Annual Operating Rept 1978.

Sa 2.wq

>~ala So~>g

P8K, < f3 llDLE3 PRKlRL%

ANNUAL REPORT OF CHANGES K) STATION FACILITIES AND PRCCEIXJRES

R. E. GINNA NUCLEAR KNER PLtÃZ~ UNIT NO. 1

DOCKEZ NO. 50-244

LICENSE NO. DPR-18

1978

NEmyy@F/Lfg @@0 ttg)g

. ~'79 0905 0

ANNUAL REPORT OF CHANGES 1Q STATICN FACILITIES AND PROCEIXJRES

R. E. GINNA NUCLEAR KNER PLANT, UNIT NO. 1

DOCKET N). 50-244

LICENSE NO. KPR-18

1978

Sc.2%9>8-si-6mo~os<4~$

PCN 4 78 Procedure a Title Meetin g 78

Ol

02

05

04

03

06

22

27

31

17

QC-1502, Nonconformance Reports

QC-1701, Quality Assurance Records

QC-401, Control of Procurement Documents forPurchased Material, Parts, Components andServices

ET-19, Test of Accoustical Leak MonitoringSystem for Ginna Safety Injection Piping

PZ-2.3, Safeguard Valve Operation

A-30. 2, Plant Procedure Classification Review,Approval and Distribution Requirements

M-55.5, Full Length Rod Control System DriveMechanism Operating Coils Polarity Check

M-51.4 Performance Check of Latch Mechanism forRelay LC-171CX

EM-197, Repair of Weld on "B" Charging PumpDischarge Line to Relief Valve 284

A-52.4, Control of Limiting Conditions forOperating Equipment

M-ll.4.4, Charging Pump Varidrive Belt Renevaland Installation

02

02

02

03

03

03

04

04

05

06

07

07

21

32

,23

29

14

18

~ EM-19 Inspection and Maintenance on 14" PrattButterfly Valve —Operator Only —Valve 4562(Containment Recirculation System —CoolingWater Return Line)

M-18.2, Waste Evaporator Feed Tank Float ValveMaintenance

E-l.l, Safety Injection System Actuation

A-50.11.3, Fire Watch/Escort Training

A-50.11.4, General Employee Fire Training

A-50.3, Preventive Maintenance Program

0-6-7-1, Plant Alarm Panels Test

0-6.4, Core Quadrant Power Tilt Calculation

07

07

07

07

07

07

07

07

l1

1

P

PCN I 78 Procedure 6 Title Meetin I 78

15 0-6.1 Plant Operation with S/G Tube Leak Indi-cation

07

24

28

S-3.2G, Transfer of Boric Concentrates

SC-3.17.1, Planning Conduct and Evaluation ofa Fire Emergency DrillQC-401, Control of Procurement Documents forPurchased Material, Parts, Components andServices

07

07

07

19

34

RSSP-2.3, Emergency D/G Annual Trip Testing

O-l. 1C, Pre-Critical Technical Specif icationCheck Sheet

07

07

12 (g-1021, Calibration and Control of Test +uip-ment

07

08 GS-21.0, Site Access Control (Security) andPersonnel Identification

07

33

35

36

09

37

40

41

26

A-61, Method of Evaluation for Reporting Require-ments in Basic Components Under 10 CFR 21

M-55.5, Full Length Rod Control System Drive Mechan-ism Operating Coils Polarity Check

GS-31. 0, Door Alarm System

GS-20.0, Classification of Ginna Station PhotoID Cards and Non-Photo Badges

PT-4, Residual Heat Removal Loop Annual HydroTest of Law Pressure Piping

CP-44.2, General Reinstate Procedure for N-44

PT-16, Auxiliary Feedwater System

M-ll.4.9, Charging Pump Varidrive Belt Removaland Installation

07

07

07

07

07

08

08

08

39

43

SC-1.12B, Station Call List

M-37.16A, Manually Cperated Grinnell DiaphragmValve Maintenance

08

08

PCN 0 78 Procedure & Title Meetin 578

30

47

48

46

79

None

None

None

RSSP-12, Testing of Primary and Secondary ReliefValves on Test Stand

RD-9, Preparing Waste for Shipment or Storage

RD-10, Shipping Radioactive Material

0-5.2, Load Increases

0-1.1C,'re-Critical Technical Specif icationCheck Sheet

SM 78 1458 g Auxiliary Building Holding FrameFilterSM 78-1845, Guide Stud Storage Rack

SM 78-1865, "A" Steam Generator Air MoverRestraint

08

08

08

08

09

10

10

10

None

None

None

81

62 & 65

63

64

51

42

45

77

SM 78-1480, Auxiliary Reactor Coolant PumpHandrails

SM 78-1464, Volume Control Tank Level(Accumulator Level)

SM 78-2160, GSM 7 Pipe Supports

S-25.4, Processing Water from Either S/G

S-4.5, Sluicing Water Condensate Polishing~ Demineralizer Spent Resin to Shipping Cask

CP-930.0, Calib. and/or Maint of Spray AdditiveTank Inlet Flow Transmitter Loop

CP-424.3, Calib. and/or Maint. of PressurizerLiquid Temp. Indicator TI-424

HP 4.3, Work Permit Use

PC-18.3, Determination of Chloride ky SpecificIon Electrode

S-27.294/296/392A, Isolation Procedure for AOV-294,AOV-296 or

AOV-392'P-12.6,

Issuance, Proper Use and Return of Respira-tors

10

10

10

10

10

10

10

10

10

10

10

PCN 5 78 Procedure 6 Title Meetin 5 78

60

52

A-52.4, Control of Limiting Conditions for OperatingEquipment

A-53.1, Equipment Inspection Period and LubricantList

10

10

54 A-53.0, Preventive Maintenance Program

69 A-49, Station Security

10

10

53

55

74

75

82

84

A-53.2, three &anth Lubrication and MaintenanceInspection

PT-2.8, Component Cooling Water Pump System

PT-13.1.13, Deluge Valve System Testing SystemNumbers 1, 2, 11 ~

PI'-13.1.5, Flood Valve System Testing SystemNumbers 3, 4, 5, 6

PT-17.1, Area Radiation Monitors

A-58, Installation of Power, Control or Instru-mentation Cables at Ginna

10

10

10

10

10

10

44

58 a 59

M-37. 3, Maintenance on Copes-Vulcan DiaphragmOperated Control Valves for AOV-

GS-18.1, Conduct of cn-the-job Training ofGuards

10

10

61 GS-9.0, Walkie-Talkie Procedure for the SecurityForce

10

67 GS-30.0, 'Ihreatening Phone Call or BombThreat'rocedure

10

68

66

76

None

70

81

GS-32. 0, Civil Disturbance Procedure

GS-3.0, Security Call List

PC-14.1, Boron in WEFI and WHVZ Waters

Liquid Waste Release 567

0-6.10, Plant Operation with Steam Generator TubeLeak Indication

S-25.4, Processing Water from Either Steam Generator

10

10

10

PCN I 78 Procedure a Title Meetin I 78

91

103

'Z-2. 5, Air Operated Valves, Quarterly Surveillance

SN 77-13.2, Inspection of Containment AntennaCoaxial Cable

12

88

109

108

85

123

87

100

Q=-603, Control of Drawings

A-55.1, Field Change Requests to EngineeringDocuments

(g-105, Indoctrination and Training of Modifica-tion Project Personnel

QC-402, Control of Procurement Documents forMaterials and Services Purchased by the GinnaModification Project

