/4 11-5 6-17 3/4 11-6 Insert B 3/4 11-8 6-18 3/4 11-9 Insert C 3/4 11-10 6-18a 3/4 11-11 6-19 3/4 11-12 Insert CC 3/4 11-13 6-20 3/4 11-14 6-22 3/4 11-17 Insert D 3/4 11-18 6-24 3/4 12-1 6-25 3/4 12-2 Insert E and F 3/4 12-3 6-26 3/4 12-4 8909150097 890906 {DR ADOCK0500gg{3 -_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - - _ - - _ _ _ .
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Transcript of Proposed Tech Specs re implementation of Generic Ltr 89-01 ...
. _ _ _ _ _ _
Attachment 1ULNRC- 20 70
,
PROPOSED TECHNICAL SPECIFICATION CHANGES
Pages: 1-4 3/4 12-5.Insert A 3/4 12-61-6 3/4 12-7
3/4 3-63 3/4 12-83/4 3-64 3/4 12-93/4 3-65 3/4 12-103/4 3-66 3/4 12-113/4 3-67 3/4 12-123/4 3-68 3/4 12-133/4 3-69 3/4 12-143/4 3-70 B 3/4 3-53/4 3-71 B 3/4 3-63/4 3-72 B 3/4 11-13/4' 3-73 B 3/4 11-23/4 3-74 B 3/4 11-33/4 3-75 B 3/4 11-4Insert AA B 3/4 11-53/4 11-l' B 3/4 11-63/4 11-2 B 3/4 11-73/4 11-3 B 3/4 12-13/4 11-4 B 3/4 12-23/4 11-5 6-17
3/4 11-6 Insert B3/4 11-8 6-183/4 11-9 Insert C3/4 11-10 6-18a
3/4 11-11 6-19
3/4 11-12 Insert CC3/4 11-13 6-20
3/4 11-14 6-22
3/4 11-17 Insert D
3/4 11-18 6-24
3/4 12-1 6-25
3/4 12-2 Insert E and F
3/4 12-3 6-26
3/4 12-4
8909150097 890906{DR
ADOCK0500gg{3
-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - - _ - - _ _ _ .
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| DEFINITI0$$- '
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- 0FFSITE DOSE CALCULATION MANUAL
1.17 The OFFSITE DOSE CALCULATION h.ANUAL (ODCM) shall contain the methodology|;
and parameters used in the calculation of offsite doses due to. radioactivegaseous and liquid effluents, in'the calculation of gaseous and liquid effluentmonitoring Alarm / Trip Setpoints, an in the_c t of the EnvironmentalRadiological Monitoring Program. Ir}$ept, %OPERABLE - OPERABILITY
1.18 A system, subsystem, train, component' or device shall be OPERABLE'or |- have OPERABILITY when it is capable of performing its specified function (s),and when all necessary attendant instrumentation, controls, electrical power,cooling or seal water, lubrication or other auxiliary equipment that arerequired for the system, i,ubsystem, train, component, or device to perform'its :
-
function (s) are also capable of performing their related support function (s).,
OPERATIONAL MODE - MODE
139 e An OPERATIONAL MODE (i.e. , MODE) shall correspond to my one inclusive |'
combination of core reactivity condition, power level, anc' average reactor<
coolant temperature specified in Table 1.2.
PHYSICS TESTS
1.2.0 PHYSICS TESTS shall be those tests performed to measure the fundamental. Inuclear characteristics of the core and related instrumentation: (1) describedin Chapter 14.0 of the FSAR, or (2) authori:ed under the provisions of
. .10 CFR 50.59,' or (3) otherwise approved by the Commission.' '
-'PRESSURE BOUNDARY LEAKAGE
1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tuce |1eakage) througn a nonisolable fault in a Reactor Coolant System componentbody, pipe wall, or vessel wall.
4
PROCE55' CONTROL PROGRAM
Sck S 31.22 The PROCESS CCNTROL PROGRAM shall contain the current SmA, sampling, |analyses, tests, and determinations to be made to ensure that the processing
,
and packaging of solid radioactive wastes based on demonstrated processing of lactual or simulatad wet solid wastes will be accomplished in such a way as to j
'
assure compliance with8534884 i ::, .. .. . _
' A and State 1-
. ..
regulations, burial ground requirements, and other requirements governing I
the disposal of 4Ae.rac';oactive waste.
h to C.FR. Paxh 20flM 7/7 i&PURGE - PURGING,J
1.23 . PURGE or PURGING shall be any controlled process of discharging air or |gas from a confinement, to maintain temperature, oressure, numidity, concentra-tion or other coerating :endition, in sucn a manner that replacement air orgas is reouired to purify the :enfinement.
,
CALLAWAY - UNIT 1 1-4 Amencment No.,2.5, 25
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Insert A
The ODCM shall also contain (1) the RadioactiveEffluent Controls and Radiological Environmental MonitoringPrograms required by Section 6.8.4 and (2) descriptions ofthe information that should be included in the AnnualRadiological Environmental Operating and Semi-annualRadioactive Effluent Release Reports required bySpecifications 6.9.1.6 and 6.9.1.7.
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.- DEFINITIONS *o
{ .
DIFICNII0
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b - 32 L TCAiION s al be the nyersion wet was* s ints,. arm thI '
eet shippi bur 1E grbtm Jequiremepts. ,/ jj+. r /-
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SOURCE CHECX--
1.33 A SOURCE CHECK shall be the qualitative assessment of channel-' response j.when.the channel sensor is exposed to a source of increased radioactivity.j.
STAGGERED TEST BASIS
1.341 A STAGGERED. TEST SAb1S-shall'-consist -of:" ~~~ -"~~ " ' -
|,
a. A test schedule for n systems, subsystems, trains, or other .
. designated components obtained by dividing the specified test-interval into n equal subintervals,- and...-. - - -
,
b. The testing of one system, subsystem, train or other designatedcomponent at the beginning of each subinterval.
THERMAL POWER
1.35 THERMAL POWER shall be the total core heat transfer rate to the reactorcoolant. [
~
TRIP ACTUATING DEVICE OPERATIONAL TEST~
1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall. consist of operating the|Trip. Actur.cing Device and verifying OPERABILITY of alarm, interlock and/or
trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall includeadjustment, as necessary, of the Trip Actuating Device such that.it actuatesat the required Setpoint within the required accuracy.
~
. UNIDENTIFIED LEAKAGE
1.3 7 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGEor CDNTRDLLED LEAKAGE. j
L UNRESTRICTED AREA '
l.38 An UNRESTRICTED AREA shall be any crea at er beyond the SITE BOUNDARY jaccess to wnich is not controlled by the licensee for purposes of protection '
of individuals from exposure to radiation and radioactive materials, or anyi area within the SITE BOUNCARY used for residential quarters or for incustrial,L commercial, institutional, and/or recreational purcoses.
.
CALLAWAY - UNIT 1 1-6 Amencment No. 75, 23, 2E.
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9
_ _ _ _ _ - _ = _ - _ _ _ _ _ _ - _ - _ - _ - _ _ - - - - - - - - - - - - - - - - - - - -
. - - _ - . _.
Y/$(UMENTATION
:' -RAD 10A VE LIQUID EFFLUENT MONITORING INSTRUMENTATION
. LIMITING C ITION FOR OPERATION 7
|- 3.3.3.9 'The radio tive liquid effluent monitoring instrumental' n channelsshown in Table 3.3 2 shall be OPERABLE with their Alarm / Trip tpoints set to
ensure that the limit of Specification 3.11.1.1-are not exc ded. The Alarm /Trip Setpoints of thes channels shall be determined and justed in accordancewith the methodology an parameters in the OFFSITE 00SE ALCULATION MANUAL(00CM).
APPLICABILITY: At all time-
| ACTION: ,
With a radioactive lic 'd efflup t montioring instrumentation channela.Alarm / Trip Setpoint less consgtvative than required by the above
g; -specification..immediatel spspend the release of radioactive liquidi
effluents monitored by they fected= channel, or declare the channelinoperable.'
b. With less than the mirlimum number f radioactive liquid effluentmonitoring instrume fation channels PERABLE, take the ACTION shownin Table 3.3-12. estore the inoperab e instrumentation to OPERABLE-status within t time specified in the KTION, or explain in thenext Semiannisal Radioactive Effluent Releas Report, pursuant to
) Specification [6.9.1.7,whythisinoperability as not correctedwithin the 1me specified.'
c. The pro sions of Specifications 3.0.3 and 3.0.4 ar not applicable..
| SURVEILLANCE EOUIREMENTSI
4.3.3.9 ach radioactive liquid effluent monitoring instrumentation chan Isna11 e demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHE , CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequenc' s shown in Table 4.3-8.
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Table 3.3-12 (Continued),
!- ACTION STATEMENTS'
ACTION 31 - With the number of channels OPERABLE less than required by the is{nimumChannelsOPERABLErequirement,effluentreleasesvia.pathway may continue for up to 14 days provided that priorini' iating a release:
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At least two independent samples are analyzed in . cordancea.wit Specification 4.11.1.1.1, and
b. At leas.t two technically qualified members of ha facility.staff ihgiependently verify the release rate calculations anddischarge line valving.
Otherwise, su nd release of radioactive ef luents via thispathway.
...
ACTION 32- With the number of\ channels OPERABLE Les than required by theffluent releases via this
MinimumChannelsOPEqABLErequirement, pathway may continue (or up to'30 day provided grab samples are4 :.analyzed for principai\ gamma emitter and 1-131 at a lower limit L-
OCof' detection as specifikd in Table .11-1:
a. At least 'once per 12 urs w n the specific activity of the h! secondary coolant is greate tnan 0.01 microcurie / gram DOSE< EQUIVALENT I-131, or \ f
. b. .At least once per 24 h rs\henthespecificac'tivityofthe''
secondary coolant is ss than or equal to 0.01 microcurie / gramCOSE EQUIVALENT I-13 .
ACTION 33-WiththenumberofchMnelsOPERABLElessthanrequiredby.the'
Minimum.-Channels OP ABLErequirement,\effluentreleasesviathispathway may contin for up to 30 days p ovided that prior toinitiatir.g a rele se:
At least t o independent samples are an dyzed in accordancea.with Spe fication 4.11.1.1.1, and N
\b. At le t two technically qualified members of the facilityg
staf independently verify the release rate caipulations andd harge line valving;
nisOthe7 wise, suspend release of radioactive effluents viapa way.
ACTION 34 - ith the number of channels OPERABLE less than required by qeMinimum' Channels OPERABLE requirement, effluent releases via hispathway may continue for up to 30 aays provided the flow rate 1estimated at least once per 4 hours during actual releases. Puma
performance curves generated in place may be used to estimatei
flow.
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CALLAWAY UNIT 1 3/4 3-65
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TABLE 4.3-B-(Continued)- -
N TABLE NOTATIONS
The ANAltG CHANNEL OPERATIONAL. TEST.shall also demonstrate t) automatic(1) ~**
- isolation %f this pathway and control room alarm annuncia fn occur as-appropriate f any of the following conditions exists:
a .- Instrument indicates measured levels above th larm/ Trip 5etpoint
|. (isolation and arm), or
b. Circuit failure (' alarm only), or
c. . Instrument indicate ownscale i ure (alarm only), or
d. Instrument' controls not in perate mode (alarm only),s
(2) The initial CHANNEL CALIBRATION haNbeperformedusingoneormoreofd solidhstandards certified by the
the reference (gas or liquid p(N85) or usihg' standards that have beenNational Bureau of Standards /obtainedfromsupplierstpetparticipateinmgasurementassuranceactivi-
3
itsintendedrangeof(tandardsshallpermitchybratingthesystemoverties with NB5. These sf nergy, measurement range, And establish monitor
response to a solid calibration source. For- subsequent CHANNEL CALIBRATION,.NBS traceable stan6ard (gas, liquid, or solid) may ben sed; or a gas,liquid, or soljd source that has been calibrated by relit {ng it to equip-mentthatwaypreviously(within30 days)calibratedbythe- ame geometryand type o.f source standard traceable to NBS.
1 /, '
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods,
, of ye' lease. CHANNEL CHECK shall be made at least once per 24 hours o'days on which continuous, periodic, or batch releases are made. .
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CALLAWAy - UNIT 1 3/4 3-57,
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REVISloy 3.
.
INSTRUMENTATION,
ADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
L ITING CONDITION FOR OPERATION
.
3.3.3.1- The radioactive gaseous ef fluent monitoring instrumentation annelsshown in abic 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoi s set toensure tha the limits of Specifications 3.11.2.1 and 3.11.2.5 are t exceeded. !
The Alarm /Tgd and adjusted in accordance with the methodologySetpoints of these channels meeting Specification 11.2.1 shall
be determine parametersin the ODCM.
APPLICABILITY: A shown in Table 3.3-13.'
ACTION:
a. With a radioa tive geseous effluent. monitoring instrumentationchannel Alarm / Trip Setpoint less conse/vative than required by thegabovetspecificatiqn, immediately susp'end the release of radioactivegaseous effluents Inonitored by th affected channel, or declare thechannel inoperable.
b. With less than the minimum pumber of radioactive gaseous effluentmonitoring instrumentati channels OPERABLE, take the ACTION shown.in Table 3.3-13. Rest e inoperable instrumentation to OPERABLE
I status wit.ein the tim spect ed in the ACTION, or explain in the 3'next Semiannual Rad etive E luent Release Report, pursuant to . '{Specification 6.9, .7, why thi(s operability was not corrected ,
d thin th? .ne specified.
c. The provisi s of Specifications 3.0. and 3.0.4 are not applicable.
SURVEILLANCE RE IREMENTS
4.3.3.10 ) h radioactive gaseous effluent monitoring trumentation channelshall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK HANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TE T at the frequen-cies hown in Table 4.3-9.
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I TABLE NOTATIONS. N4
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1e: * :A a11 times.** Duri WASTE GAS HOLD UP SYSTEM operation. 7 g>
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ACTION STATEMENTS bACTION 38 igh the number of channels OPERABLE less than required by e
Miniaum Channels OPERABLE requirement, the contents of the tank (s)may 6e released to the environment for up to 14 days pro ded that
~
prior lo initiating the release:a. 'At least two independent samples of the tank's c tents are'
. analyze'd and
b. At least two technically qualified members o the facility. staff indephdently verify the release rat calculations anddischargeva1\elineup.
''
Otherwise,. suspend lease of radioactive e 'luents via thisf: pathway. .
ACTION 39 - With the number of channels OPERABLE le s than required by theMinimum Channels OPERABLE \ requirement effluent releases via thispathway may continue provi' ed the f1 rate is estimated based on-dfan status and operating curves or ctual measurements at leastonce per 4 hours. \
ACTION 40 - With the. number of channels OPE BLE less than required by the.} Minimum Channels OPERABLE regt) rhment, effluent releases' via this'
pathwaymaycontinueforupp630'daysprovidedgrabsamplesaretaken at least once per 12 Jiours arid these samples are analyzedforradioactivitywithin)4 hours.
ACTION 41 - With the number of chant)61s OPERABLE one less than required bythe Minimum Channels 0 ERABLE requirement, PURGING of radioactiveeffluents via this p way may continue for 24 hours. With bathchannels inoperable immediately suspend P' URGING of radioactiveeffluents via this athway.
jACTION 42 - With the Outlet *ygen Monitor channel inoperable, operation of
the system may ontinue provided grab samples are taken and analyzedsat least once er 24 hours. With both oxygen channels or both the
inlet oxygen nd inlet hydrogen monitors inoperable, suspend oxygensupply to e recombiner. Addition of waste gas th the system maygcontinue ovided grab samples are taken and analyzed at least onceper 4 ho rs during degassing operations and at least bnce per24 hour during other operations. \
ACTION 43 - With he number of channels OPERABLE less than required by theMin' mum Channels OPERABLE requirement, effluent releases Qa the
ected pathway may continue for up to 30 days provided samplesa
re continuously collected with auxiliary sampling equipmentMsrequired in Table 4.11-2.
{ACTION - With tne number of channels OPERABLE one less than required by t'e fMinimum Channels OPERABLE requirement, suspend oxygen supply to jthe recombiner. '
AC ON 45 - Flow rate for this system shall be based on fan status and operatingcurves or actual measurements.
CALLAWAY - UNIT 1 3/4 3-71 Amendment No. 20)
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___ _ _ _ - _ _ _ _ _ _ _ _ _ _
f _ _ _.,
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). REVislON 2
,
#-
,
i ] .- TABLE 4.3-9 (Continued)
TABLE NOTATIONS,
.
" At all mes.
** During WAS GAS HOLDUP SYSTEM operation.
(1) The ANALOG C NNEL OPERATIONAL TEST shall also demonstratefhat automaticisolation of t *s pathway and control room alarm annunciation occur asappropriate if a of the following conditions existst p
a. Instrument in cates measured levels above the arm / Trip Setpoint(isolation and alarm); or
\b. Circuit failure (ala ly), or ) ,
Ohc. Instrument indicates a downscale failure (alarm only), orN operate / c,\nmode (alarm only).d. Instrument controls not set i
-''(2) The ANALOG CHANNEL OPERATIONAL TEST'sQaalso demonstrate that control f-room alarm annunciation occurs if any nf the following conditions exists:/
Instrument indicates measured ieve\ N)Q-
ls\above the Alarm Setpoint, ora.
b. Circ'uit failure, or' |,
'J ')c. Instrument indicates ownscalefailure,o(d. Instrument controls et set in operate mode.
i
(3) The initial CHANNEL CA BRATION shall be performed using one or more ofliquid and solid) standards certl ied by the National
NBS)orusingstandardsthathave(beenobtainedfromthe reference (gas oBureau of Standards gsuppliers that par icipate in measurement assurance activi4ies with NBS.Thesestandardspsallpermitcalibratingthesystemoveritsintendedrangeof energy, meaperement range, and establish canitor response \to a solidcalibration source. For subsequent CHANNEL CALIBRATION, NBS t aceablestr.ndard (gpl, liquid, or solid) may be used; or a gas, liquid, r solidsource that' has been calibrated by relating it to equipment that aspreviousJf(within30 days)bythesamegeometryandtypeofsourctraceab e to NBS.
(4) The ANNEL CALIBRATION shall include th.e use of standard gas samplesto aining a nominal:
One volume percent hydrogen, balance nitrogen, and
b. Four volume percent hydrogen, balance nitrogen.
-
CALLAWAY - UNIT 1 3/4 3-74
.
_ _ _ . _ _ _ . - _ _ _ _ _ . - _ _ . . _ _ _ . _
-!g -.. .
. . - ..
d.
RE'j Stoy y
TABLE 4.3-9 (Continued) ;
_.-
TABLE NOTATIONS (Continued) .
,
-(5) The C NEL CALIBRATION shall include the use of stan ard gas samplescontain1 a nominal:
a. One volwe percent oxygen, balance nitrogen and ,
b. Four volum p reent oxygen, balance nityogen.
(6) -The CHANNEL CALIBRATION shall include the/use of standard gas samplescontaining a nominal: /
a. 10 ppm by volume oxy , balance nitrogen, and .|-
fb. 80 ppm by volume oxygen, .alance nitrogen..
Ifflowrateisdeterminedby/exh pst fan status and fan performance.
(7)Li ' curves, the following surveillance 's rations shall be performed at least
once per 18 months: /6
/~
a. The specific vent flows by direct m urement, orl'
b. -The differential pressure across tile e ust fan and vent flowestablished by the fan's " flow-AP" curve, or
/} The fan motor horsepower measured and vent f w established by thec.-
_,fan's'" flow-horsepower" curve.
,/'! Go N
D9 (.p' vw 6
Yaheew
>,
CALLAWAY - UNIT 1 3/4 3-75
. _ - - ..
_ _ _ _ ._
2NSERT AA'g ,
i .-
INSTRUMENTATION'
F , WASTE _ GAS HOLDUP SYSTEM
b. , EXPLOSIVE GAS' MONITORING INSTR _UMENTATION
LIMITING CONDITION FOR OPERATION
3.3'.3.10 _At least one hydrogen and both the inlet'andoutlet oxygen explosive gas monitoring instrumentationchannels for each WASTE' GAS HOLDUP SYSTEM recombiner shallbe OPERABLE.with their ALARM / TRIP SETPOINTS set to ensurethat the limits of Specification 3.11:.2.5 are not exceeded.
APPLICABILITY: During WASTE GAS HOLDUP SYSTEM operation.
ACTION:
.a. .With an outlet oxygen monitor channel inoperable,operation of the , system may continue provided: grabsamples are taken'and analyzed at least once per-24 hours.
1
b. ' With both. oxygen or both_ hydrogen channels or boththe inlet oxygen and inlet hydrogen monitorchannelsLfor one recombiner inoperable, suspendoxygen supply to the recombiner. Addition ofwaste gas to.the system may continue provided grab !
samples are taken and analyzed at least once per 4hours during' degassing operations and at leastonce per 24 hours during other operations,
c. The provisions of Specifications 3.0.3 and 3.0.4i
are not applicable.
SURVEIL _ LANCE REQUIREMENTS
4.3.3.10 Each explosive gas monitoring instrumentationchannel shall be demonstrated OPERADLE by performance of:
,
a. A CHANNEL CHECK at least once per 24 hours,,
!
b. An ANALOG CHANNEL OPERATIONAL TEST at least onceper 31 days, and
c. A CHANNEL CALIBRATION at lease once per 92 days I
with the use of standard gas samples containing anominal:
1
1l
-_ - _ - _ - _ _ _ - _ . . _ - _
1
INSERT AA continued
INSTRUMENTATION',.
. WASTE GAS HOLDUP SYSTEM
' EXPLOSIVE GAS MONITORING _ INSTRUMENTATION-
SURVEILLANCE REQUIREMENTS CONTINUED
L 1)' One volume percent hydrogen, balance nitrogen
|and four volume percent hydrogen,. balancenitrogen for the hydrogen monitor, and'
| .~ 2) One volume percent oxygen, balance. nitrogen," .and four volume percent oxygen, balance
'
: nitrogen for the inlet oxygen monitor, and
3) 10 ppm by volume oxygen, balance nitrogen and80 ppm by volume oxygen, balance nitrogen forthe outlet oxygen monitor.
,
1
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. ... . _ : ::. . . a ,_ . ' . .. ,..n .. ' . . . . r W, .,, ,
*,'
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.' .- . . < . . . - ... . . . .
I
.
REVISIob; .
3 .11 RADIOACTIVE EFFLUE U S,,
y 1 LIQUID EFFLUENTS*
CONCEH1 10N
LIMIf1NG COND 3.10N FOR OPERATION
3. l t.1.1 The concent 4 tion of radioactive material released in liquid effluentsto UNRESTRICTED AREAS (' Figure 5.1-4) sh611 be limited to the concentrationsspecified in 10 CFR Part . Appendix B, T,able II, Column 2, for radionuclides
ases. For dissolved or entrainedainednobleplimitedto2x104other than dissolved or enshall b - microcurie /mlnoble gases, the concentrate
total activity.
APPLICABILITY: At all times.-
AC110N:
With the concentration of radioactive material released in liquid effluents togUNRESTRICTED AREAS exceeding the above li ts, immediately restore the concen-tration to within the abo /e limits.
~
Si!RVEILLANCE REQUIREMENTSfm/
1
4.11.1.1.1 R ioactive liquid wastes shall be sampled a analyzed accordingto the sampi ng and analysis program of Table 4.11-1.
4.11.1.l e The results of t.he radioactivity analysis shall be sed in accordance j
fwith the methodology and parameters in the ODCM to assure that t concentrations {at the/ point of release are maintained within the. limits of Speci ation3.11 l.l.
9 opcfc\10
wof"4 .606g#x 1
\|
i
!
Call AWAY - IINil 1 3/4 11-1..y
!
|
t
1 !
_ _ _ _ _ _ _ - _ _
- _ _ _ _ _ ________________ _ ____ _ _ ,
, $.d : . . - '' . * 5.- -~ ' " * * ~* '
. . . - -
- Ls'o' . 0.2-~~ -
.
- pp, Amendment No. 2*
..
TABLE 4.11-1
RADIbACTIVELIOUIDWASTESAMPLINGAND-ANALYSISPROGRAM. . . ,.;.
'
, .j:..
' *
"~
LOWER LIMIT. MINIMUM OF DETECT j
LIQUID RE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLDP|~''
TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)
1. Batch Waste P P '.Release Ea Batch Each.Baten- Principal Gamma Sx 0
'
Tanks (2) Emitters (3) j I,
[# -6I-131 1x10\ !a. Waste rMonitor
Dissolved a /.- 1x10''[.
Tank P M vOne Batch /M Entrained asas '
__-
(Gamma itters) .
b. SecondaryLiquid -5Wasta P M H- 1x10-
Monitor Each Batch Composite {,, 7
Tank ss Alpha 1x10
'
w. '_'Tc Discharge P Q Sr-k, Sr-90 5x10'8g ,[. 4)' Monitor Each Batch Composi' -6
Fe-55\C'
. Tank 1x10
\ 72. Continuous W Principal G ia 5x10'
Releases (5) Daily (6) ,,p,,$g,(4) hitters (3)Gran Sample
/-6I-131 \ 1x10
\SteamGenerator N .cBlowdown M M Dissolved and 1210 "
Gr Sample Entrained Gases(Gamma Emitters)
0hM H-3 1x10Daily (.6) Compos'ite(4)
7.
Grab' Sample Gross. Alpha 1x10
~8Q Sr-89, Sr-90 5x10 \
Daily (6) Composite (4) NyGrab Sample . Fe-55 1x10
.
3/4 11-2CALLAWAY - UNIT 1 ,,
.
--- _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _
|g" - . . . , _
.'., ,
; ., , .- e ,,,, j.- -
.. ^ 7 , , ., ,. - .,
i. .' .
> ...: .:... h _ _ w .a .... n .t :-,o h :...--.-.'-2._.,, . . : . _.2.. .:. . .,4 ' i . ~ ,- ~~' ' v' ' :r: ,s ..,
'
J '3 - REVISlon 1-t-
l AHLI' 4.11- 1 (Continued)..
- TABLE NOTATIONS
(1)The LD is defined..for purposes of these specifications, as the s llestL
conc tration of radioactive material in a sample that will yield net
| count, above system background, that will be detected with 95% p obability.with on' 5% probability of falsely concluding that a blank ob rvation
. represent a "real" signal.
'For a parti lar measurement system, wh4ch may include rad chemicalseparation:
4.66 s 0hLLD =
E V *\ .22'x 108 Y exp (-Mt)
Where:
LLD = the "a prior 1' lower limit of detect on (microcuries per unit ..
mass or volume),
the standard devia ion of the bac round counting rate or ofs :b
the counting rate of a bl k sample appropriate (counts per -
minute),
4.s per disintegration),E = the counting efficiency ( ug j...~s
V = the sample size (units of a or volume),
2.22 x 106.= the number of disinteg tions per minute per microcurie,
Y = the fractional rad' chemical yiel , when applicable,*
A = the radioactive ecay constant for th particular radionuclides(s 3), and
i
at = the elaps time between the midpoint of ample collection !
and the time f counting (s).
Typical v ues of E, V, Y, and at should be used the calculation,
it shuuld recognized that the LLD is defined as an a_ p ori (before .
Lhe fact limit representing the capability of a measuremen system and !
not as n a posteriori (after the fact) limit for a particula measurement.
(2)A b ch release is the discharge of liquid wastes of a discrete olume. kPr ur to sampling for analyses, each batch shall be isolated, and
wn thoroughly mixed by a method described in the ODCM to assurerepresentative sampling.
6
CALLOWAY - UNIT 1 3/4'11-3
_ - _ _ _ _ -
_ _ _ _ _ - - _ . - _ _ _
. . . . .. -.. . - .-- - -- . ..
.- . > . ..
. . . .a. . .. . ... . ... ... ; u.a. .w: . . . w . . ~ . , - . ., ;, a.- x .= . . .- . . . . L r. a.. .a._v.u.c.w.;. . .:
REVISION'
TABLE 4.11-1 (Continued) Q'b'
TABLE NOTATIONS (Continued),
(3)The prin algammaemittersforwhichtheLLDspecificatjenapplies.Include the ollowing radionuclides: Mn-54,Fe-59,Co-J5,Co-60,In-65,Mo-99, Cs-134 s-137, Ce-141, and Ce-144. -This list <loes not mean thatjonly these nuc1 are to be considered. Other gansna peaks that areidentifiable, toge with those of the above nuc11 des, shall also beanalyzed and reporte the Semiannual Radioactive Effluent Release Reportpursuant to Specificati g6.9.1.7, in the format outlined in RegulatoryGuide 1.21, Appendix B, Rev sion 1, June 1974.
(4)A corrposite sample is one in w h th antity of liquid sampled isproportional to the quantity of NJid waste discharged and in which theJmethod of sampling employed resu tt h a specimen that is representativeof the. liquids released. Pri o anaTy is, all samples taken for thecomposite shall be thoroughl ixed ,in or for the composite samples'
to be representative of th- ffluent release. ,.
,
'
(5)A continuous release i / he discharge of liquid w tes of a nondiscretet
volume, e.g., from olume of a system that has an ' ut flow during thecontinuous releas
(6) Samples shall e taken at the initiation of effluent flow and t least onceper 24 hour thereafter while the release is occurring. To be resenta-
@h'.tive of -e liquid effluent, the sample volume shall be proportion to the
efflue stream discharge volume. The ratio of sample volume to effl t ':-disc rge volume shall be maintained constant for all samples,taken forth composite sample.