QC-606, Control of Engineering Documents

QC-304, Control of Modification Activities by theGinna Modification Project

9 -202, Modification Project Organization

0-1.1, Plant Heatup From Cold Shutdown to HotShutdown

12

12

12

12

12

12

12

101

102

PZ-7, Hydro Test of Reactor Coolant, System

0-2.2, Plant Shutdown From Hot Shutdown to Cold. Shutdown

12

12

104

138

139

94

97

106

RD07, Liquid Waste Release

EH-154, Steam Generator Handle CoverGasket Leak Repair Using "Furmanite" Process

T-7C, Regeneration of Cation-Anion DI Unit

S-3.3A, Coolant Chemistry Addition Tank

EM-198, Replacement of the Buchanan TerminalBlocks for Pressurizer Pressure and Level Trans-mitters Terminations with a Westinghouse StyleN542247 Terminal Block

PZ-2.4, Cold Refueling Motor Operated Valve Sur-veillance

12

12

12

12

12

12

PCN ¹ 78 Procedure 6 Title Meetin ¹ 78

107

24

121

95

83

110

90

S-2.4A, Draining the Pressurizer (RCS Degassed)

S-3.3A, Coolant Chemistry Addition Tank

W-101, Ginna QA Program Implementation

GS-l. 2, Security Event Report

A-30.3, Plant Procedure Content and FormatRequirements

0-6.11, Routine Operations Check Sheet

E-1.2, Zass of Coolant Accident

PT-2. 6, Cold/Refueling Shutdown Air OperatedValve Surveillance

12

12

12

12

12

12

12

89 PZ-2.5, Air Operated Valves, Quarterly Sur-veillance

12

105

98

99

49

PT-6. 2, NIS Intermediate Range Channels

PT-23.14, CV Air Sample Inlet

PT-23.20, BC'as Header

M-29, Decontamination of R-18 Liquid Sampler

12

12

12

12

126, 129 & 0.2, Main Control Board System Status141 Verification

12

114

120

119

S-27.2776, Isolation of Valve 2276

S-3.1M, Isolation of Batching System

S-27.2, Isolation of CVCS Letdawn Demineralizersand Associated Valves

S-27.164SA, Isolation of Waste Evaporator ReturnValve 1654A

13

13

13

13

115

118

S-3.2J, Isolation of Reactor Coolant Filter andAssociated Grinnell Diaphragm Valves (249, 250, 251,248A 248B)

S-27.245, Isolation of Mixed Bed Demineralizer BypassValve 245

13

13

Procedure a Title Meetin I 78

S-27.1610B, Isolation of Demineralizer DrainValve 1610B

13

153 GS-26.1, Unoccupied Vital Area Key Control andAccountability

13

132

131

S-3.1G, Isolating, Flushing and Draining the"A" Boric Acid Storage Tank for Major ValveTank or Piping Maintenance and Inspection

0-2.2, Plant Shutdown for Hot Shutdown to GoldShutdown

13

130

128

127

0-2.4, Plant Shutdown from Hot Shutdown to ColdShutdown During Blackout

0-5.1, Load Reductions

0-5.2, Load Increases

13

0-6.9, Operating Limits for Ginna Station Trans-mission

13

149 M-37.3.2, AOV-296, Auxiliary Spray to PressurizerMaintenance

13

155

140

148

M-37.3.1, Maintenance Isolation Procedure for V-294Charging Line to Cold Leg Loop "B"

S-3.4, Boron Recycle Process Operation

HP-3.1, Exposure Reports to Individuals andNRC

13

13

152

151

136

HP-8. 4, Radioactive Source Inventory

PT-2.3.1, Post Accident Charcoal Filter Damgers

M-53, Containment Air Locks Inspection

13

13

135 M-40. 7, Steam Generator, Snubber Maintenance Snubber5

144 M-37.2, Maintenance of Pressurizer Relief ValveGuards

13

162

161

GS-21.2, Unoccupied Vital Area Access Control

GS-5.0, Security Guard General Instructions

13

13

PCN 0 78 Procedure a Title Meetin 5 78

147

157

158

150

145

170

183

173 a175

165

156

169

187A

RF.O, Site Removal of New Fuel Assembliesfrom Shipping Containers and Handling ofShipping Containers

HP-1.1, Issuing Personnel Dosimeters

HP-1.3, External Exposure Records

T-27.6, Diesel Fuel Oil Transfer Pump Isolation

T-27.4, Diesel Generator Operation

M-73.3, Welding on Carbon Steel Piping and Com-ponents


Reinstallation of Steam Generator BlowdownRestraint, SGB-28

SM 76-21.5, Battery Room Air Conditioning-ServiceWater Piping Installation

SM 76-21.4, Battery Room A'ir Conditioning-AirConditioner Discahrge Ducts, end of Battery Room

SM 76-21. 6, Battery Room Air Conditioning-AirSupply Duct to the Air Conditioner

SM 77-1832. 1,

13

14

14

14

14

14

14

14

14

14

24

179

178

160

159

174

172

CP-31.0, Calibration and/or Maintenance of Sourcerange N-31

CP-32.0, Calibration and/or Maintenance of SourceRange N-32

SC-1.12A, Immediate Call List


A-61, Method of Evaluation for Reporting Requirementsin Basic Corrponents Under 10 CFR 21

HP-6.2, Posting of Contaminated and Airborne Areas

14

14

14

14

14

14


181

180

166

189

78

167

176

CP-31.3, Calibration of Source Range N-31


PC-l.l, Analysis Schedule and Limits PrimaryCoolant

A-54.3, Open Flame, Welding and Grinding Permit

SM 77-1057.1, Relaocation of the Charging PumpFilter Vent

M-48.3, Isolation and Restoration of Bus e15

T-35F, Steam to Auxiliary Building, Screen Houseor Diesel Generators and Oil Room

14

14

14

15

15

15

184 T-31.8, Turbine Generator Bearing Drain Vapor Extractor 15Vent-Hydrogen Loss Calculation

93

113

HP-12.2, Medical Check, Fitting and Training ofPersonnel Using Respirators

M-11.4.6, Charging Pump Stuffing Box Maintenance

15

15

112 M-11.4.7, Charging Pump Stuffing Box Assembly Inspection 15and Maintenance

197 M-37.IA, Repacking of Pressurizer Spray Valves 43IA and 15431B

192

190

191

188

195

194

193

154

. M-37.16B, Isolation of Batching System GrinnelDiaphragm Valves

M-37.16N, Repair of Demineralizer Drain Valve 1610B

M-37.16P, Repair of Valve 2276

GS-5.0, Security Guard General Instructions

GS-28, Inspection of Personnel, Vehicle and Packages

, GS-21.0, Site Access Control (Security) and PersonnelIdentification

GS-41. 0, Employee Screening Program

QC-304, Control of Modification Activities by theGinna Modification Project

15

15

15

15

15

15

15

15

-10-

PCN I 78 Procedure & Title Meetin 5 78

194 a230

GS-21..0, Site Access Control (Security) and PersonnelIdentification

16

231 GS-5.0, Security Guard General Instructions 16

177 A-60.3, Calibration Survey Program for Instrumentation/ 16Equipment of Safety Related Components

186

205

206

204

RSSP-15.7, Inservice Inspection Hydro Test of Class BSafety Related Piping

.M-37.16Q, Isolation of CVCS Letdmm Demineralizers andAssociated Grinnell Diaphragm Valves