.
w.
CALLAWAY - UNIT 1 3/4 11-4 -
_
_ _ -_ _
. ..
'.- . .- \.Fh * * :* - - - * .
- ... ..:...- ..-.=.z_ -. ._ ; . e .. .. . ;.2. ._ . =. :1. e.r.: . , .u ; . . 9 .. . -. -.
- . ....=..._.:....
|
1
iREVISION 3.
D10 ACTIVE ~ EFFLUENTS*
~
. ',}' -,
.,j
LIMITING ONDITION FOR OPERATION I
3.11.1.2 The se or dose commitment to a MEMBER OF THE PUBLIC fr radioactivematerials in liq 'd ef fluents released, from each unit, to UNREST CTED AREAS(see' Figure 5.1-4) hall be limited: i
a. During any alendar quarter to less than or equal 1.5 mrems tothe whole bo .and to less than or equal to 5 mre s to any organ,""
b. During any calen r year to less than or equ to 3 mrems to thewhole body and to ess than or equal to 10 ems to any organ.
APPLICABILITY: At all times.**
O4AC110N:
a. With the cair.~ated dose om the r ease of radioactive materialsin liquid ef .ents exceedi g ar.y f the above limits, prepareand submit t. the Commission wit n 30 days, pursuant to Specifica-tion 6.9.2, a Special Report t identifies the caus,e(s) for exceeding
,|- the limit (s) and defines the rective actions that have been taken d.
%Qf to reduce the releases and t e oposed corrective actions to be taken Dto assure that subsequent r less will be in compliance with the
above limits. This Speci Report shall also include: (1) theresults of radiological nalyses o the drinking water source, and h(2) the radiological i act on finis d drinking water supplies with-
regard to the require nts of 40 CFR rt 141, Clean Drinking g*
Water Act.* K*
b. The provisions of specifications 3.0.3 an 3.0.4 are not applicable. Qs
SURVEILLANCE REQUIREME S ,:
4.11.1.? Cumul ive dose contributions from liquid effluents for the currentcalentlar quart r and the current calendar year shall be determ .ed in accordancewith the met dology and parameters in the ODCM at least once pe 31 days.
9 he equirchshtfoi ACTION a.(1) and (2) are applicaDie only if drinki water
ply is taken from the receiving water body within 3 miles of the plan.t
scharge. In the case of river-sited plants this is 3 miles downstream ly.,
*
-
CALLAWAY - UNIT 1 3/4 11-5
_ _ _ _ _ _ _ _ _ _ _ _
;
. . , m. .. c .. . a. . . . .. , . . . ,
. . ..L2 :.J.::.a. :;1 f w i ....x ;. .a.i:.. . :. ... . ....
u w.::~.aJ ..=
RUISION 1-
, .. . , m y r.. 9'c. ,1
R 10 ACTIVE EFFLUENTSm\ ' ' * 'i
-
LIQU19 RADWASTE TREATMENT SYSTEMdi-
LIMITING NDITION FOR OPERATION:
|
|
3.11.1.3 lhe L uld Radwaste Treatment System shall be OPERABLE and a repriateportions of.the sygtem shall be used to reduce releases of radioacti' ty when
| the projected duses due to the liquid effluent, from each unit, to RESTRICTED
AREAS (see Figure 5. -4) would exceed 0.06 mrem to the whole body r 0.2 mrem to }_any organ in a 31 day eriod.
hAPPLICABilliY: At all t es,'
AC110N: .
'' a. With radioactive li id waste being discharg without treatment andin excess of the abov glimits and'any porti of the Liquid Radwaste
Treatment System not irt peration, prepare and submit to the Commissionwithin 30 days, pursuan o Specification 6.9.2, a Special Report that ,
includes the following in rmation:
1. Explanation of why liquid radwp te was being discharged without b.Gtreatment, identification f ny inoperable equipment or
subsystems, and the reason r the inoperability,C h.
' \2. Action (s)- taken to resto the'inopera'ble equipment to OPERABLE Y .f.~
status, and
3. Summary description f action (s) then to prevent a recurrence.!
h. -the provisions of Spe fications 3.0.3 and .0.4 are not applicable.
%URVLlLLANCE REQUIREMENTS.-.
-
I
4.11.l.3.1 Du es du to liquid releases from each unit to UNRES ICTED AREAS j
.h.ill be prujected t least once per 31 days in accordance with t . methodology {
|!and parameters i the 00CM when Liquid Radwaste Treatment Systems a not beingtully utilized.
4.11.1.3.2 he installed Liquid Radwaste Treatment System shall be cons ered |
OPERABLE meeting Speci fications 3.11.1.1 and 3.11.1.2.
!
i
1'
.
'',/.
CAtLAWAY - UNIT 1 3/4 11-6 i
1
1
--...--.m___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
__ _, _.--
, , ,,
o.e-+... . . . ja a-y. 4.~ - .+9~--=-. , . - - ~ . ;p., , r~v * *. tr.. L, } * ..x;. ~ *'. * . - ?*,,a. , ,
l'i d IL: d d_l': * h _A_:.'.l ...-J..S.di. M 2;..E E.T.A. h R'.Rr M Cs 0n:P M' "; "'
) ADI0 ACTIVE! EFFLUENTS
3 .11.2 GASEOUS EFFLUENTS Q005 ATE
:
LIMITING ONDITION FOR OPERATION
,
3.11.2.1 The se rate due to radioactive materials re ased in gaseouseffluents from e site to areas at and beyond the SIT BOUNDARY (see Figure5.1-3) shall be 'mited to the following:
.
a. For noble ases: Less than or. equal toj600 mrems/yr to the wholebody and 1 s than or equal to 3000 mr ms/yr to the skin, and
b. For Iodine-13 - and 133, for tritiu . and for all radionuclides hin particulate orm with half-liv greater than 8 days: Less thanor equal to 150 mrems/yr to any organ. 0 -
APPLICABILITY: At all times.
ACTION: Y
With the dose rate (s) exceeding t . above limits, immediately rest. ore therelease rate to within the above 1 it(s)..
,p. ...
gW 0Q
SURVEILLANCE REQUIREMENTS i
44.11.2.1.1 Thedoserpeduetonoblegasesingaseouseffluentsshallbe hdetermined to be with n the above limits in a ordance with the methodologyand parameters in t ODCM.
4.11.2.1.2 The' e rate due to Iodine-131 and 13- tritium,abdallradionuclides i articulate form with half-lives g ter than 8 days in gaseouseffluents shal e determined to be within the above 'mits in accordance withthe methodolo and parameters in the ODCM by obtaining representative samplesand performi g analyses in accordance with the sampling a analysis programspecified i Table 4.11-2.
..
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.TABtF 4.11-2 (Continued) ' f ' .\
,' ;~yI,
,.
TABLE NOTATIONSu. .
-
(1)th. LLD is defined, for purposes of these specifications, as the snallestconc tration of radioactive material in' a sample that will yield a net -count, bove system background, that will be detected with 95% probabili .
with oni 5% probability of falsely concluding that a blank observatio |
represent a "real" signal.
For a partic ar measurement' system, which may include radiochemi el -
separation:
4.66 s "b
LLD =E V 2}R2 x 108 - Y exp (-Mt)
Where:
~ icroCuries per unitLLD = the "a priori" 1 wer limit of detection mmass or volume),
of the backgr /und counting rate or.ofs = the standard deviatio'thecountingrateofabla%nkb
ample as ppropriate (counts perminute),,
mE = the counting efficiency (coun per disintegration), 9MV = ~ the' sample size (units of ss ume),
2.22 x 106 = the number of disintegrations per minute per microcurie,j
Y = the fractional radi emical yield, when plicable.
A = the radioactive decay constant for the particular radionuclides g
(s 8), and- J,
at = the elapsep time between the midpoint of sample llection andthe time of comnting (s).
Typical va es of E, V, Y, and at should be used in the ca lation.ia
It shoJId'b recognized that the LLD is defined as an a_ priori (bef'
t.he fact) imit representing the capability of a measurement system anot as a posteriori (after the fact) limit for a particular measurem t,
Y ~'
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'#CALiAWAY - UN!T I 3/4 11-10
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REVISloy 3 . - - .
TAFLE 4.11-2 (Continued). . . .-$, ,
},4 TABLE NOTATIONS (Continued)
(' he principal gamma emitters for which the LLD specification applii lude the following radionuclides: Kr-87 Kr-88, Xe-133,Xe- 3m, Xe-135, and Xe-138 in noble gas releases and Mn-54, F 9, 1~ ~ ~ "
Co-58, Co-60, In-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, a Ce-144 in~
.
lodine d particulate releases. This list does.not mean tbit only thesenuclides e to be considered. Other gamma peaks that ar identifiable,
together wi those of the above nuclides, shall also b nalyzed and-reported in t Semiannual Radioactive Ef fluent Releasp Report pursuantto $pecificatio 6.9.1.7, in the-format outlined in Rdgulatory Guide 1.21Appendix B. Revis n 1, June 1974
(3) Sampling and analysis hall also be performed fp lowing shutdown, startup,or a IHERMAL POWER chan e exceeding 15% of RA D THERMAL POWER within 1huur p+riod.
(4) Tritium grab samples shall b taken and ahalyzed at least once per 24 hours[when the refueling canal is fl ded. ..
,(5) Tritium. grab samples shall be take.<and analyzed at least once per 7 days-
from the ventilation exhaust from th spent fuel pool area, whenever spents
fuelisinthespentfuelpool./ Grab mples need to be taken only whenspent fuel'is in the spent fuel pool.
pg /.. .
-(6)The ratio.of|the sample flow rate'to the sam d stream flow rate shall>+ *
V be known f or the time perj6d covered by each d e-or dose rate calculationmade in accordance withw$ specifications 3.11.2.1, .11.2.2, and 3.11.2.3.
/(/) Sample < shall be changed at least once per 7 days an4 analyses.shall be
completed within 4,B' hours af ter changing, or af ter rem val from sampler.For unit vent, sampling shall also be performed at leas -once per 24 hourslor at least STARTUP or T RMAL POWER changeexceedingly [/daysfollowingeachshutdown,of RATED THERMAL POWER withir) a 1-hour period nd analyses
- shall be completed within 48 hours of changing. When samples ollectedfor 24 ho.urs are analyzed, the corresponding LLDs may be increa d by afactor of 10. This requirement does not apply if: (1) analysis .ows
that tlie DOSE EQUIVALENT I-131 concentration in the reactor coolant ~ asnot fncreased more than a factor of 3, and (2) the noble gas monitorshods that effluent activity has not increased more-than a factor of 3. .A
(8)bontinuous sampling of the spent fuel building exhaust needs to be perform/ only when spent fuel is in the spent fuel pool.
.cd
kD
h CAILAWAY - UNIT 1 3/4 11-11
,
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.
./,d!3!'!E REVISION 1~
L q!
- R 10AC11VE LIFLUFNih|,
- ' ,A1: DOSE NOBLE CASES / .;;Tgf
LIMITING CO ITION FOR OPERATIONi
|. . . .. .: _ . - .3.11.2.2 The air se due to noble gases released in gaseous effluents, fromeach unit, to areas'et and beyond the SITE BOUNDARY (see Figure 5.1-3) shall,
~
L be limited to the follh ing: /k /
a. During any calenu.ar quarter: Less than' or equal to 5 mrads forgamma radiation ann less than or. equal to 10''arads for beta radiation,and /
/b. During any calendar year Less than or' equal to 10 mracs for gamma
radiation and less than o qual to 20 mrads for beta radiation. .
/
APPLICABILITY: At all times. / ~ 9
...
,
ACTION: //r
a- With the calculated air dose from rad tactive noble gases in gaseous.
ef fluents- exceeding any,4f the above linh(o 4' specification 6.9.2, as, prepare and ' submit to
the Commission within 30 days, pursuant tSpecial Report that)$entifies the cause(s) for exceeding the limit (s) ,
and defines the-coprirctive actions that have bh n taken to reduce -|;j.gthe releases and the proposed corrective actionsh o be. taken to assure 't -fthat subsequenyreleases will be in compliance with the above limits.
h. The provisipo of Specifications 3.0.3 and 3.0.4 are applicable.
\ '
SURVEILLANCE REQUIREMENTS
4. l!.2.2jtumulative dose contributions for the current calendar quarter andcurrentjtalendar year for noble gases shall be determined in accordance withthe thodology and parameters in the ODCM at least once per 31 days.
l
c co q-
8h |_3.
CAIIAWAY - ltNI1 1 3/4 11-12
;_
, = = . - - -. . - . .-
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REVISION 1=-
i RAD 10ACilVE EFFLUENIS .1
'.;.I ~ E'- 10 DINE-131 AND 133, IRITlUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM.
,p'
.
LIMIT! CONDITION FOR OPERATIONI
1
J 3.11.2.3 lh dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133,pritium,--
.and all radioritplides in particulate form with half-lives greater than 8 days' "
in gaseous effl nts released, from each unit, to areas at and be phd the SITEBOUNDARY (see Fig e 5.1-3) shall be limited to the following:-
-
-
During any alendar quarter: Less than or equal to 7.5 mrems to anya.organ, and
b. During any cale at year: Less than or equal 'o 15 mrems to.anyorgan. ..
~
APPLICABILITY: At all times.--
ACTION:' ,,
With the calculeted dose from thy release of Iodine-131 and 133,a,tritium,andradionuclidesh rticulate form with half-lives greaterthan 8 days,.in gaseous eff ts exceeding any of the above limits,prepare and submit to the M ion within 30 days,' pursuant to Speci-
Q~ lication 6.9.2, a Specia Report'that ide'ntifies the cause(s) for' .. . ; ; 7 * exceedi'ng the limits a defines the, corrective actions that have been
' .'' * :taken-to reduce ^the easesandthehoposedcorrectiveactionstobetaken to assure th subsequent releases,will be in compliance with theabove limits. -
.4 are not applicable.of Specifications 3.0.3 and 3}q\
b .- The provision-
SURVEILLANCE REOU MENTS \s
4.11.2.3- mulative dose contributions for the current calenda qbarterandcurrent lendar year for lodine-131 and 133, tritium, and radionuclides inpartic ateformwithhalf-livesgreaterthan8daysshallbedetermind(inacco ante with the methodology and parameters in the ODCM at least once'per31 ays.
." ()NV
90 e w\9 &jUiCALLAWAY - UNil 1 3/4 11-13
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!,o t ate 'sp REVISIoy.1-.