M-37.16K, V-245 (Mixed Bed Demineralizer Bypass Valve)Isolation Draining and Restoration to Service

M-37.16G, Isolation of Waste Evaporator Return Valve1654A

16

17

17

17

203

257

250

249

238

M-37.16F, Isolation of Reactor Coolant Filter andAssociated Grinnell Diaphragm .Valves

T-27.2, lB Emergency Deisel Generator Pre-StartAlignment

SM 76-21.5, Battery Room Air Conditioning ServiceWater Piping Installation

QCIP-15, Visual Inspection During Hydro-Static andSystem Pressure Testing

GS-21.0, Site Access Control (Security) and PersonnelIdentification

17

17

17

17

17

220

228

223

221

235

210

211

PT-2.7, Service Water System

GS-26.0, Security Key and Lock Controls

HP-9.1, Steam Generator Blowdawn Activity

RD-3, Plant Vent Iodine and Particulate Releas'e-Sampling and Analysis

A-l, Radiation Control Manual

AR/C-3, Accumulator IA Level

~C-4, Accumulator 1B Level

17

17

17

17

17

17

17

-11-

PCN O 78 Procedure & Title Meetin 0 78

207 AR/E-27, NIS Power Range Single Channel Lo RangeAlert

17

213

208

214

209

215

AR/D-20, Pressurizer Lo Pressure

~~15, Reactor Coolant Lo Flow UndervoltageUnderfrequency Zaop A

~M23, Reactor Coolant Lo Flow UndervoltageUnderfrequency Loop B

AR/D-10, NIS Power Range Lo Range Reactor Trip

~~19, Pressurizer Lo Pressure and Level

17

17

17

17

17

200

201

M-73.3, Welding on Carbon Steel Piping or Components 17

M-73.2, Welding on Stainless Steel Piping or Components 17

243

242

237

QCIP-3, Receiving Inspection of New Fuel

QCIP-2, Pre-closure Core Verification'S-31.1,Coor Alarm Assessment and Response —High

Radiation Areas

19

19

19

185 PR-7, Protective Relay Calibration and Trip Test 512ATransformer, 34KV and 4KV Bus Relaying

19

262 SM 76-21.6, Battery Room Air Conditioning —Air Supply 19Duct to the Air Conditioner

297

300

292

PT-7, Hydro Test of Reactor Coolant System

SM 76-21. 4, Battery Room Air Conditioning —AirConditioner Discharge Duct South End of Battery Room

S-3.4B, Gas Stripper Startup

19

19

19

266 CP-2.3, Rod Position Indication System "Shutdown" Bank 19Hot Shutdown Alignment

266 CP-2.3.1, Rod Position Indication System "Shutdown"Bank at Power Alignment

19

~ 289 A-30.2, Plant Procedure Classification, Review Approval 19and Distribution Requirements

264 GS-20.0, Classification oj Ginna Station PhotoID Cards and Non-Photo Bactges

19

-12-

PCN N 78 Procedure a Title Meetin N 78

251

240

A-17, Plant Operations Review Committee Operating2rocedure

4

A-30.3, Plant Procedure Content and Format Requirements 19

288

270

A-50.11.3, Firewatch/Escort Training

CP-2.5.0, Bod Position Indication System "A" BankHot Shutdown Alignment

19

19

269 CP-'2.4.1, Rod Position Indication System "Part Length" 19Bank at Power Alignment

268

265

299

259

258

279

CP-2.4.0, Rod Position Indication System "Part Length"Bank at Hot Shutdown Alignment

CP-2.0, Calibration and/or Maintenance of the RodPosition Indication System

PT-17.1, Area Radiation Honitors Rl-R9

PT-13, Fire Pump Operation and System Alignment

SC-3.15.15, Emergency Fire equipment LockerInventory and Inspection

CP-2.10, Rod Position Indication System MaintenanceCalibration Check.

19

19

19

19

19

19

296

256

CPO. 2, Rotameter Calibration

RF-8.4, Fuel and Core Component Mvement in theSpent Fuel Pit

19

19

305 RSSP-6.0, Containment Integrated Leakage Rate Test 19

283 PT-16, Auxiliary Feedwater System 20

343

344

A-30.2, Plant Procedure Classification, Review, Approval 20and Distribution Requirements

A-.30.3, Plant Procedure Content and Format Requirements 20

310

329

SC-3.15.6, Fire Hose Reel Inspection

A-60.1, Ginna Station Technical Specif icationSurveillance Program

20

20

-13-


334

307

308

312

314

313

298

395

30Ci

306

182

322

218

336

337

143

245

335

237

S-3.4J, Transferring Monitor Tank to RMÃ Tank

E-1.2, Loss of Coolant Accident

A-25.1,, Ginna Station Event Report

E-23.5, Reactor Coolant Pump No. 1 Seal Leak-offLmr Flow or Off

('-8,-Loss of Reactor Coolant Flow

E-23.1, Malfunction of Il Reactor Coolant Pump Seal

CP-218.2, Calibration of R-18 Detector

M-15, Diesel Generator Maintenance

RF-9.8.1, Part Length Control Rod Drive ShaftUnlatching

RF-l, Refueling Organization

GS-26.1, Unoccupied Vital Area Key Control andAccountability

A-l.l, Locked Radiation Areas

A-5.1, Protective Clothing LockerLocat'P-215.2,

Calibration of R-15 Detector

RSSP-6.1, Integrated Leakage Rate Test Valving Align-ment

RSSP-6.2, Presurization Monitoring of PenetrationFree Volumes During CV ILRT

QC-1402, System and Equipnent Operating Status Control

QCIP-5, Cleanliness Inspection of Components

S-3.3G, CVCS Deborating Demineralizer Bed OperationUsing "B" Deborating Unit

GS-31.1, Door Alarm Assessment and Response Controlled

20

20

20

20

20

20

20

20

20

20

20

20

20

20

20

20

20

20

20

20

346

347

ISI-1.8, Quality Control A Inservice Inspection

ISI-2.6, Quality Control B Inservice Inspection

20

20

,S,y

'r.~

ir

t

pig

'-14-

PCN N 78 Procedure 6 Title Meetin N 78

348

241

244

246

247

234

239

229

395

362

363

ISI-3. 5, High Energy Inservice Inspection

QCIP-1, Quality Control Inspection Procedure SteamGenerator (Primary Side) Preclosure Inspection

QCIP-4, Quality Control Inspection Procedure ReceivingInspection of NG-6 Type Relays

QCIP-9, Quality Control Inspection Procedure PressurizerPreclosure Cleanliness Inspection

QCIP-13, Quality Control Inspection Procedure MaterialReceiving Inspection of Chemicals and Radio-ChemicalLaboratory Supplies

RSSP-13.6, Inservice Inspection Hydro Test of Class "C"Safety Related Piping (Auxiliary Feedwater PumpsDischarge Piping)

RSSP-15.8, Inservice Inspection Hydro Test of Class "B"Safety Related Piping (Charging Pump Suction excludingVCT)

SM 76-16.1, Eddy Current Wiring Conduits

Rl-200, Replacement or Rework of Solenoid Valvesfor CV Purge Exhaust Valve 5879

S-2.5A, Burping the Reactor Goolant Drain Tank (To BeOpened to Atmosphere)

. S-2.5B, Restoring Reactor Coolant Drain Tank to ServiceAfter Maintenance

20

20

20

20

20

20

20

20

21

21

21

364 S-4.2.10, Burping the Pressurizer Relief Tank andReactor Goolant Drain Tank and Isolating from theVent Header

21

361

353

SM 76-17.2, Screen House Intake Heater Cable Tray

SM 76-21.5, Battery Room Air Conditioning —ServiceWater Piping Installation

21

21

-15-

PCN 5 78 Procedure & Title Meetin " 78

383

384

385

386

387

388

389

381

382

399

412

SN 77-1660.23, RCS Overpressure Protection Loop 452Rack R2 Instrumentation Installation and Wiring

SN 77-1660.24, RCS Overpressure Protection Loop 455Rack=W2 Instrumentation Installation and Wiring

B4 77-1660.25, RCS Overpressure Protection Loop 456Rack R2 Instrumentation Installation and Wiring

&1 77-1660.26, RCS Overpressure Protection Loop 409Rack RCS2 Instrumentation Installation and Wiring

SM 77-1660.27, RCS Overpressure Protection Loop 410Rack RCS2 Instrumentation Installation.and Wiring

SM 77-1660. 28, Overpressure Protection Rxlificationof the Relay Racks

SN 77-1660.29, Overpressure Protection Rx3ificationAnnunciator Termination

SN 77 1660 21 g Overpressure Protection Loop 450Rack B2 Instrumentation Installation and Wiring

SM 77-1660.22, RCS Overpressure Protection Loop 451Rack W2 Instrumentation Installation and Wiring

'lCIP-10, Test Instrument Calibration Procedure

CP-625.1, Residual Heat Reaaval Heat Exchanger OutletValve HCV-625 Isolation

21

21

21

21

21

21

21

22

22

410

411

396

355

263

222

PR-6, Protective Relay Calibration and Trip Test 19KVand 115KV Relaying

CP-624.1, Residual Heat Removal Heat Exchanger OutletValve HCV-624 Isolation

RSSP-10.2, Main Steam Safety Valve Test

S1 75-58.8, Modification of the Walkway and Railings, Around the Spent Fuel Pool

A-60.2, Control of Inservice Inspection Status

PR-2, Protective Relay Calibration and Trip Test1A Emergency Diesel

PR-3, Protective Relay Calibration and Trip Test1B Emergency Diesel

22

22

22

22

22

22

-16-


372

374

373

293

294

403

406

413

400

332

345

380

356

354

353

342

349

341

338

340

CP-2019.0, Turbine Driven Au-iliary Feeawater PungDischarge Pressure Loop 2019

CP-2030.0, 1B Wtor Driven Auxiliary Feedwater PumpDischarge Pressure Loop 2030

CP-2029.0, 3A Motor Driven Auxiliary Feedwater PumpDischarge Pressure Loop 2029

M-15.3, Diesel Fuel Oil Transfer Pump Maintenance

M-15.4, Diesel Startup Air Compressor Maintenance

M-40.7, Steam Generator Snubber Maintenance

A-53.2, three anth Lubrication and MaintenanceInspection

A-35, Prime Mover Holding and Markup Requirements

RF-8.1, Step ky Step Fuel Loading and Maps

GS-12.0, Security Guard Actions During a Fire

GS-31.0, Door Alarm System'I


GS-28.0, Search of Personnel, Vehicles and Packages

. PT-5.20, ~ss instrumentation Reactor ProtectionChannel Trip Test (Channel 2)

RSSP-15.7, Inservice Inspection Hydro Test of Class "B"Safety Related Piping (Charging Pumps Discharge Piping)

RSSP-12, Testing of Primary and Secondary ReliefValves on Test Stand

Fire Pump Ceration and System Alignment

SC-1.12A, Inmdiate Call List

HP-4.1, Controlled Area Entry


CP-209, Calibration of Area 8onitors, TA-62Detectors (Rl-R9)

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

22

-17-

PCN 5 78 Procedure & Title Meetin 5 78

303

302

RF-2, Reactor Refueling Outage Operations andActivities

RF-10, Fuel Transfer System Checkout and DemonstrationProcedure

22

22

351

376

277

A-50.11.4, General Employee Fire Training

SM 76-26.4, Installation of 7.5KV Floor MountedConstant Voltage Transformer lB

SN 76-21.7, Battery Room Air Conditioning —Misc.

22

22

22

317

260

RSSP-13.8, Inservice Inspection Hydro Test ofSafety Related Piping (Service Water Piping-

RSSP-13.7, Inservice Inspection Hydro Test ofSafety Related Piping (CVCS Holdup Tank InletGas Stripper Pumps Discharge Piping IncludingRemoval and Cation Ion Exchangers Piping)

Class IICI1

Loop A)

Class "C"Piping,Base

22

22

248

252

290

377

375

378

321

325

318

320

319

QCIP-14, Quality Control Inspection Procedure MaterialReceiving Inspection of Mechanical Measuring Tools

HP-12.1, Usage of Respirators

A-54.6, Health Phsyics Tour

SN 76-26.2, Installation of 1B Inverter and AlternatePower Supplies

SN 76-26.3, Installation of 7.5KVS Floor WuntedConstant Voltage Transformer 1A

SN 76-26.1, Installation of 1A Inverter andAlternate Power Supplies

SM 77-1682.1, Penetration Testing ModificationPenetration 304

SN 76-27.1, Penetration 332 Modification

SN 77-1682.4, Penetration Testing ModificationPenetration 107

SN 77-1682.2, Penetration Testing ReificationPenetration 202


22

22

22

22

22

22

22

22

22

22

22

-18-


394

291

425

426

409

SM 77-1660.2, Overpressurization Mechanical Package

B4 76-01.1, Safeguard Buses DC Control Voltage bhnitor

SN 77-1660. 10, RCS, Overpressurization ProtectionElectrical Conduit and Wiring

RI 77-2.10, DI Water Containment IsolationElectrical Conduit and Wiring

SM 78-2273.1, Armor Plate on the East Wall of theControl Room

22

22

22

22

22

408

398

Rl 77-1836.1, Turbine Building Pressurization andSecurity Wall

B4 77-02.1, DI Water to Containment ModificationMechanical

22

22

359

327

438

447

RSSP-15.9, Inservice Inspection Hydro Test of Class "B"Safety Realted Piping (Service Water Loop B)

SM 78-1048.1, Accumulator Relief Modification

M-52.3, Incore Thimbles Cleaning

A-17, Plant Operations Review Committee OperatingProcedure

24

24

24

420 ISI-3.5, High Energy Inservice Inspection 24

434 6 446 SM 77-1057.1, Relocation of the Chargine Pump Filter Vent 24

421 a 431 BI 77-1660.28, Overpressure Protection Modificationof the Relay Backs

24

433

440

441

417

414

443

M-73.3, Welding on Carbon Steel Piping or Components

S-2.5A, Burping RCVZ (To Be Opened to Atmosphere)

S-2.3B, Burping the Pressurizer Relief Tank (To beOpened to Atmosphere)

S-2.3B, Burping the Pressurizer Relief Tank (To beOpened to Atmosphere)

TCIP-9, Test Instrument Calibration Procedure

S-2.4A, Draining the Pressurizer (RCS Degassed)

24

24

24

24

24

24

k

1

i


418 6 437 S-2.5A, Burping Reactor Coolant Drain Tank 24

432

405

407

404

397

402

459

458

463

462

464

350

M-65.0,. Main Steam Line Weld Repairs (Outside ofContainrent)