,
R 0 ACTIVE EFFLUENTS
$)-GAS S RA0 WASTE TREATMENT .iYSTEML:Jy~ ,
|- LIMITIN CONDITION FOR OPERATION .' -
|
|'
3.11.2.4 The ENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HD DUPSYSTEM shall be PERABLE and appropriate perions of these systems shall be
fi 31 dayseasesofradioactivitywhentheprojecteddoses)6eyondtheused to reduce ruent releases, from each unit, to areas at an@due to gaseous ef
SITE BOUNDARY (see gure 5.1-3) would exceed: -
'
a. 0.2 mrad to ir from gamn.a radiation, or -
b. 0.4 mrad to air-from beta radiation, or
c. 0.3 mrem to any or n of a MEMSER OF THE P98LIC.
APPLICABILITY: At all times. ( --
ACTION:i
*
a. With radioactive gaseous wa te b,rg discharged without treatment 'and in excess of the above 1 i s, prepare and submit to theCommission within 30 days, pu ant to Specification 6.9.2, a5pecial Report that include . the following information: ,5 i
-
~
L','
,
'*1. Identification of inoperab equipment or' subsystems, and |
the reason for th noperabilit ;I
'r 2. Action (s) take o restore the inop able equipment to OPERABLE
status, and*
3. Summary des iption of action (s) taken t prevent a recurrence.
b. The provisions of ' Specifications 3.0.3 gnd 3.0.4 re not applicable./
SURVEILLANCE REOUIRE'MENTSs
4.11.2.4.1 oses due to gaseous releases from each unit to areas a nd
beyond th ITE BOUNDARY shall be projected at least once per 31 days 'naccnrdan with the methodology and parameters in the ODCM when Gaseous adwasteTrea t.m t systems are not being fully utilized.
4.1 .7.4.7 The installed VENTILATION EXHAUST TREATMENT SYSTEM and the VASTG .Il0lDtiP %YSTEMS shall be considered OPERABEE by meeting Specifications 3.1 .1nil 3.11.?.7 or 3.11.2.3.
h h.m.CAIIAWAY - UNIT 1 3/4 11-14
#w h* .wp#/9
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.; ;;' *' *.
Y SiON I -
DI0 ACTIVE EFFLUENTS;.
^ 3/ 1.3 SOLID RADIOACTIVE WASTES~
LIMIThGCONDITIONFOROPERATION.
-3.11.3 R ioactive wastes shall be solidified or dewatered in accordance th
the PROCESS ONTROL PROGRAM to meet shipping and transportation requirementsduring transi- and disposal site requirements when received at the disposal
[,/site.APPLICABILITY: A .all times.ACTION: [
With SOLIDI ICATION or dewatering not meeting dispos,a1 site and ,a.shipping an transportation requirements, suspend shipment of theinadequately rocessed wastes and correct the PROCESS CONTROL PROGRAM,the procedure and/or the Solid Waste System asphecessary to prevent
,/ frecurrence.
b. With SOLIDIFIC ION or dewatering not performid in accordance withthePROCESSCON(0LPROGRAM,testtheimpyoperlyprocessedwasteineach container togensure that it meets bprial ground and shippingrequirements and ke appropriate administrative action to prevent .
frecurrence.The provisions of Spe ifications 3.'0.3 and 3.0.4 are not applicable.c.
'
SURVEILLANCE REQUIREMENTS .
.' 4.11.3 501 EDIFICATION of at least o representative test specimen from at(..f least every tenth batch of each type'o wet radioactive wastes (e.g., filter
sludges, spent resins, evaporator pettom boric acid solutions and sodiumsulfatesalutions)shallbeverifjedina ordance with the PROCESS CONTROLPROGRAM: /
ofthebatchunderte/ailstoveri(SOLIDIFICATION,theSOLIDIFICATIONIf any test specimena.st shall be susp ded until such time as additional
test specimens canjbe obtained, altern ve SOLIDIFICATION parameterscan be determined /in accordance with th ROCESS CONTROL PROGRAM,
and a subsequent test verifies SOLIDIFIC |0N. SOLIDIFICATION of#
the batch may ,then be resumed using the al{ rnative SOLIDIFICATIONparameters dytermined by the PROCESS CONTROL PROGRAM; J
b. If the initial test specimen from a batch of w te fails to verify fISOLIDIFICATION, the PROCESS CONTROL PROGRAM sha provide for the
collecticIn and testing of representative test spe imens from eachconsecutive batch of the same type of wet waste u il at least threeconsep6tive initial test specimens demonstrate 50L IFICATION. ThePROCTSS CONTROL PROGRAM shall be modified as require', as providedin specification 6.13, to assure SOLIDIFICATION of su sequent batcheso/ waste;and
c. ' ith the installed equipment incapable of meeting Speci ' cation3.11.3 or declared out-of-service, restore the equipment o operablestatus or provide for contract capability to process waste as
Inecessary to satisfy all applicable transportation and disp alf
requirements.
'
jfCALLAWAY - UNIT 1 3/4 11-17
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-
[ ._ a.e.w;5eMPp.{ 7.y ^.'q.5 ;a;.az.cc.m .7 3. y; .$ , p::.,:=x.p"m m,.3.
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I.
REVISION 1.
j. . o . ., ..
010 ACTIVE' EFFLUENTS'
-
'3 .4 TOTAL DOSE .M~
;
. h '|'*
| [ LIMITING CONDITION FOR OPERATION
/x.,; ,
..; C 3.11.4. The annu (. calendar year) dose or dose commitment to any MEMBER OF3E THE.PUBLIC due to Nieases of radioactivity and to radiation from urphium fuel I qT " cycle sources shall h limited to less than or equal to 25 mrsans to/the whole Jl
~ m body or any organ, exhept the thyroid, which shall be limited to ss than or| . equal to 75 mrems.
APPLI(' ABILITY: At all imes. M M' ACTION: Cj
k'
a. With the calcul ted doses from the release of dioactive materials gh ,1in liquid.or gas ous effluents exceeding twi the limits ofSpecification 3.1 . 1.2a., 3.11.1.2b., 3.11, 2a., 3.11.2.2b., W,
3.11.2.3a., or 3. 2.3b., calculations sh Id be made including h.
- direct radiation co ributions from the .its and from outside storage_
,
tanks to determine wrie her the above 1 ts of Specification 3.11.4have been exceeded. I such is the c ', prepare and submit to the
~ Commission within 30 da s, pursuant Specification 6.9.2, a SpecialReport that defines the correctiv adtion to be taken to reduce sub-sequent releases to pre nt recu /nce of exceeding the above limitsand includes the schedule - r leving conformance with the above' D[jlimits. This Special Report s defined in 10 CFR 20.405c, shallinclude an analysis that es sa'
anium.. the radiation exposure (dose) to a TMEMBER OF THE PUBLIC from el cycle sources, including alleffluent pathways and di et radiati for the calendar year thatincludes the release (s covered by thi report. It shall also-
describe levels of ra at. ion and concent 'tions of radioactivematerial involved, a the cause of the e sure levels or concentra-j
tions. If the esti ted dose (s) exceeds th gabove limits, and if therelease condition sulting in violation of 4B CFR Part 190 has notalready been corr ted, the Special Report shah include a requestfor a variance accordance with the provisions' f 40 CFR Part 190. *
Submittal of t report is considered a timely rei$ west, and a varianceis granted u. il staff action on the request is co lete.
b. The provi ons of Specifications 3.0.3 and 3.0.4 are t applicable.
,$_U_RVEILLANCE REO EMENTS,
4.11.4.1 C ulative dose contributions from liquid and gaseous eff1 ts5. hall be d. ermined in accordance with Specifications 4.11.1.2, 4.11.2.2 and4.ll.2.3 and in accurdance with the methodology and parameters in the O M.
4.11.4 Cumulative dose contributions from direct radiation from the units .
.ind om radwaste storage tanks shall be determined in accordance with theIme .odology and parameters in the ODCM. This requirement is applicable only
ur er conditions set forth in ACTION a. of Specification 3.11.4_ . , , .
.
# 'CALLAWAY - UNIT 1 3/4 11-18
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,
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.
.
.
3 REVISIONy ,,,
N' f/--12 RAll!010GICAL I. ENVIRONMENTAL MONIl0 RING*Mc N.
3/4.12.1 MONITORING PROGRAM'
r )LIMITING CONDITION FOR OPERATION
k 4
3.12.1 The Radiological Environmental Monitoring Program shall be conduc. d [as specified in\ able 3.12-1. . (/*
APPLICABILITY: At' ell times.'\
\~
JACTION:With the Rad q,Jogical Environmental Monitoring Program t being ogo Oa.conducted as specified in Table 3.12-1, prepare and supmit to the NCommission, in tie Annual Radiological Environmental perating Reportt
[required by Specification 6.9.1.6, a description of he reasons fornot conducting the p{Aogram as required and the plap for preventing ha recurrence.
b. h th the level of rad oactivity as the result o plant effluents in -
*
an environmental sampling medium at a specifit location exceedingthe reporting levels of Tab,le 3.12-2 when avpr; aged over any calendarquarter, prepare and submit \to the Commissiin within 30 days,pursuant to Specification 6.9g2, a Specia)/ eport that identifiesR
the cause(s) for exceeding theglimit(s) gnd defines the correctiveactions to be taken to reduce r&dioact'4e effluents so that thei,, .
yj, . potential annual dose * to a MEMB&R OF .HE PUBLIC is less than the..
Q9 calendar year limits of Specificat s 3.11.1.2, 3.11.2.2, or
3.11.2.3. When more than one of e radionuclides in Table 3.12-2are detected in the sampling med m,%dhis report shall be submitted if:
concentration (1) conce ration (2). + * * * > 1. 0reporting level (1) reporting level (2) -
When radionuclides other an those in Table 3.12-2 are detected andare the result of plant (fluents, this repo,r$ shall be submitted ifthe potential annual d ~e* to A MEMBER OF THE KJBLIC from all radio-nuclides is equal to r greater than the calendag year limits of Speci-fications 3.11.1.2 .11.2.2 or 3.11.2.3. This rbport is not requiredif the measured i 1 of radioactivity was not the*tesult of plant
Ipallbereportedand described jf,ge, in such an event, the conditioneffluents: howev
t the Annual Radiological Environmental perating Report, i
required by Specification 6.9.1.6.c. With milk of fresh leafy vegetable samples unavailable fr one or
more of , e sample locations required by Table 3.12-1, iden fy#
specift locations for obtaining replacement samples and add hemwithip 30 days to the Radiological Environmental MonitoringProyramgivenintheODCM.** The specific locations from which amples
*The met 'dology and parameters used to estimate the potential annual dosea MEM OF THE PUBLIC shall be indicated in this report.
'
**Ex .uding short term or temporary unavailability.1
'
.;
ALLAWAY - UNIT 1 3/4 12-1
)i
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~ 7'i~..: f t:y w:: . - ,i,; ~ _ I,f f.]I - T~D:;^, .f:7:t. .Ltbi" KG.; g(;[L;? * '*w ' ~ ~' '% ;Y" : ...
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-
,
REVISjog "t
} _ OGICAL.4NVIRONMENTALMONiiORING'
RAD
'1tikli! NDITION FOR OPERATION. 3..;, ; .. x
ACTION (Contin ),
were unavai le may then be deleted from onitoring program.fication 6.14, submit i e next Semiannual Radio- .
Pursuant to Spec {H ase Report docum ion for a change in theactive Effluent Rd table for the 00CM reflectingODCM, including a r
d figure (s) information identifying thethe new location (s) wi upportingcause of the unavailabili of'' samples and justifying the selectionof new location (s) for obtai g samples.
_
d. The provisions of Specifications . 3 and 3.0.4 are not applicable...
.
SURVEILLANCE REQUIREMEN
/ <
4.12.1 Thefditiological environmental monitoring samples sha e collected ~-
pursuant to Table 3.12-1 from the specific locations given in th ble and --
figure ( *in the ODCM, and shall be analyzed pursuant to the requir ts of
Tabl .12-1 and the detection capabilities required by Table 4.12-1.
.
,
1
uQ chSv
t
~
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I REVI8/ONTABLE 3.12-1 (Continued)I '
2ni .Y TABLE NOTATIONS
..
(1) ecific parameters of distar.:e and direction sector from the centep ineoneunit,andadditionaldescriptionwherepertinent,shallbefrovidedo
for achandeverysamplelocationinTable3.12-1inatableanpfigure(s)in tha ODCM. Deviations are permitted from the required sampli,ng scheduleifspehmensareunobtainableduetohazardousconditions, seasonalunavailab(lity,malfunctionofautomaticsamplingaquipment,/andother ;
legitimate" easons. If specimens are unobtainable due to r,dmpling equip-ment malfun on, every effort shall be made to complete p'orrective actionprior to the ad of the next sampling period. All deviations from thesampling scheduh shall be documented in the Annual Ra#iological Environ-mental Operating teport pursuant to Specification 6.9/1.6. It is recog- - pnized that, at tim'ef, it may not be possible or pra ficable to continue toobtain samples of the media of choice at the most esired location ory
time. In these instahces suitable specific alter ative media and loca-tionsmaybechosenfohtheparticularpathwayj question and approprit.tesubstitutions made withi'n 30 days in the Radiologien1 Environmental \0MonitoringProgramgivenktheODCM. Pursupnt to Specification 6.14, Wsubmit in the next Semiannua) Radioactive fluent Release Report documen-tation for a change in the 00CM including revised figure (s) and tablefor the ODCM reflecting the ne'w locationf ) with supporting informationidentifying the cause of the unAyailabjiity of samples for that pathwayand justifying the selection of the pew location (s) for obtaining samples.
5, (2) One or more instruments, such as pressurized ion chamber, for measurings
(D..Oand recording dose rate continuously may be used in place of, or inaddition to, integrating dosimet'ers. Fqr the purposes of this table, athermoluminescent dosimeter (Jf.D) is considered to be one phosphor; twos
or more phosphors in a packet are considefed as two or more dosimeters.Film badges shall not be ysbd as dosimeters \for measuring direct radia-tion. The 40 stations 1 The number of directradiationmonitoringsa/notanabsolutenumber.tions may be reduced a'ccording to geographicallimitations; e.g. , a n ocean site, some sectohg will be over water sothat the number of imeters may be reduced accordingly. The frequencyof analysis or read 6,ut for TLD systems will depend \upon the characteristicsof the specific f stem used and should be selected to obtain optimum dosefinformation with minimal fading. \
(3)ThepurpuseAfthissampleistoobtainbackgroundinfo\/ rmation. If it is
not pract'ial to establish control locations in accordanceswith thedistanc and wind direction criteria, other sites that prov3de validbackg 'and data may be substituted.