SN 78-1875.1, "A" Feedwater Venturi Monorail

SN 78-1480.1, ".A" RCP Ladder and Handrail Installation

SM 77-1474.1, RCP Seal Bypass Modification

SN 75-14, Boric Acid Batch Tank Recirculation Pipingand Supports

SN 78-1485.1, Dillon Cell Storage Frame

SN 77-1660.2, Overpressurization Mechanical Package

SN 77-02.1, Demineralized Water to ContainmentModification Mechanical

RD-6, Gas Decay Tank Releases

M-ll.8B, Reactor Coolant Pump —Seal Injection andService Mechanical

SN 77-1623.1, Charging Pump Mnorails

SC-3.15.16, Fire Protection System Inspections andTests

24

25

25

25

25

25

25

25

358

366

367i

368

369

370

371

255

CP-70.5, Test Gauge Calibration Procedure

. CP-617.0, Component Cooling Water Pumps DischargePressure PIC-617

CP-628.0, RHR Loop Reactor Coolant Test Bypass Flow

CP-2033.0, Service Water Flow From "3A" Vent CoolerFlowmeter FIA-2033

CP-2034.0, Service Water Flow From "lB" Vent CoolerFlowmeter FIA-2034

CP-2035.00 Service Water Flow From "lC" Vent CoolerFlowmeter FIA-2035

CP-2036.0, Service Water Flow Frcm "1D" Vent CoolerFlowmeter FIA-2036

HP-10.7, Flow Calibration of Low Volume Air Samplers

26

26

26

26

26

26

26

-20-


323

448

449

435

454

450

457

456

424

428

429

430

445

427

444

439

202

PR-7.2, Protective Relay Calibration and Trip Test512B Transformer 34KV Relaying

A-19, Change in Written Procedures

RSSP-6.1, Integrated Leakage Rate Test ValvingAlignment

RSSP-6. 0, Containment Integrated Leakage Rate Test

M-37.24A, Main Steam Safety Valve Maintenance Valve No.


SM 77-1660.28, Overpressure Protection Modification ofthe Relay Racks

S-4.1U, Velocity Flush of R-18

A-35, Prime Hover Holding and Markup Requirements

ISI-1.8, Quality Group A Inservice Inspection

ISI-2.6, Quality Group B Inservice Inspection

ISI-3.5, High Energy Inservice Inspection

O-l. 1C, Pre-Critical Technical Specif ications CheckSheet

HP-12.4, Fitting and Testing of Respirators

A-52.4, Control of Limiting Conditions for OperatingEquipment

GS-41. 0, Employee Screening Program

, A-58, Installation of Power, Control or InstrunentationCables at Ginna Station

26

26

26

26

26

26

26

26

26

26

26

26

26

442

360

451

469

505

A-54. 4, Empty Engineer Responsibilities

M-43.15, Installation of Steam Generator Manway Insert

SM 76-28.1, Flange Installation on Main FeedwaterFlow Venturis —Ginna Station Feedwater Line

&1 78-1845.1, Guide Stud Storage Racks

SM 78-2160.1, GSM-7 Pipe Supports

26

26

27

27

-21-

PCN I 78 Procedure & Title Meetin 5 78

470

510

460

455

513

512

508

465

517

474

473

511

476

516

466

518

509

452


SM 76-28.2, Flange Installation on Feedwater FlowVenturis —A Feedwater Line

SM 75-5.50, Auxiliary Feedwater Hanger APW-51 Repair

RF-51, Reactivity Insertion Computation

ISI-2.1.6, Quality Group B Inservice Inspection

ISI-1.1.8, Quality Group A Inservice Inspection

SM 76-26.1, Installation of 1A Inverter and.AlternatePower Supplies

0-2.3.1, Draining the Reactor Coolant System

S-3.2J, Isolation of Reactor Coolant Filter andAssociated Grinnel Diaphragm Valves (249, 250, 253,251, 248A, and 248B)


S-3.2J, Isolation of Reactor Coolant Filter andAssociated Grinnell Diaphragm Valves (249, 250, 253,251, 248A, and 248B)

M-43.1, Steam Generator Manway Cover Rermval SteamGenerator

EN-201, B Steam Generator Secondary Side Peripheral TubeRemoval

RSSP-15.9, Inservice Inspection Hydro Test of Class "B"Safety Related Piping (Service Water Loop B)

SM 75-14, Boric Acid Batch Tank Recirculation Pipingand Supports

SM 77-2.10, DI Water Containment Isolation —ElectricalConduit and Wiring

RF-2E, Draining of Refueling Canal


E-1.2, Zoss of Coolant AccidentGS-1.2, Ginna Station Security Event Report

27

27

27

27

27

27

27

27

27

27

27

27

27

27

27

27

27

27

2727

)g 4

t

'\

?

-22-


548

542

558

559 a 546

521

520

520

552

551

561

554

SM 76-26.2, Installation of 1B Inverter and AlternatePawer Supplies

A-54.3, Open Flame, Welding and Grinding Permit

S-27.209, Isolation of CVCS Relief Valve 209

RSSP-13.8, Inservice Inspection Hydro Test of Class "C"

Safety Related Piping (Service Water Piping —Loop A)P

RSSP-15.8, Inservice Inspection Hydro Test of Class "B"'afetyRelated Piping (Charging Pump Suction Excluding

VCT)

RF-10, Fuel Transfer System Checkout and DemonstrationProcedures

M-11.8.3, Reactor Coolant Pump Seal Inspection andService Mechanical

B4 77-1057.1, Relocation of the Charging Pump FilterVent

RSSP-14.8, ISI Hydro Test of Class "C" Safety RelatedPiping (Service Water Piping — Loop A)

M-38.5; 1B Constant Voltage Transformer Maintenance

RSSP-12, Tiesting of Primary and Secondary Relief Valveson Test Stand


28

28

28

28

28

28

28

28

28

28

28

28

553

562

S-27.209, CVCS Relief Valve 209 Isolation

S-27.1, Volume Control Tank Grinnell Diaphragm ValvesIsolation

28

28

545

550

A-50.6, R.'. Ginna Operator Requalification Program

M-ll.8A, Reactor Coolant Pump 5 Removal from Servicefor Pump Maintenance

28

28

471 S-2.1B, Reactor Coolant Pumps —Isolation for Naintenance 28

522

515

, PZ-2.5, Air Operated Valves, Quarterly Surveillance

A-36, Station Holding Rules

28

28

'k

A

P)

/

-23-


543

519

316

507

472

330

540

538

541

539

532

533

CP-429.7, Pressurizer Pressure Bistable PC-429A

M-15.5, lA Deisel Startup Air Compressor Maintenance

QC-1403, Inspection and Test Status Control


M-15.6, 1B Deisel Fuel Oil Transfer Pump Maintenance

0-6.4, Core Quadrant Power Tilt Calculation

CP-410.0, Reactor Coolant Temperature Gold Leg"410B" Calibration and/or. Maintenance

CP-409, Reactor Coolant Termperature Cold Leg"409B" Calibration and/or Maintenance

CP-410.3, Reactor Coolant Temperature Cold LegBistable TC-410A/B

CP09.3, Reactor Coolant Temperature Cold LegBistable TC-409A/B

CP-455.0, N2 Accumulator Pressure Low Loop 455

CP-455.'1, N2 Accumulator Pressure Lear Zoop 455Transmitter

28

28

28

28

28

28

28

28

28

28

28

28

534

535

536

CP-455.2, N2 Accumulator Pressure Low Loop 455. Bistable Power Supply and Indicator

CP-456.0, N2 Accumulator Pressure Low Xaop 456

CP-456.1, N2 Accumulator Pressure Lcm Eaop 456Transmitter

28

28

28

537

531

526

527

528

CP-456.2, N2 Accumulator Pressure Low Eoop 456Bistable Power Supply and Indicator

CP-452.2, Overpressure Protection Loop 452 PowerSupply and Bistable

CP-451. 0, Overpressure Protection Loop 451

CP-451.1, Overpressure Protection Loop 451 Transmitter

CP-451.2, Overpressure Protection Loop 451 Power Supplyand Bistable

28

28

28

28

28

-24-

PCN N 78 Procedure & Title Meetin N 78

529

530

524

525

514

477

478

479

480

481

482

483

484

485

486

487

488

489

490

CP-452.0, Overpressure Protection Loop 452

CP-452.1, Overpressure Protection Loop 452 Transmitter

CP-.450.1, Overpressure Protection Loop 450 Transmitter

CP-450.2, Overpressure Protection Loop 450 Ewer Supplyand Bistable

CP-450.0, Overpressure Protection Loop 450

QCIP-20, Verification of Accuracy for MechanicalMeasuring Tools


ISX-1.2.1, Quality Group A Inservice Inspection

ISI-1.2. 2, Quality Group A Inservice Inspection




ISI-l.2.6, Quality Group A Inservice Inspection

ISI-1.2.7, Qaulity Group A Inservice Inspection

~ ISI-1.2.8, Quality Group A Inservice Inspection




ISI-1.3.3, Quality Group A Inservice, Inspection


28

28

28.

28

28

28

28

28

28

28

28

28

28

28

28

28

28

28

28

491 ISI-'1.3.5, Quality Group A Inservice Inspection

492 ~ ISI-1.3.6, Quality Group A Inservice Xnspection

28

28

493

494


ISX-1.3. 8, Quality Group A Inservice Inspection

28

28

-25-


495

496

497

498

499

500

501

502

503

504

597

557

565











A-54.6, Health Physics Tour

EM-202, Safety Injection Sequence Timing RelayReplacement

SM 76-01.2, Cable Installation for the DC ControlFuses

SN 77-1660.15, Instrumentation Tie-Ins for RCS

Overpressurization

28

28

28

28

28

28

28

28

28

28

28

29

29

29

544 SN 78-1865.1, Steam Generator "A" Air Mver Installation 29

603

604

S-27.348B, Valve 348B Isolation

EN-201, "B" Steam Generator Secondary Side PeripheralTube Removal

30

30

608 S-3. 1K, 1A Boric Acid Transfer Pump Isolation/RestOration 30

574 SM 77-1682. 2, Penetration Testing lkx3ification-Penetration 202

30

579

598

566

SM 77-1682.3, Penetration Testing Modification—.Penetration 210

RF-51, Reactivity Insertion Computation

PT-2.10.2, RHR System Core Deluge Check Valves 853Aand 853B

30

30

30

-26-

PCN 5 78 Procedure & Title Meetin N 78

564 .

569

N-32.1, KS-25, CG-50 and DB-75 Circuit BreakerMaintenance and Overcurrent Trip Device Test and/orReplacement

SM 75-5.40, Standby Auxiliary Feedwater Rework InsideContainment

30

30

576 M-37.2.1, Inspection and Repair of Hain Steam CheckValves

30

575

572

580

601


A-30.3, Plant Procedure Content and Format Requirements

A-13, Maintenance Record Requirements


30

30

30

30

609 A-30.2, Plant Procedure Classification, Review, Approval 30and Distribution Requirements

584

611

610

SM 78-1873.1, Pressurizer Jib Crane

Rl 77-1660.11, RCS Overpressurization Protection—Electrical Terminations in the Control, Room and in theField

EM-203, Repair of Valve 4738 —Service Water to MotorCoolers

31

31

31

643 ~ S-27.2, Isolation of CVCS Letdown Demineralizers andAssociated Valves

31

642

617

621

613

582

581

605

M-37.46, Reactor Compartment Cooler Service WaterOutlet Valve 4758 Maintenance and Inspection

GS-10.1, Security Guard Action During a LocalRadiation Emergency


RF-2D, Filling the Refueling Canal

CP-950.3, Containment Pressure Transmitter PT-950

CP-949.3, Containment Pressure Transmitter PT-949

M-43. 24.1, Inspection of Steam Generator SecondarySide Upper Internals

31

31

31

31

31

31

31

-27-

PCN I 78 Procedure & Title Meetin I 78

602

600

583

570

560

563

591

PZ-2.7, Service Water System

S-27.887, Safety Injection Relief Valve 887 Isolation

T-17J, Generator Bearing Drain Vapor Extractor—Normal Lineup and Operation

PZ-7, Hydro Test of Reactor Coolant System

PT-22.10, Mechanlical Manifold "C" Leak Rate Test


PZ-23.45, Containment Isolation Va1ve Leak Rate TestingLeakage Test Instrumentation

31

31

31

31

31

31

31

593 PZ-23.51A, Containment Isolation Valve Leak Rate Testing 31"A" Hydrogen Recombiner (Pilot and Hain)

594

595

589

587

622

624

620

590

592

596

567

PZ-23.S1B, Containment Isolation Valve Leak Rate Testing"B" Hydrogen Recombiner (Pilot and Main)

PZ-23.51C, Containment Isolation Valve Leak Rate Testing"A" and "B" Hydrogen Recombiner Oxygen Makeup

~23.23, Containment Isolation Valve Leak Rate TestingSump "A" Discharge

PT-23.22, Containment Isolation Valve Leak Rate TestingRCDZ Discharge

l

A-20, Control Room ItsA-25.1, Ginna Station Event Reports

S-14.1, Radiation Honitoring and Related SystemsDaily Plot Hequirements

PT-23.29, Containment Isolation Valve Leak Rate TestingDemineralized Water

PZ-23.46, Containment Isolation Valve Leak Rate TestingNitrogen to Accumulators

PZ-23A, Containment Isolation Valve Test ConnectionBoundary Control

M-ll.27, Corrtponent Cooling Pump Inspection andMaintenance

31

31

31

31

31

31

31

31

31

31

31

-28-


637

636

658

SN 77-02.2, Hydrostatic Testing and Initial ServiceL'eat Test of the Deraineralized Water to ContainmentModification

SN 77-1682.10, Hydrostatic Testing of Penetration 143Piping Modification

SN 78-1048.1, Accumulator Relief Rx3ification forAccumulator Relief Line

32

32

32

657 SM 77-1682.4, Penetration Testing ModificationPenetration 107

32

659

666

665

668 & 670

650

664

650

663

674

644

653

654

645

SN 77-1832.1, Flame Retardant Cable Coating in theEast Cable Vault

SN 75-47.50, Rework of CVCS Hangers Inside Containment

SM 77-1660.15, Instrumentation Tie-ins for RCSOverpressurization

SN 77-1660. 2, Overpressurization Mechanical Package

EM-194, Repair of CVCS Hanger CH54

N-37.38.1, Crosby Safety and Relief Valve Maintenance

N-48.5, Isolation of Bus 17

RSSP-15.7, Inservice Inspection Hydro Test of Class "B"Safety Related Piping (Charging Pumps Discharge Piping)