(4) Ai orne particulate sample filters shall be analyzed for gross betainactivity 24 hours or more after sampling to allow for radon Agdr
hurun dauqhter decay. If gross beta activity in air particulate SRmplesis greater than 10 times the yearly mean of control samples, gammaisotopic analysis, shall be performed on the individual samples,
t
\Ns
CALLAWAY - UNIT 1 3/4 12-7
r~_._ - - _ _ - >~
' ....'s 4 .s:t:p k h ,.i r 7 7 -.--, j , . .! - *".r-~'
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REVIS)[y' gTABLE 3.12-1 (Continued)
*s
TABLE NOTATIONS (Continued) A: 'b:),
w/(5) Gamma isotopic analysis means the identification an. uantification of
gamma'h mitting radionuclides that may be attribut e to the effluentsfrom th N acility.
Nam stance beyond significantinfluence of the'ple" shall be taken at a(6) The."upstr
dQcharge. The " downs eam" sample shall-be taken in anarea beyond but nearNthe mixing zone.
(7) In this program composite plej liquots shall be collected at timeintervals that are very shorMe.g. , hourly) relative to the compositingperiod (e.g. , monthly) in o . der'to assure obtaining a representative-
sample.
(8) Groundwater samples y all be taken when ttis source is tapped for drinkingor irrigation purp tes in areas where the hydraulic gradient or rechargeproperties are 1 table for contamination.
(9) The dose sh 11 be calculated for the maximum organ a age group, using --
''
the metho logy and parameters in the ODCli. .
(10) If.h vest occurs more than once a year, sampling shall be per, formeddu ng each discrete harvest. If harvest occurs continuously,'sempling
all be monthly. Attention shall be paid to including samples o uberousand root food products. .
$y.,h.. ;..
.
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*J ' CALLAWAY - UNIT 1 3/4 12-9
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lABLE 4.12-1 (Continued)! . .
TABLE NOTATIONS.
. list does not mean that only these nuclides are to be considerep.(1)iTh4 peaks that are identifiable, together with those of the abovp/ogicalOthnucli . s, shall also be analyzed and reported in the Annual RadiEnvironmental Operating Report pursuant to Specification 6.9.1.
(2). Required detection capabilities for thermoluminescent dosime ers usedhe recommenda-for environmental measurements shall be in accordance with'
tions of RegdTatory Guide 4.13, Revision 1, July 1977.. " .'
, 'for purposes of these specificatiphs, as the smallest(3) The LLD is' deficoncentration of r'adioactive material in a sample t%t will yield a net' count, above system' background, that will be deteeped with 95% probabilityt a blank observationwith only 5% probability of falsely concluding trepresents a "real" sig~nal.
\ include radiochemicalFor a particular measurement system, which m -
-
separation: <
%4.66 s
LLD = IA$t)s
E * V - 2.22 Y - exp
:\ |hWhere:
Yb@M imit ofydetection (picoCuries per unit..
\'
LLD = the "a priori'" lowermass or volume),
b = the standard devi tion of the background counting rate or ofs ga blank sample as appropriate (counts pert.he- counting rate o
' minute),
E = the countin efficiency (counts per disintegration),N
size (units of mass or volume),V = the samp
number of disintegrations per minuto pergpicoCurie,2.22 = th \fractional radiochemical yield, when applicable,Y=t s
A - the radioactive decay constant for the particular radionuclides\8 ), and
\
at = the elapsed time between se.mple. collection, or end of thesample collection period, and time of counting (s).
Typical values of E, v. Y, and at should be used in the calculation.s
,
u 3/4 12-11CALLAWAY - UNIT 1-
,
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o/'"TABLE NOTATIONS (Continued)
It should be reco. Qed that the LLD is ined as an a_ priori (beforethe fact) limit reprebt ty of a measurement system ar.dnot as an a posterior'i'pting the cap [atd{n ter the t) limit for a particular measurement.Analyses shall be performe(5Qnch a manner that the stated LLDs will beachieved under' routine condi s. Occasionally background fluctuations,
#
unavoidable small sample zes,'theq resence of interfering nuclides, orother uncontrollable - cumstances'may render these LLDs unachievable.In such cases, the ntributing factors qh,all be identified and describedin the Annual R ological Environmental Op'e. ating Report pursuant to
~ Specification .9.1.6.\
(4) LLD for inking water samples. For surface water sampi.gs, the LLD ofgamma sotopic. analysis may be used. N ,%
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) . 4A010LOGICAt ENVIRONMENTAL MONITORING
s 3 12.2 LAND USE CENSUS qI
\vLIMITING CONDITION FOR OPERATION ]
f\ 13.12.2 A Land Use Census shall be' conducted and shall identify withi. a
. distance of 8 (5 miles) the location in each of the 16 meteorologicalsectors of.the arest milk animal, the nearest residence and the , nearestgarden * of greater than 50 m (500 ftz) producing broad leaf vegetation.2
)APPLICABILITY: At a 1 times.
,
IACTION:'
With a Land Use Census identifying a location (s) that yields a - ,v
a. t
calculated dose %r dose commitment greater than the values currentlybeingcalculated% specification 4.11.2.3,/dentifythenewloca- ;
tion (s) in the nex Semiannual Radioactive / Effluent Release Report, me (4'
Tpursuant to Specifi tion 6.9.1.7. /b. With a Land Use Census identifying a 1ptation(s) that yields a * dg
calculated dose or dose commitment (yia the same exposure pathway) p20% greater than at a lo tion frog'which samples are currently-
e with/ specification 3.12.1, add the newSbeing obtained in accordalocation (s) within 30 days o the Radiological Environmental Moni- wtoring Program given in the DCM. The sampling location (s), excludingthe control station location, aving the. lowest calculated dose or
. ..._ dose. commitment (s),.via the/sa exposure pathway, may be deletedfrom this' monitoring program af r-October 31 of the year in which.?|%
' ~ ' ' ~
y this Land Use Census was/conducte . Pursuant to Specification 6.14,submit in the next Semjiinnual Radi etive Effluent Release Reportdocumentation for a change in the O M including a revised figure (s)-and table (s) for the'0DCM reflecting he new location (s) with infor-mation supporting t'he change in sampli locations.jThe provisions pf Specifications 3.0.3 a 3.0.4 are not applicable.c.
SURVEILLANCE REQUIREMENT
4.12.2 The Land Census shall be conducted during th growing seasonat least once pe 2monthsusingthatinformationthatw{1providethebestresults, such a by a door-to-door survey, aerial survey, o . by consultinglocal agriculture authorities. The results of the Land Use nsus shall be
' included in 3 e Annual Radiological Environmental Operating R ort pursuant to6Specific 4n 6.9.1.6.
*Broa/ leaf vegetation sampling of at least three different kinds of vegetationmay/ e performed at the SITE BOUNDARY in each of two different direc ion sectorsbw'th the highest predicted D/Qs in lieu of the garden census. Specif sationsor broad leaf vegetation sampling in Table 3.12-1, Part 4.c. shall be Ypliowed,
including analysis of control samples.
.
9
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. 3/4. INTERLABORATORY COMPARISON PROGRAM' #
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LIMITING CONDIT _FOR OPERATION
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3.12.3 Analyses shall b ef erials supplied as partofanInterlaboratoryComparbormedonradioactivemoo Program that has b approved by theCommission.
APPLICABILITY: At all times.*
ACTION:.
. .
a. With analyses not being pe ormed as r'tquired above, report thecorrective actions taken o prevent a reh grence to the Commissionin the Annual Radiolog al Environmental Oper ting Report pursuantto Specification 6.9 .6.
~
b. The provisions Specifications 3.0.3 and 3.0.4 a' not applicable. ..
SURVEILLANCE RE IREMENTS' '
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4.12.3 he Interlaboratory Comparison Program shall be described in the ODCH.A su ary of the results obtained as part of the above required Interlaboratoryto arison Program shall be included in the Annual Radiological Environmental
erating Report pursuant to Specification 6.9.1.6.
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3/4.3.3.8 LOOSE-PART DETECTION SYSTEM-
The OPERABILITY of the loose-part detection instrumentation ensures' thatsufficient capability is available *w detect loose metallic. parts in-the.Reactor Coolant System and avoid or mitigate damage to Reactor Coolant System -components. -The allowable out-of-service times.and Surveillance Requirements
4 ^ ' ' are' consistent with the recommendations of Regulatory Guide-1.133, " Loose-PartDetection Program for.the Primary System of Light-Water-Cooled Reactors,"May 1981.
.
~3/4.m M OACTIVE'LIOUID EFFLUENT MONITORING INSTRUMENTATION
The radioact e nt instrumentation ovided to monitor .
1 and control; as' applicable, t fr 1ve materials'in. liquid'
effluents during actual or potential'- iquid effluents. The -Alarm / Trip Setpoints for these . uments shall-be 1tglated and adjustedin accordance with the m + o ogy and parameters in the D %. + ensure that
.
the alarm / trip wil ur prior to exceeding the limits of 10 CFR + 20.The OPERABILT* nd use of this instrumentation is consistent with therequir , s of General Design Criteria 60, 63, and 64 of Appendix A to |
rd Part 50. ;
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- CALLAWAY - UNIT 1 B 3/4 3-5 Amendment No. 30
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__ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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REVISION 2 '
. INSTRUMENTATION . ' ,;t
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4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATlDN
The ra tive gaseous effluent instrumentation vided to monitorand control, as a able, the releases of radio 4;ti e materials in gaseous Oeffluents during actua tential releases ef' gaseous effluents. The Alarm / bTrip Setpoints for these instr s sha e calculated and adjusted inaccordance with the methodology and eters in the ODCM to ensure that thealarm / trip will occur prior to eding t mits.of 10 CFR Part 20. Thisinstrumentation also includ rovisions for moni ng (and controlling) theconcentrations of poten31e y explosive gas mixtures WASTE GAS HOLDUPSYSTEM. The OPERAB LITY and use of this instrumentation is istent withthe . requirements General Design Criteria 60, 63, and 64 of App A to
10 CFR Part The sensitivity of any noble gas activity monitor use show.
complian with the gaseous effluent release, requirements of Specifica- Ition . 1.2.2 shall be such that concentrations as low as 1 x 10 S pCi/cc are F
"(m surable.
*
3/4.3.4 1URBINE OVERSPEED PROTECTION.
This specification is provided to ensure that the turbine overspeedprotection instrumentation and the turbine speed control valves are OPERABLEand will protect the turbine from excessive overspeed. Although the orientationof the turbine is such that the number of potentially damaging missiles which )-
I' could impact and damage safety-related components, equipment, or structures is*/|minimal, protection from excessive turbine overspeed is required.
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Sl0N J3/4.11 RADIOACTIVE EFFLUENTS
,HBASES
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h4.11.1-LIQUIDEFFLUENTS
3/4 .1.1 CONCENTRATION
Th specification is provided to ensure that the concentration ofradioacti materials released in liquid waste effluents to UNRESTRICTED AREASwill be les ' than the concentration levels specified in 10 CFR Part 2 ,' Appen-dix B, Table .I, Column 2. This limitation provides additional ass ance thatthe' levels of dioactive materials in bodies of water in UNRESTRIf ED AREAS
| will result in posures within: . (1) the Section II. A design objectives of Ap' pen--dix I, 10 CFR Par 50,' to a MEMBER OF THE PUBLIC, and (2) the eits of 10 CFRPart 20.IO6(e) to e population. The concentration limit fo dissolved or,
. entrained noble gas is based upon the assumption'that Xe-13 is the control-
ling radioisotope an its MPC in air (submersion) was convpfted to an equivalent- concentration in water sing the' methods described in In ernational Commission'. on Radiological Protecti (ICRP) Publication 2.
,
The required detection capabilities for radioac. ve materials in liquidwaste samples are tabulated termsofthelower}/mitsofdetection(LLDs).
E Detailed discussion of the LL and other detectiph limits can be found in! HASL Procedures Manual, HASL-30 (revised annual)y), Currie, L. A. . . " Limits .
for Qualitative Detection.and Qua titative Detptmination - Application toRadiochemistry," Anal. Chem. 40, 5 -93 (1968), and Hartwell, J. K. , " Detection-
I Limits for Radicanalytical Counting chni "s," Atlantic-Richfield HanfordCompany Report ARH-SA-215 (June 1975).
'3/4.11.1.2 DOSE '
This specification is provided o imple ent the requirements ofSections II.A, III.A and IV.A of pendix I, Q CFR Part 50. The LimitingCondition for Operation implemen theguidessagforthinSectionII.AofAppendix I. The ACTION statem .ts provide the required operating flexibilityand at the same time implemen the guides set forth in Section IV.A of Appen--dix ! to assure that the re ases of radioactive mat rial in liquid effluentsto UNRESTRICTED AREAS will e kept "as low as is reas ably achievable." Also,for f resh water sites wi drinking water supplies that an be potentiallyaf fected by plant operpt) ions, there is reasonable assuranthat the operation
of,the facility will ot result in radionuclides concentrat ns in the finisheddrinking water that re in excess of the requirements of 40 'R Part 141. Thedose calculation . thodology and parameters in the ODCM implem t the require-
ments in Sectio [ dix I be shown by calculational procedures based oh models and111.A of Appendix I which specify that cenform qce with the
guides of Appe,pdata, such ft the actual exposure of a MEMBER OF THE PUBLIC throu 5 appropri-ate pathwa is unlikely to be substantially underestimated. The eq tionsspecifiep in the ODCM for calculating the doses due to the actual rele e ratesof ra active materials in liquid effluents are consistent with the me odologyprov' d in Regulatory Guide 1.109, " Calculation of Annual Doses to Man f m
Ro ne Releases of Reactor Effluents for the Purpose of Evaluating Complia e
- CALLAWAY - UNIT 1 B 3/4 11-1
REVISlay 3 ._
. RADIOACTIVE EFFLUENTS-
{ . . - _ . - - . . . . . . . . . . . . . . . . - - - - . . . - . . . . . - ...._/ 7Bases
- _ . . . _ -
. . - . . . . ,
,,SE (Continued)
with FR Part 50, Appendix I," Revision 1, October ' and RegulatoryGui'de 1. 13,, " Estimating Aquatic Dispersion of Eff nts from Accidental and
. ,
Routine Reactor Releases for the Purpose of Im nenting Appendix I,"
April 1977. N ~7 $,3/4.11.1.3 LIOUID RADWASTE TREATMENT,8 STEM @.
The OPERABILITY of tv Radwaste Treatment System ensures that thissystem will be available f % benever liquid effluents require treatment
prior to release to the ironment.NQg requirement that the appropriateportions of this syste e used when specif4ef provides assurance that thereleases of radioac ' e materials in liquid efflugnts will be kept "as low asis reasonably ac vable". This specification impIhmegs the requirements of10 CFR Part 50 6a, General Design Criterion 60 of Appendix to 10 CFR Part 50and the de n objective given in Section II.D of Appendix I CFR Part 50.The spe ied limits go wning the use of appropriate portions of 4 uidRadw e Treatment System were specified as a suitable fraction of the Id gn objectives set forth in Section II.A of Appendix I, 10 CFR.Part 50,
m ' i g,;iM <1 nontey
3/4.11.1.4 LIOUID HOLDUP TANKS"
The tanks listed in this specification include all those outdoor radwaste,
tanks that are not surrounded by liners, dikes, or walls capable of holdingthe tank contents and that do not have tank overflows and surrounding areadrains connected to the Liquid Radwaste Treatment System.