SN 77-1057.1, Relocation of the Charging Pump FilterVent

QC-105, Indoctrination and Training ModificationProgram

QC-301, Work Start Authorization

QC-304, Control of Modification Activities by theModification Project

SN 77-1660.100, Pneumatic Testing of the ContainmentDI Water Automatic Isolation Valve 8418

S-27.861, Relief Valve 861 Isolation

S-27.1817, Relief Valve 1817 Isolation

SN 77-02.15, Air Tie-in for the DI Water to Containment

32

32

32

32

32

32

32

32

32

32

32

32

33

33

33

33

-29-

PCN I 78 Procedure & Title Meeting I 78

673

679

678

677

676

683

682

686

685

687

699

634

684

612

700

RF-2, Reactor Refueling Outage Operations and Activities

SM 76-27.1, Penetration 332 Modification


SM 76-27.1, Penetration 332 Modification

Rl 77-1682.1, Penetration Testing ModificationPenetartion 304

RSSP-13.6, Inservice Inspection Hydro Test of Class "C"Safety Related Piping

SM 77-1660.15, Instrumentation Tie-ins for RCSOverpressurization

SM 78-1485.1, Dillon Cell Storage Frame

SN 78-1480.1, A RCP Ladder and Handrail Installation

SN 78-1865.1, Steam Generator "A" Air Mover Installation

M-37.11, Repair and Inspection of Pressurizer PowerOperated Relief Valves 430 and 431C

SN 78-1888.1, Spray Additive Tank Recirculation LineShutoff Valve Installation

SN 76-26.5, Installation of 7.5 KVA Floor Munted. Constant Voltage Transformer Backup Supply for

Instrument Busses A, B, C, and D

PT 32.2, Initial Checkout of the KS OverpressureProtection System

SN 77-1660.24, KS Overpressure Protection Loop 455Rack W2 Instrumentation and Wiring

33

33

33

33

33

34

34

34

34

34

34

34

35

35

35

635

655

S-12.4, RCS Leakage Surveillance Record Instructions 35

RF-2, Reactor Refueling Outage Operations and Activities 35

649

691

690

RF-2E, Draining of Refueling Canal

RF-14.4.1, Relaxing and Removing Reactor Vessel HeadStuds, Stud Hole Plugs and Guide Stud Installation

RF-14.412, Removing Reactor Vessel Guide Studs and StudHole Plugs, Installating and Tensioning Head Studs

35

35

35

-30-


688

706

697

627

647

648

662

675

672


S-SA, Component Cooling Water System Startup andNormal Opeation Valve Alignment

M-47.1, Inspection of Pressurizer Internals

M-44.2, Isolation and Restoration of Motor ControlCenter 1A

CP-924.0, Calibration and/or Maintenance of SafetyInjection Flow Loop "B"

CP-925.0, Calibration and/or Maintenance of SafetyInjection Flaw laop "A"

BSSP-15.7, Inservice Inspection Hydro Test of Class "B"Safety Related Piping (Charging Piping)

S-4.5.9, Letdown Deborating DI (A or B) ResinReplacement

GS-17.0, Accountability of Personnel During EmergencyConditions

35

35

35

35

35

35

35

35

35

660

669

GS-31.0, Door Alarm System 35

RF-2; Reactor Refueling Outage Operations and Activities 35

707

705

704

671

RF-8. 2, Fuel Handling Instruction Pre-Loading andPeriodic Valve Test

0-1.1B, Establishing Containment Integrity

RF-2B, Recpired Valve Line-.Up for Reactor Head Removal

HP-4.3, Work Permit Use

35

35

35

35

628

629,

623

0-2.5, Plant Shutdown from Hot Shutdawn to Cold Shutdown 35When Condenser Steam Dump is Unavailable

0-2.4, Plant Shutdown from Hot Shutdown to Cold Shutdown 35During Blackout

0-2.2, Plant Shutdawn fram Hot Shutdown to Cold Condition 35

696 PT-16, Auxiliary Feedwater System 35

-31-

PCN 5 78 Procedure a Title Meetin I 78

694

695

693

692

703


PT-3, Containment Spray Pumps and NaOH AdditiveSystem

PZ-2.2, Residual Heat Removal System

PT-2.1, Safety Injection System Pumps

PT-2. 4, Cold/Refueling Motor Operated ValveSurveillance

35

35

35

35

651

702

701

698

315

640

RSSP-1.1, Valve Interlock Verification ResidualHeat Removal System

RSSP-3.0, Verification of Emergency StartLogic Auxiliary Feedwater Pumps

PT-2. 5, Air Operated Valves —Quarterly Surveillance

SC-3, Fire Emergency Plan

QC-1003, Control of Inservice Inspection Activities

QC-103, Periodic Review of Quality Control Procedure

35

35

35

35

35

35

638 a 639 QC-201, Ginna Quality Control Organization

.QC-303, Control of System Modification Activities

35

35

652'20

S-3.1N, Isolation of Miscellaneous Valves in theBoric Acid Storage Tank Room

SM 77-1682. 2, Penetration Testing ModificationPenetration 202

36

36

714

710

SM 75-14, Boric Acid Batch Tank Recirculation Pipingand Supports

&I 76-28.2, Flange Installation on Feedwater FlowVenturis A Feedwater Line

36

36

721

711

713

CP-455.0, N2 Accumulator Pressure Low Loop 45S

S-3.2A, Charging and Volume Control Systen Pre-StartupAlignment

P-8, Precautions, Limitations and Setpoints WasteDisposal System

36

36

36

-32-


715 S-13A, RHR System Lineup for Safety Injection 36

709 S-3.1K, lA Boric Acid Transfer Pump Isolation/Restoration 36

723

722

767

EM-155, Safeguard Rack Relays VI and/or CI Replacement

M-81, Safeguard Rack Ventillation and ContainmentIsolation Relays Replacement

A-54.6, Health Physic's Tour

S-2.3B, Burping the Pressurizer Relief Tank with N2(Not to ke Opened the Atmosphere)

36

36

37A

774 M-40.1, Hydraulic Snubber Unit Removal and Reinstallatio 37AProcedure

766'24

725

726

727

728

RF-2, Reactor Refueling Outage Operations and Activities





ISI-2.2. 2, Quality Group B Inservice Inspection

37A

37

37

37

37

37

729

730

ISI-2.2. 3, Quality Group

ISI-2. 2. 4, Quality Group

B Inservice Inspection

B Inservice Inspection

37

37

731

732

733

734

735

736

737

738

739

ISI-2.2.55 Quality Group B Inservice Inspection






ISI.3.22 Quality Group B Inservice Inspection



37

37

37

37

37

37

37

37

37

-33-


740

741

742

743

744

745

746

747

748

749

750

751

680

681

789

771

784

768

712

752

716

791

780





ISI-2.3. 9 Quality Group B Inservice Inspection








S.5.11, "B" Letdown Deborating DI Replacement

S-4.5.10, "A" Letdown Deborating DI Resin Replacement

PT-23A, Containment Isolation Valve Test ConnectionBoundary Control

RF-2, Operations and Activities

T-16A, Turbine Pre-Statup

O-l. 1B, Establishing Containment Integrity

T-41A, Alignment of Auxiliary Feedwater System Priorto Power Operation

O-l. 1B, Establishing Containment Integrity

S-2.5B, Restoring Reactor Coolant Drain Tank to ServiceAfter Maintenance



37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

-34-

PCN -5 78 Procedure & Title Meetin I 78

782

781

ISI-3.1.5, High Energy Inservice Inspection

ISI.1.6, Quality Group B Inservice Inspection

37

37

785 PT-13.1.1, Protomatic Deluge Valve System Testing Systen 37Number 7, 8, 9, 10

787

777

795

794

793

718

778

769

788

770

753

708

779

717

790,

783


ET-23.3, Containment Isolation Valves Leak Bate TestingMakeup Water to Pressurizer Relief Tank Line