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REVISlay yRADIOACTIVE EFFLUENTS
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[.c,, BASES*
LIQUID HOLDUP TANKS (Continued)
Restricting the quantity of radioactive material contained in the specifiedtanks provides assurance that in the event of an uncontrolled release of the
' tanks' contents, the resulting concentrations would be less than t.he limits of10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable watersupply and the nearest surface water supply in an UNRESTRICTED AREA.
& 4.11.2 GASEOUS EFFLUENT 5~
',3/ .1 DOSE RATE
I Thi b cification is provided to ensure that the dose at any time at d
aeyond the BOUNDARY from gaseous effluents from all units on the sit will>e within the anqual dose limits of 10 CFR Part 20 to UNRESTRICTED AREA The<innual dose limitt te the doses associated with the concentrations o 10 CFRPart 20,' Appendix B, able II, Column 1. These limits provide reas ableissurance that radioac ive material discharged in gaseous effluen+ will not'esult in the exposure o a MEMBER OF THE PUBLIC in an UNRESTRI .ED AREA,either within or outside e SITE BOUNDARY, to annual average concentrations
i exceedingthelimitsspecifydinAppendixB.TableIIof1 CFR Part 20' :10 CFR 20.106(b)). For MEMB 5 0F THE PUBLIC who may at imes be within
the SITE BOUNDARY, the occupan of that MEMBER OF THE JBLIC will usually be
' ~sufficiently low to compensate f any increase in th atmospheric diffusionfactor above that for the SITE B0 ARY. Examples calculations for suchMEMBERS OF THE PUBLIC, with the app priate occup cy factors, shall be givenin the ODCM. The specified release r ?e limits estrict, at all times , thecorresponding gamma and beta dose rates bove ackground to a MEMBER OF THEPUBLIC at or beyond the SITE BOUNDARY to es than or equal to 500 mrems/ yearto the whole body or to less than or equal o 3000 mrems/ year to the skin.These release rate limits also restrict t 11 times, the corresponding
thyroid dose rate above background to child ia the inhalation pathway to
less than or equal to 1500 mrems/ye
The required detection cap ilities for radio tive materials in gaseouswaste samples are tabulated i terms of the lower li *ts of detection (LLDs).Detailed discussion of the D, and other detection li ts can be found in HASLProcedures Manual, HASL-32 (revised annually), Currie, A., " Limits for |
Qualitative Detecti E y d Quantitative' Determination - Ap ication to Radio- !
.
chemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. . " Detection f
| Limits for Radioapalytical Counting Techniques," Atlantic Ric.#ield HanfordJ Company Report FtH-SA-215 (June 1975). ;
3/4.11.2.2 E - NOBLE GASES11
is specification is provided to implement the requirements of j'
se ions II.B Ill.A and IV.A of Appendix 1. 10 CFR Part 50. The Limitin- I
_
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} . .. sSASES
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D NOBLE GASES (Continued) |* Conditio for Operation implements the guides set forth in Section II.B of
Appendix I. The ACTION statements provide the required operating flexib' ityand at the sa time implement the guides set forth in Section IV.A of ppendix Ito assure'that releases of radioactive material in gaseous efflu ts toUNRESTRICTED AREA ill be kept "as low as .is reasonably achievabl . ' The Sur-veillance Requirement implement the requirements in Section III of Appendix Ithat conformance with t guides of Appendix I be shown by cal ational proce- idures based on models and ta such that the actual exposure f a MEMBER OF |iTHE PUBLIC through appropria. pathways is unlikely to be bstantially under- 4 i
estimated. The dose calculati methodology and paramet s established in the I|ODCM for calculating the doses d to the actual relea rates of radioactive ! ;
noble gases in gaseous effluents ar consistent with e methodology providedin Regulatory Guide 1.109, "Calculati of Annual ses to Man from. Routine i
Releases of Reactor Effluents for the P ose of valuating Compliance with30 CFR Part 50, Appendix I," Revision 1, tob 1977 and Regulatory Guide 1.111,
C T'' '" Methods for~ Estimating. Atmospheric Transpo and Dispersion of. Gaseous Effluentsin" Routine Releases f rom Light-Water Coole ctors," Revision 1, July.1977. h
The ODCM equations provided for determin' g the ir doses at and beyond theSITE BOUNDARY are based upon the histo cal avera atmospheric conditions.
3/4.11.2.3 DOSE - 10 DINE-131 AND 3, TRITIUM, AND 10 ACTIVE MATERIAL INPARTICULATE FORM
)- .g
This specification is p vided to implement the requi ments of . .)Sections II.C, III.A and I .A-of Appendix I, 10'CFR Part 50. The LimitingConditions for Operation re the guides set forth in Section .C of Appendix 1.The ACTION statements ovide the required operating flexibilit and at thesame time implement e guides set forth in Section IV.A of Appe ix I to assurethat the releases radioactive materials in gaseous effluents to UNRESTRICTEDAREAS will be ke "as low as is reasonably achievable." The ODCM c culationalmethods specif' d in the Surveillance Requirements implement the requi mentsin Section J .A of Appendix I that conformance with the guides of Appe ix Ibe shown b calculational procedures based on models and data, such that
,
actual e osure of a MEMBER OF THE PUBLIC through appropriate pathways isunlike tn be substantially underestimated. The ODCM calculational method- )niog and parameters for calculating the doses due to the actual release rates J
.
of e subject materials are consistent with the methodology provided in Regula-y Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of
eactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50,
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.
O. BAS, ,
DOSE - 1 i-131 AND 133, TRITIUM, AND RADIOACTIVE MATERIAL INPARTICULATE %RM (Continued)
Appendix I," Rev on 1, October 1977 and Regulatory Guide .111. " Methods'forEstimating Atmosphe c Transport'and Dispersion of Gaseou Effluents in RoutineReleases from Light-W r-Cooled Reactors," Revision 1, uly 1977. These equa-tions also provide for. ermining the cetual d.oses b ed upon the historicalaverage-atmospheric condit s. The release rate s cifications for Iodine-131and 133, tritium, and radionu ides'in particulat form with half-lives greater.than 8 days are dependent upon e existing rad nuclide pathways to man, inthe areas at and beyond the SITE NDARY. T pathways that were examined inthe development of these calculation were: (1) individual, inhalation ofairborne radionuclides, (2) deposition radionuclides onto green leafy vege-tation with subsequent consumption by , (3) deposition onto grassy areaswhere milk animals and meat producin nima g graze with consumption of the milk'and. meat'by' man,.and (4) deposition n the gr' d with subsequent exposure of man.~ '
'
3/4.11.2.4 GASEOUS RADWASTE TR TMENT SYSTEM
The OPERABILITY of theat the systems will be availa{he ' VENTILATION EXHAUST,ASTE GAS HOLDUP SYSTEM and%
TREATMENT SYSTEM ensures b for use whenevergaseous effluents requi treatment prior to release to the nvironment. The,
i requirement that the propriate portions of these systems be sed, when| specified, provides essonable assurance that the releases of r ioactive
materials in gase s effluents will be kept "as low as is reasona y achievable"..
( -This specificat' n implements the requirements.of 10.CFR Part 50.3 GeneralDesign Criter n 60 of Appendix A to 10 CFR Part 50, and the design ectivesgiven in Se ion 11.0 of Appendix I to 10 CFR Part 50. The.specified - mits
,
governing e use of appropriate portions of the systems were specified asuitabl fraction of the dose design objectives set forth in Sections II.B dII.C o Appendix I, 10 CFR Part 50, for gaseous effluents.
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-_ _ _ - _ - _ _ _ . - _ _ _ _ - - _ - _ _ _ _ _ _ - _ _ - _ - _ __
- _ _ - _ _ - - - _ - _ - _ _
.
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RADI0 ACTIVE EFFLUENTS ,,
~BASES .h
-.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE
This specification is provided to ensure that the concentration ofpotentially explosive gas mixtures contained in the waste gas holdup system ismaintained below the flammability limits. of hydrogen and oxygen. Automaticcontrol features are included in the system to prevent the hydrogen and oxygenconcentrations from reaching these flammability limits. These automatic controlfeatures include isolation of the source of hydrogen and/or oxygen. Maintainingthe concentration of hydrogen and oxygen below their flammability limits pro-vides assurance that the releases of radioactive materials will be controlledin conformance with the requirements of General Design Criterion 60 ofAppendix A to 10 CFR Part 50.
3/4.31.2.6 GAS STORAGE TANKS
The tanks included in this specification are those tanks for whichthe quantity of radioactivity contained is not limited directly or indirectly
.by another Technical Specification. Restricting the quantity of radioactivitycontained in each gas storage tank provides assurance that in the event of anunco 7 trolled release of the tank's contents, the resulting whole body exposureto a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will rot exceed 0.5 rem.
*
This is consistent with Standard Review Plan 11.3, Branch Technical PositionETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak orFailure," in NUREG-0800, July 1981.
) # W 1.3 SOLID RADIDAL61Vt WA5T25 .
_
] . . ., 'This specificatica implements the requirements of 10 a and.
General Design Criterion 7tbofdppendix A to 1 ER-P 50. The process-
parameters included in establishing"the ff.00E ONTROL PROGRAM may include,
but are not limited to, waste,typeliiste bas uid/ SOLIDIFICATION agent /
catalyst ratios, was,teAMo'ntent, waste principal nstituents, and'
mixing andjurirrg'fimes.
RGLO CRTED~
To @
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. .
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.RA010 ACTIVE EFFLUENTS ?-
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NBASESi
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'
3/ .4' TOTAL DOSE
RTh specification is provided to meet the dose limitations of 40 ThePart 190 t t have been incorporated into 10 CFR Part 20 by 46 FR 18 .
specification equires the preparation and submittal of a Special port
whenever the ca ulated doses due to releases of radioactivity d the radia-tion from uranium el cycle sources exceed 25 mrems to the le body or any
organ, except the th id, which shall be limited to less an or equal to
75.mrems. For sites co aining up to four reactors, it highly unlikely thatthe resultant dose to a M ER OF THE PUBLIC will ex d the dose limits of40 CFR Part 190 if the indiv al reactors remain hin twice the dose design
' objectives of Appendix I, and iT irect radiatio doses from the reactor units.and from outside storage tanks are pt small The Special Report will describea course of action that should result ' th imitation of the annual dose toa MEMBER OF THE PUBLIC to witnin the 40
. Part 190 limits. For the purposesof.the Special Report, it may be assum t the dose commitment to the MEMBEROF THE PUBLIC from other uranium fu cycle s rces is negligible, with the ,
exception that dose contributions om other nu 3 ar fuel cycle facilities atthe same site or within a radi of 8 km must be c sidered. If the dose to
j any MEMBER OF THE PUBLIC is imated to exceed the uf rerrents of 40 CFRPart 190, the Special Rep with a request for a varia e (provided the-release conditions resu ing in violation of 40 CFR Part . have not already
' been corrected), in ordance with the provisions of 40 CF ' 90.11 and 10 CFR( 20.405c,:is consid ed to be a timely request and fulfills the ecuirements of
40 CFR Part 190 til NRC staff action is completed. The varian only relatesf 40 CFR Part 190, and does not apply in any way to e other
to the limits for dose limitation of 10 CFR Part 20, as addressed in 5' .cifica-requirementions 3. .1.1 and 3.11.2.1. An individual is not considered a MEMBER .THE
PUBLI uring any period in which he/she is engaged in carrying out any o ra-
Lio hat is part of the nuclear fuel cycle.
Ret.oarreosoCYD CY
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j 1 REVISlay yH 3/4.12 , RADIOLOGICAL ENVIRONMENTAL MONITORING
| e .
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.
.12.1 MONITORING PROGRAM
Radiological Environmental Monitoring Program required by thisspecifi tion provides representative measurements of radiation and of dio-
active ma ials in those exposure pathways and for those radionucli s thatlead to the ighest potential radiation exposures of MEMBERS OF T PUBLICresulting fro the station operation. This monitoring program lementsSection IV.B.2 Appendix 1 to 10 CFR Part 50 and thereby s lements theRadiological Eff1 t Monitoring Program by verifying tha e measurableconcentrations of r ioactive materials and levels of rad tion are not higherthan expected on the . is of the ef fluent measuremey'and the modeling ofnthe environmental expos pathways. Guidance for Jnis monitoring program is
* "provided'by the Radiologic ,]' Assessment Branch Tectinical Position on Environ-mental Monitoring, Revision November 1979.Aeinitiallyspecifiedmoni-toring program will be effecti .for at leas the first 3 years of commercialoperation. Following this perio , rogra hanges may be initiated based onoperational yxperience.
The required detection capabi]A ies or environmental sample analyses.
} are tabulated in terms of the low (r limits detection (LLDs). The LLDsrequired by Table 4.12-1 are gaffsidered optim for routine environmentalmeasurementsinindustrial) laboratories. It sho be recognized that the
-( LLD is defined as an a_ priori (before the f act) lim (representing the capa-*
bility of a measuremenysystem and not as an a, posteribej (after the fact)limit for a particul f measurement.
Detailed df cussion of the LLD, and other detection limits, can be foundin HASL Proc Dres Manual, HA5L-300 (revised annually), Currie, L. " Limits.,
'for Quali ive Detection and Quantitative Determination - Applicati to
Radioc istry," Anal. Chem. 40,'586-93 (1968), and Hartwell , J. K. , " ctionLim for Radioanalytical Counting Techniques," Atlantic Richfield Hanfor
pany Report ARH-SA-215 (June 1975).
AsLoaVTED40
@CO
>.
CALLAWAY - UNIT 1 B 3/4 12-1
!
___ _ - - _ _ - _ _ _ - _ _ -
.
R{yggION3/4.12 = RADIOLOGICAL ENVIRONMENTAL MONITORINGz
1,~
1 5 .. . s ;
- 3/4.12.2 AND USE CENSUS -|
This spe itation is provided to ensure that changes in the se of areasat and beyond t SITE BOUNDARY are identified and that modif ions to theRadiological Envir ~ ental Monitoring Program given in th M are made ifrequired by the resu of this census. Information th ill provide the best
'
- results, such as door-t oor survey, aerial survey consulting with local-agricultural authorities, - all be used. This c us satisfies the requirements-of'Section IV.B.3 of Append 1 I to 10 CFR Par Restricting the census to.
gardens of greater than 50 m2p vides ass nee that significant exposure path-ways via leafy vegetables will be ent ed and monitored since a garden ofthis size is the minimum required to- oduce the quantity (26 kg/ year) of leafy
- vegetables assumed in Regulatory de 9 for consumption by a child. Todetermine this minimum garden e' e, the fo ing assumptions were made:(1) 20% of the garden was u for growing bro leaf vegetation (i.e., similar
2to lettuce and cabbage), d (2) a vegetation yie of 2 kg/m ,|
.
3/4.12. 3 'INTERL ATORY COMPARISON PROGRAM
The re _ rement for participation in an approved Interlabora ComparisonProgram i rovided to ensure that independent checks on the precisio,n 'id accu-racy of e measurements of radioacti,ve material in environmental sample
O matr' s are performed as part of the quality assurance program for environ- .
~[- m al monitoring in order to demonstrate that the results are valid for the
.
rposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. .
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CALLAWAY - UNIT 1 B 3/4 12-2 -..
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REVISloy 3ADMINIS1RAllVE CONTR01.5 ,_,
PROCLDUHl'g ND PRUGRAM) (Continued). A'
'-
\ lurbine Overspeed Protectinn Reliability Programe.
A program to increase the assurance that the Turbine Overspeed |Protection System functions, if challenged, and to assure structural '
integrity of turbine components which could result in missile gen-eration'in the event of an actual overspeed occurrence. The pro-. , ,
gram shall include the following:
1) Periodic testing and inspection requirements,2) Specification of test and inspection intervals, and3) Administrative restrictions and procedural guidance for !
program implementation such as: record keeping; reporting;evaluation and disposition of discrepancies; review and.
approval of revisions to the program; and authorization (s)required to program guidelines.
6.9 REPORTING REQUIREMENTS.
ROUTINE REPORTS .
In addition to the applicable reporting requirements of Title 10, Code6.9.1of Federal Regulations, the following reports shall be submitted to the RegionalAdministrator of the NRC Regional Office unless otherwise noted.
STARTUP REPORT
- 6. 9.1.1 A summary report of plant startup and power escalation testing shallbe submitted following: (1) receipt of an Operating License, (2) amenament tothe ticense involving a planned increase in power level, (3) installation offuel that has a different design or has been manufactured by a differest fuelsupplier, 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 theFSAR and shall include a description of the measured values of the operatingconditions or characteristics obtained during the test program and a comparisonof these values with design predictions'and specifications. Any correctiveactions that were required to obtain satisfactory operation shall also bedescribed. Any additional specific details required in license conditionsbased on other commitments shall be included in this report.6. 9.1. 3 Startup Reports shall be submitted within: (1) 90 days followingcompletion of the Startup Test Program, (2) 90 cays following resumption orcommencement of commercial power operation, or (3) 9 fronths following initialcriticality, whichever is earliest. If the Startup Report does not cover allthree events (i.e. , initial criticality, completion of Startup Test Program, andresumption or commencement of commercial operation) supplementary reports shallbe submitted at least every 3 months until all three events have been completed.
.
.A.N_NUAL REPORTS
6.9.1.4 Annual Reports covering the activities of the unit as described belowf or the previous calendar year 7, hall be submitted prior to March 1 of eachyear. The initial report shall bt submitted prior to March I of the yearfollowing initial criticality.
CALLAWAY - UNIT 1 6-17*
i
m.1 .__.
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Insert B
f. Radioactive Effluent Controls Program
A program shall be provided conforming with10 CFR 50.36a for the control of radioactive effluentsand for maintaining the doses to MEMBERS OF THE PUBLIC
|
from radioactive effluents as. low as reasonably ;
achievable. The program (1) shall be contained in theODCM, (2) shall be implemented by operating procedures,and (3) shall include remedial actions to be takenwhenever the program limits are exceeded. The programshall include the following elements:
1) Limitations on the. operability of radioactiveliquid and gaseous monitoring instrumentationincluding surveillance-tests and setpointdetermination in accordance with the methodologyin the ODCM,
2) Limitations on the concentrations of radioactivematerial released in liquid effluents toUNRESTRICTED AREAS conforming to 10 CFR Part 20,Appendix B, Table II, Column 2,
3) Monitoring, sampling, and analysis of radioactiveliquid and gaseous effluents in accordance with10 CFR 20.106 and with the methodology andparameters in the ODCM, ,
l
4) Limitations on the annual and quarterly doses ordose commitment'to a MEMBER OF THE PUBLIC from
I
Lradioactive materials in liquid effluents released
' from each unit to UNRESTRICTED AREAS conforming toAppendix 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 yearin accordance with the methodology and parametersin the ODCM at least every 31 days,
6) Limitations on the operability and use of theliquid and gaseous effluent treatment systems toensure that the appropriate portions of thesesystems are used to reduce releases ofradic. activity when the projected doses in a 31-dayperiod would exceed 2 percent of the guidelinesfor the annual dose or dose commitment conformingto Appendix I to 10 CFR Part 50,
- _ _ _ - _ - - _ _ _
__ - __ -_ - -_ - - _ _ _ -
-! s
s
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"tInsert B continued-
6.8[4.f. ' Radioactive' Effluent Controls Program (Cont.)'
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 11,
8) Limitations ~on the annual and quarterlyfairdoses resulting'from noble gases released in-. gaseous'effluentsLfrom each unit to areas-beyond the SITE BOUNDARY conforming to. Appendix I to 10 CFR Part 50,,
1
9)^ : Limitations'on the annual and quarterly doses~
1to a MEMBER OF THE PUBLIC from Iodine-131,. Iodine-133,-tritium, and all radionuclides in. particulate. form.with half-lives greater than8 days'in gaseous effluents released fromeach unit to areas beyond the SITE BOUNDARY-conforming to Appendix I to 10 CFR Part 50,
10) Limitations on the annual dose or dosecommitment to any MEMBER OF THE FUBLIC due toreleases of radioactivity and to radiationfrom uranium fuel cycle sources conforming to40 CFR'Part 190.
g. Radiological Environmental Monitoring Program
A program shall be provided to monitor theradiation and radionuclides in the environs of the" plant. .The programLshall provide (1)representative measurements of radioactivity inthe highest potential exposure pathways,. and (2)
L 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 guidanceof Appendix I to 10 CFR Part 50,.and (3) includethe following:
1) Monitoring, sampling, analysis, and reportingof radiation and radionuclides in the. environment in accordance with themethodology and parameters in the ODCM,
_ - _ _ _ _ _ _ _ - - _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ _. . - _ . .
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Insert B' continued.
.
2)' A L'and'Use~ Census.to ensure that changes inV the use of areas at and beyond.the SITE-
BOUNDARY..are identified.and'thatmodifications to:theanonitoring program are,'
cmade if required by the resulto of thiscensus; and
3) Participation in.a Interlaboratory_ ComparisonProgram to ensure;that independent' checks onthe precision andLaccuracy of;the=measurements of, radioactive materials inenvironmental sample matrices'are performedH
,
.as part of:the quality ascurance program forenvironmental monitoring.
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ADMINISTRATIVE CONTROLS __
' |-ANNUAL REPORTS _(Continued)|
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 (includingcontractors) receiving exposures greater than 100 mrems/yr and their associatedman-rem exposure according to work and job functions,* e.g., reactor operations~' '
and surveillance,; inservice' inspection, routine maintenance, special mainte-nance (describe maintenance), waste processing .and refueling. The doseassignments to various duty functions may be estimated based on pocket dosi-meter, TLD, or film' badge measurements. . Small exposures totalling less than20% of the individual total-dose need not be accounted for. In the aggregate,at least. 80% of'the total whole body dose received from external sourcesshould be assigned to specific major work functions.
~
The report shall also include the results of specific activity analysis inwhich the primary, coolant exceeded the limits of Specification 3.4.8. The
pfollowing infonnation shall be' included:- (1) Reactor power history starting .
(2) Results'48 hours prior to the first sample in which the limit vias exceeded: -
of the-last isotopic analysis for radioiodine performed prior to exceeding --
the limit, results of analysis while limit was exceeded and results of oneanalysis after the radiciodine activity was reduced to less than limit.Each result should include date and time of sampling and the radiciodine- .
concentrations; (3) Clean-up system flow history starting 48 hours prior tothe first sample in which the limit was exceeded; (4) Graph of the I-131concentration and one other radiciodine 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 radiciodine Ifmit.
ANNUAL RADIOLOGICAL ENVIRONMEitTAL OPERATING REPORT **
nh.
6.g.1.6^ tv .. uni Rodk,legicsi O .i.e,-nt.PCperanng Repor
i; w.}a6 ion of.
ing e previous calendar year s submitted*
for to May 1 f each year. "tial report s 61' u mi prior .o
1 of the r following in ial er .
Oper(ing Re shall inc1 de;The Annual diological nviro; ries, i te retations, nd ysis of rends of tp 1 ts o
the[adio ogical envi onmental ypre adce activi ies fo th report od,t
inclu ing a compar(son tfi preoperat onal studies, w th peration 1 co 1s
and wi p vious to ental survei lance ports, n an assess nt of ,.
the obs cts f e plant opera on n the env p nment. The reportsshall' nel u' a- t'.c . =1ts-of4and-U nsusas-voquired by 5 F4fi
.9 1HseRT c.-
1
-
~ * This tabulation supplements the requirements of 820.407 of 10 CFR Part 20.
** A single submittal may be made for a multiple unit station. lI
CALLAWAY - UNIT 1 6-18 Amendment No. 27I
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__
Insert C
6.9.1.6 The Annual Radiological Environmental OperatingReport covering the operation of the unit duringthe previous calendar year shall.be submittedbefore May 1 of each_ year. The report shallinclude summaries, interpretations, and analysisof trends of the results of the RadiologicalEnvironmental Monitoring Program for the reportingperiod. The material provided shall be consistentwith the objectives outlined in (1) the ODCM and(2) Sections IV.B.2, IV.B.3, and IV.C of AppendixI to 10 CFR Part 50.
,
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'(II|-
ADMINISTRATIVE C0itTROLS
,
Al1NUAL RADIOLOGICAL ENVIRONMENTAL OPERATIf1G REPORT. (Continued),
__
'
Annual Radiological Envir'onmental Operating Reports Js ar includef all j
the resu saf analysis of all radiological environmental,sa:fiples and oenvironmental ation measurements. taken during thepfied pursuant to the [
- .."
locations specifie in4he Table and Figures in the1DCM, as well as'
summarized and tabulated}esq1ts of these andyibs and measurements in theformat of the table in the Radio ogical Assessment Branch Technical Position,Revision 1, November 1979. In the 6 that so=e individual results are notavailable for inclusion with the re' port, 'e report shall be submitted noting
"1ts. The missing data shalland explaining the reasons (for'the missing rbe submitted as soon as sible in a supplementha eport.
The reports shall also include the followir.g: a s . ry description ofthe radiologij.a1,. environmental. monitoring program; at least twDoegible maps ***
LcoveringjM sampling locations keyed to a table giving distances andN4 ectionsfrom the centerline of one reactors the results of licensee participation n 7
,-
.
s
.
.. .
1 e th i s t
CALLAWAY - UNIT 1 6-18a Amendment No. 27.
e
- --_um. - _ _ _ _ _ _
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I-
REVISlay y )-
'7,[' : ADMINISTRATIVE CONTROLS
. -.-
ANNUAL' RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ** (Continued)4
. h ieri a ..t g ca m ehnn peg- .. anu tne corrective action being takf if.the ied program is not being performed as required b ation
3.12.3; reasons of not conducting the Radiological ental Monitoring ].
Programasrequiredby)tc441cQion tscussion of all deviations ].from the sampling schedule discussion of environmental' sample jmeasurements.tha ed the reporting leve 3.12-2 but are not theresult o plant effluents, pursuant to Specification discussionof analyses in which the LLD required by Table 4.12-1 was not achievevi
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT *t
6.9.1.7 o em'TannuePRacioactTW Efflucou neiene neports covering theera ion of tne unit during the previous 6 months of operation shall be*
mitted within 60 days af ter January 1 and July 1 of each year. The per d -s
of t first report shall begin with the date of initial criticality. -
'k The miannual Radioactive Effluent Release Reports shall incly asummary of quantities of radioactive liquid and gaseous effl hts andsolid waste re ogsed from the unit as outlined in Regulatory de 1.21," Measuring,EvaluTtfng,andReportingRadioactivityinSol Wastes and
*
Releases.of Radioactke Materials in Liquid and Gaseous fluents frcan,
Light-Water-Cooled Nucl r Power Plants," Revision 1 une 1974, with dataf. e summarized on a quarterly sis following the fo of Appendix B thereof.,
i ', f For solid wastes, the format qr Table 3 in Ap ndix B shall be supplementedwith 'three additional categorieh class of olid waste (as defined by 10 CFRu-
Part 60), type of container (e.g. , A, pe A, Type B, Large Ouantity), and .
SOLIDICATION agent or absorbent (e.g. ement, urea formaldehyde).The' Semiannual Radioactive y fluent R Qase Report to be submitted within
60 days af ter January 1.of ea.c(year shall inM de an annual summary of hourlymeteorological data collec d over the previous This annual summary may.
be either in the form o, an hour-by-hour listing on og etic tape of windspeed. wind directi , atmospheric stability, and precip on (if measured),or in the form o oint frequency distributions of wind speed, d direction,and atmospher stability.** This same report shall include an a wussment ofthe radiat~ doses due to the radioactive liquidjand gaseous effluen'ts releasedfrom th init or station during the previous calendar year. This same re rtshal 15o ir.clude an assessment'of the radiation doses from radioactive
|1 sid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their activities
D456RT C C-~
__
"A single submittal may be made for a multiple unit station. The submittalshould combine those sections that are common to all units at the station;however, for units with separate radwaste systems, the submittal shallspecify the releases of radioactive material from each unit.
n li3u of mission ytt the Semiannual Radio tive E Jent aseg
epprL, t li enseeAas t e optjin of etal ing his .umm 3r r qu d
mepeorolpgical dat.4 on sit in 4 file tlat shall e rovidt# to th R /~
gon p uest.
CALLAWAY - UNIT 1 6-19 '
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_ _ _ - _ _ _ _ -
Insert'CC
6.9.1.7 The Semiannual Radioactive Effluent Release Report j'
covering the operation of the unit during the Iprevious 6 months of operation shall be submitted
{within 60 days after January 1 and July 1 of eachyear. The report shall include a summary of thequantities of radioactive liquid and gaseous 4effluents and solid waste released from the unit, d
The material provided shall be (1) consistent with lthe objectives outlined in the ODCM and PCP and {(2) in conformance with 10 CFR 50.36a and Section jIV.B.1 of Appendix I to 10 CFR Part 50. '
|
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_
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.
REVIStay ,t ~,.., ,
ADMINISTRATIVE CONTROLS . "A.5 .Jg.
_ SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT * (Continued)-- _-
-~ ,
b de the SITE B0UNDARY (Figures 5.1-3 and 5.1-4) during the report periodusing istorical average atmospheric conditions. All assumptions used in ma ngthese as ssments, i.e..' specific activity, exposure time and location, sh beincluded i these reports. The meteorological conditions concurrent wi hetime of relea of radioactive inaterials in gaseous effluents, as dete ned bysampling freque and measurement, shall be used for determining th ' gaseouspathway doses. Th assessment of radiation doses shall be perform in accord-fancewiththemethod1pgyandparametersintheOFFSITEDOSECAL LATION MANUAL
(DDCM).
The Semiannual Radioact v Effluent Release Report to e submitted within60 days af ter January 1 of each ear shall also include assessment of Iradiation doses to-the likely.mos exposed. MEMBER OF T PUBLIC from ReactorL **
releases and other nearby uranium f cycle sources including doses from ,
primary effluent pathways and direct r iation, fo the previous calendar year f ..
to show conformance with 40 CFR Part 190, "Envi mental Radiation ProtectionStandards for Nuclear Power Operation." Ac ble methods for calculatingthe dose contribution from liquid and gaseo ffluents are given in RegulatoryGuide 1.109, Rev. 1, October 1977.
.
|
t The Semiannual Radioactive Efflye'nt Release Re rts shall include a list ,
'
and description of unplanned releases from the site UNRESTRICTED AREAS of yradioactive materials in gaseous nd liquid effluents de during the reporting f|, .period. ' fa-
The Semiannual Radio ive Effluent Release Reports sha 1 include any' changes made during the porting period to the FCP and the O M, pursuant ton Specifications 6.13 an .14, respectively, as well as any majo change to
. Liquid, Gaseous, or lid Radwaste Treatment Systems, pursuant t Specifica- .
tion 6.15. 'It sha) also include a listing of new locations for se calcula-tions and/or.env'fonmental monitoring identified by the Land Use C.e us pursuantto Specificati 3.12.2.
The S iannual Radioactive Effluent Release Reports shall also inc e
the foll ing information: An explanation as to why the inoperability of a
liquid r gaseous effluent monitoring instrumentation was not corrected wi in lthe me specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and {de ription of the events leading to liquid holdup tanks or gas storage tanks j
e eeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively. J
HONTHLY OPERATING REPORT
6.9.1.8 Routine reports of operating statistics and shutdown experience,including documentation of all challenges to the pressurizer PORVs or RCSsafety valves, shall be submitted on a monthly basis to the Director, Officeof Resource Management, U.S. Nuclear Regulatory Commission, Washin-) ton, D.C. ,
20555, with a copy to the NRC Regional Office, no later than the 15th of each !
month following the calendar month covered by the report. |
.) |
CALLAWAY - UNIT 1 6-20 ]~
I
t
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.
ADMINISTRATIVE CONTROLS
RECORD RETENTION (Continued)
Records of changes made to the proteoures required by Specification je.6.8.1;
f. Records of radioactive shipments;*.
Records of sealed source and fission detector leak tests and results;g.and
h. Recorcs of ar.nual physical ir.ver. tory cf all sealed source raterialof record.
5.10.2 The felicsin; rccords shall be retained fcr the d:;raticn of the unitOperating License:
Records and crtwing cranges reflectir.; uni: cesign : deificationsa.cade tc systers and ecuioment described in the Final Safety AnalysisRecort: 1
b. Records of new and irradiated fuel inventory,. fuel transfers andassembly burnup histories;Records of radiation exposure for all individuals entering radiationc.control areas;
d. Records of gaseous and liquid radioactive material released to the -environs;
Records of transient or operational cycles for those unit componentse.identified in Table 5.7-1;
f. Records of reactor tests and experiments;Records of training and qualification for current members of theg.-
unit staff;
h. Records of in-service inspections perforned pursuant to these.Technical Specifications;
i. Records of quality assurance activities required by the QA Program;
j. Records of reviews performed for changes made to procedures orequipment or reviews of tests and experiments pursuant to10 CFR 50.59; ;
k. Records of meetings of the ORC and the NSRB;
1. Records of the service lives of all hydraulic and mechanical snubbersrequired by Specification 3.7.8 including the date at which theservice life commences and associated installation and maintenance~
I records;
Records of secondary water sampling and water quality; andm.
Records of analysis required by the Radiological Environmentaln.Monitoring Program that would permit evaluation of the accuracy
should include proceduresof the analysis at a latesdateMhi4'h ds showing that theseeffective at spetjMfd times and QA reprocedures wer ellowed.
Insed- ~D
CALLKn'AY - UNIT 1 6-22 Amendment No. 28 i
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Insert D
o. Records of reviews performed for changes made toAPA-ZZ-01003, the OFFSITE DOSE CALCULATION MANUALand APA-ZZ-01011, the PROCESS CONTROL PROGRAM.
1.
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.
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.
. ADMINISTRATIVE CONTROLS
} .3'
HIGH RADIATION AREA (Continued).
in radiation protection procedures to provide ppsitive exposure control overthe activities being performed within Lhe area.
lor individual high radiation areas accessible to personnel with radiationlevels of greater than 1000 mR/h that are located within large areas,'suchas PWR containment, where no enclosure exists for purposes of locking, andwhere no enclosure can be reasonably constructed around the individual area,.
l. that individual area shall be barricaded, conspicuously posted, and a flashinglight shall be activated as a warning device.
6.13 PROCESS CONTROL' PROGRAM (PCP)
IN5ER T F_.,
.1 The PCP shall De appivved by who L.ommission prior to implementation .,
6.13.2 ensee-initiated changes to the PCP:
a. Shall submitted to the Commission in the Semiannua adioactiveEffluent lease Report for the period in which change (s) wasmade. This bmittal shall contain:
Sufficiently ailed informat to totally support theJ
1)rationalefort(hdqangew' out benefit of additional or
-supplemental informa ,
,
I' 2) 'A determinate hat t e did not reduce the overall ' '\ .I 1-conforman of the solidified ste product to existing cr.iteria .,
for so 'd wastes; and '
3) documentation of the fact that the change s been reviewed andfound acceptable by the ORC.
'
Shall become effective upon review and approval by the ORC in.
accordance with Soarifir=tinn 6 U .1.
f 6.14- 0FFSITE DOSE CALCULATION MANUAL (ODCM)FIN SERT -,
1 lhe N e!' M cpp ewed L.y the CEmmission17tm te i .p1mcHcaT.ivo.-
.
6.14.2 Lic %nitiated changes to the ODC!i:
a. Shall be s mitttd to the Commission in the Sem pi al RadioactiveEffluent Release R#por(for the period in,which the change (s) wasmade effective. This suDmi. c6ntain:
1) Sufficiently deta An7ormatic to totally support therationale for hange without b it of additional orsuppleme i nformation. Information s 'tted should consistof ekage of those pages of the ODCM to be ed with each
~ge numbered, dated and containing the revision nu togetherwith appropriate analyses or evaluations justifying th (e chso e(s); )
. __
/''
CALLAWAY - UNIT 1 6-24 "
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.-
L
Insert E
6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
a. Shall be documented and records of reviewsperformed shall be retained as required bySpecification 6.10.2o. This documentation shallcontain:
1) Sufficient information to support the changetogether with the appropriate analyses orevaluations-justifying the change (s) and
2) A determination that the change will maintainthe overall conformance of the solidifiedwaste product to existing requirements ofFederal, State, or'other applicableregulations.
b. Shall become effective after review and acceptanceby the ORC and the approval of the Plant Manager.
Insert F
6.14 OFFSITE DOCE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
a. Shall be documented and records of reviewsperformed shall be retained as required bySpecification 6.10.2o. This documentation shallcontain:
1) Sufficient information to support the changetogether with the appropriate analyses orevaluations justifying the change (s) and
2) A determination that the change will maintainthe level of radioactive effluent controlrequired by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part50 and not adversely impact the accuracy orreliability of effluent, dose, or setpointcalculations.
b. Shall become effective after review and acceptanceby the ORC and the approval of the Plant Manager.
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c. Shall be' submitted to the Commission in the: form'
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H of a. complete, . legible' copy of.the entire:ODCM asa part of'or concurrent.with the Semiannual 1
-Radioactive Effluent Release Report-for-the period-of the report in which any' change::to the.0DCM wasmade. Each change shall be identified by' markings'in the margin |of the'.affected pages, clearly i
indicating the area'of_the page-that was changed,7 ' and shall indicate the date.-(e.g., month / year) the
_ change was implemented.
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ADMINISTRATIVE' CONTROLS
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urr h DG5E--CALCutal10N MANUAL (OUGM) (Continued)-
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ination that the change will.not reduc accuracy orreliabil dose calculations or Set determinations; >
and .
- 3). Documentation of act tha change has been reviewed.andfound acc e by the ORC.
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b. S ecome effective upon review and approval by the\andinaccordance with Specification 6.5.3.1. q
MAJORCHANGEST0-LIQUID, GASEOUS,ANDSOLIDRADWASTETREATMENTSYSTEM[
6.15.1 icensee . initiated major changes to the.Radwaste Treatment Syst .s(liquid, eous,'and solid):
a .- tShal reported.to the Commission in the Semiannual R ioactive'Effluen elease' Report for the period in which the ev uation was.
reviewed b he ORC. Th'e discussion of each change iall'contain:
'1) A summary the evaluation that led to the determination thatthe change co d be made in accordance wi 10 CFR 50.59;
}- f 2) Suf ficient detail ' information to tot ly support the reasonfor the change with t benefit of ad tiona'l or supplemental
,C \ information;\9,'
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iV.. 3) A detailed description o he uipment,. components and processes
(,) . involved and the interface .i h other plant systems;d-
- 4) An evaluation of the chan ,w * h shows the predicted releasescof radioactive material in liq Ed and gaseous effluents and/orquantity of solid was that diff y from those previouslypredicted in the Li nse applicatio' and amendments theretc;
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5) An evaluation oEMBER OF THE PUBLIC in k. the expected maximumthe change, which sh
e UNRESTRICTED AREA and-
- exposures toto the gene population that differ from those previouslyestimated n the License application and am' dments thereto;
j. h 6) A com rison of the predicted releases of radio tive materials,T in' quid and gaseous effluents and in solid wast to the actual
r eases for the period prior to when the changes a ..to be made:
7) An estimate of the exposure to plant operating personne as aresult of the change; and
' *Li' nSees may chose to submit the information called for in this specification.
part of the annual FSAR update.
CALLAWAY - UNIT 1 6-25,
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''4 MAJOR CHAN O LIQUIDi GASEOUS, AND SOLID RADWAS TREATMENT' SYSTEMS
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s 8) .Documentat1B . fact that the change was reviewed and found3acceptab1pAff 'DA
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approval by the ORC and in.
. .. bome effective upon revi.
'Sha p~ dance with Specification 6.5.3.1.' b. .
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kAttachment 2
. ULNRC- 20 7 0 -
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! SAFETY EVALUATION :
This amendment. request implements changes concerning.I the radiological and environmental Technical Specifications ;
.(TS). .'The changes simplify the TS, while maintaining '!_
regulatory requirements. Procedural details of the -!Radiological Effluent Technical Specifications (RETS) are- !
relocated from TS to the Offsite Dose Calculation Manual-(ODCM), and for solid radioactive wastes to the ProcessControl Program (PCP). In all cases the programmaticcontrols are retained in the Administrative Controls sectionof the TS. ~The! changes are based upon the guidance given inGeneric Letter _89-01. .In adoition an inappropriate footnote.
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reference to Callaway as'a multiple unit-station is deleted.This is a purely administrative change.
In Generic Letter 89-01 the NRC staff determined that~
programmatic controls can be implementedzin theAdministrative' Controls section of TS to' satisfy existingregulatory requirements ~for RETS. At the same time theprocedural details can be relocated to the ODCM of the PCPas appropriate. The changes are consistent with theCommission's' goals for TS Improvements.'
The proposed changes do not alter the content of theinvolved programs nor their implementation to meet.theregulatory requirements. Revisions to the RETS remain underadequate controls and allow continued reporting for NRCreview and oversight. The substance of the proposed changesinvolves only administrative and documentation revisions,without1 a lessening of commitments in these areas. Thechanges do-not impact the severity or the consequences of anaccident. They do not impact on the probability of anaccident occurring or a>different accident than one alreadyevaluated.
Based on the above discussion, the proposed TechnicalSpecification changes do not adversely effect or endangerthe health or the safety of the general public and do notinvolve an unreviewed safety question.
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Attachment 3ULNRC-2070
SIGNIFICANT_ HAZARD EVALUATION
This amendment requent implements changes concerningthe radiological and environmental Technical Specifications(TS). The changes simplify the TS, while' maintainingregulatory requirements. Procedural details of theRadiological Effluent Technical Specifications (RETS) arerelocated from TS to the Offsite Dose Calculation Manual(ODCM), and for solid radioactive wastes to the ProcessControl Program (PCP). In all cases the programmaticcontrols are retained in the Administrative Controls sectionof the TS. .The changes are based upon the guidance given inGeneric Letter 89-01. In addition an inappropriate footnotereference to Callaway as a multiple unit station is deleted..This is a purely administrative change.
In Generic Letter 89-01 the NRC staff determined thatprogrammatic controls can be implemented in theAdministrative Controls section of TS to satisfy existingregulatory requirements for RETS. At the same time theprocedural details can be relocated to the ODCM of the PCPas appropriate. The changes are consistent with theCommission's-goals for TS Improvements.
Union Electric has reviewed the proposed changes anddetermined that:
1. The proposed amendment does not involve asignificant increase in the probability orconsequences of an accident previously evaluatedbecause the_ proposed changes do not alter thecontent of the involved programs nor theirimplementation to meet the regulatoryrequirements.
2. The proposed amendment does not create thepossibility of a new or different kind of accidentthan previously evaluated because the change isadministrative in nature, and no physicalalterations of plant configuration or changes tosetpoints or operating parameters are proposed.
3. The proposed amendment involves an administrativetype change and does not involve a significantreduction in a margin of safety.
Revisions to the RETS remain under adequate controls j
and allow continued reporting for NRC review and oversight.The substance of the proposed changes involves onlyadministrative and documentation revisions, without alessening of commitments in these areas.
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Attachment 3ULNRC-2070
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The Commission has provided guidance concerning the )application of the standards in 10CFR50.92 by providing i
;'' certain examples (48 FR 14870), One of the examples ofactions involving no significant hazards consideration j
relates to a purely administrative change to TechnicalSpecifications.
.These requests do not involve a significant increase in"
the probability or consequence of an accident or otherj adverse condition over previous evaluations; or create the| possibility of a new or different kind of accident or
conditions over previous evaluations; or involve a'
significant reduction in a margin of safety. Based on thisinformation, the requested license amendment does notpresent a significant hazard. ,
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