FT-32.2, Initial Checkout of the RCS OverpressureProtection System


0-6.2, Main Control Board System Status Verification

M-7.3, Boric Acid Concentrates and Ion Exchanger FilterReplacement

M-48.3, Isolation and Restoration of Bus 115

PC-1.3, Daily Chemistry Analysis Results

HP-11.2, Iodine in Air-Charcoal Cartridge Method


A-52.2, Control of Locked Valve Operation



T-34A, Generator Seal Oil System Startup

M-40.8, Functional Testing of Hydraulic Snubbers

R1-201, "B" Steam Generator Secondary Side PeripheralTube Removal

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

37

786

796

799

RSSP-13.8.1, Hydro Test of Loop A Underground ServiceWater Piping

EM 204 I Seal Welding MOV-700 RHR from Loop A

&1 76-01.1, Safeguard Buses DC Control Voltage Mnitor

38

38

38

-35-


800

830

831

840

841

842

899

RSSP-1.4, Valve Interlock Verification - ReactorCoolant System

PT-32.2, Initial Checkout of the RCS OverpressureProtection System

0-1.2, Plant from Hot Shutdcam to Steady Load

S-29.1, Prealignment of the Reactor Vessel OverpressureProtection System N2 Supply System

S-29.2, Charging the Reactor Vessel OverpressureProtection System Accumulators With N2

0-7, Alignment and Operation of the Reactor VesselOverpressure Protection System

EN-204, Seal Welding MOV-700 RHR "A" Loop

38

38

38

39

39

39

39

883 0-2.5, Plant Shutdown from Hot Shutdown to Cold Shutdown 39When Condenser Steam Dump is Unavailable

792

839

O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown


39

39

838 0-2.2, Plant Shutdown from Hot Shutdown to Gold Condition 39

837

834

836

0-2.3, Plant at Gold Shutdown

Filling and Venting the Reactor Coolant System

Plant Blackout from Hot Shutdown to Cold ShutdownDuring Blackout

39

39

39

835 0-2.5, Plant Shutdown from Hot Shutdown to Cold Shutdown 39When Condenser Steam Dump is Unavailable

888

896

897

898

887

844

A-l.1, Locked Radiation Areas

QC-1404, Test Status Control

O-l.2.2, Critical Rod Position Calculation

0-3.1, Boron Concentration for the Hot Xenon FreeShutdown Margin

ISI-4.1. 5, High Energy Inservice Inspection

&1 75-14, Boric Acid Batch Tank Recirculation Pipingand Supports

39

39

39

39

40

40

-36-

PCN 4 78 Procedure & Title Meetin I 78

845

846

847

SN 76-11.10, No. 12B Auxiliary Transformer — DelugeSystem Tie-in

SM 76-26.1, Installation of 1A Inverter and AlternatePower Supplies

I

SN76-26.2, Installation of 18 Inverter and AlternatePower Supplies

40

40

40

848

849

850

SN 76-26.3, Installation of 7.5KV Floor Mounted Constant 40Voltage Transformer 1A

SN 76-26.4, Installation of 7.5KV Floor Mounted Constant 40Voltage Transformer 1B

SN 76-26.5, Installation of 7.5KV Floor Haunted Constant 40Voltage Transformer Backup Supply for Instrument BusesA, B, C and D

851

852

853

854

855

856

857

858

RI 76-27.1, Penetration 332 Modification

SN 76-28.2, Flange Installation on Feedwater FlowVenturis —A Feedwater Line

RI 77-02.1, Demineralized Water to ContainmentModification —Mechanical

SN 77-02.2, Hydrostatic Testing and Initial ServiceLeak Test of the Demineralized Water to ContainmentModification

SM 77-2.10, DI Water Containment Isolation —ElectricalConduit and Wiring

SN 77-02. 12, Demineralized Water Containment Isolation

SN 77-02.15, Air Tie-in for the DI Water to Containment

SM 77-1057.1, Relocation of the CHarging Pump FilterVent

40

40

40

40

40

40

40

40

860

861

862

SN 77-1660.10, RCS Overpressurization Protection—Electrical Conduit and Wiring

SN 77-1660.11, RCS Overpressurization Protection—Electrical Terminations in the Control Room and in theField

SN 77-1660.15, Instrumentation Tie-Ins for RCS

Overpressurization

40

40

40

-37-

PCN 5 78 Procedure & Title Meetin I 78

863

864

865

866

867

868

869

870

871

872

873

874

875'I

876

877

878

879

887

SN 77-1660.21, BCS Overpressure Protection Loop 450Rack B2 Instrumentation Installation and Wiring

SM 77-1660.22, RCS Overpressure Protection Loop 451Rack W2 Instrumentation Installation and Wiring

SN 77-1660.23, KS Overpressure Protection Lcop 452Rack R2 Instrumentation Installation and Wiring

SN 77-1660.24, BCS Overpressure Protection Loop 455Rack W2 Instrumentation Installation and Wiring

SN 77-1660.25, RCS Overpressure Protection Loop 456Rack R2 Instrumentation Installation and Wiring

SN 77-1660.26, BCS Overpressure Protection Loop 409Rack RCS2 Instrumentation Installation and Wiring

SM 77-1660.27, KS Ovezpressure Protection Loop 410Rack RCS2 Instrumentation Installation and Wiring

SN 77-1660. 28, Overpressure Protection Rx3ificationof .the Belay Backs

SN 77-1660.29, Overpressure Protection Rx3ificationAnnunciator Wiring



B4 77-1682.3, Penetration Testing Rx3ificationPenetration 210

SM 77-1832.1, Flame Retardant Cable Coating in theEast Cable Vault

SN 77-1480.1, "A" RCP Ladder and Handrail Installation

SM 78-1485.1, Dillon Cell Storage Frame

SM 78-1865.1, Steam Generator "A" Air Mover Installation

Rf 78-1890.1, Feedwater Line Drain Valves Before theContainment Check Valves


40

40

40

40

40

40

40

40

40

'40

40

40

40

40

40

40

40

40

-38-

PCN 5 78 Procedure a Title Neetin 5 78

880

890

901

895

902

M-ll.10, Major Inspection of Service Water Pump

A-52.2,'ontrol of Locked Valve Operation

N-40.3, Inspection and Maintenance of Spring Hangers

PZ-2.2, Residual Heat Removal System

EK-203, Repair of Valve 4738, Service Water to MtorCoolers

40

40

40

40

40

900

884

882

843

885

889

893

904

903

M-40.3, Inspection and Naintenance of Spring Hangers


S-3.1N Isolation of Miscellaneous Valves in Boric AcidStorage Tank Boom


M-ll.15, RHR Pumps Inspection/Maintenance

S.5.2, Waste Condensate Polishing Demineralizer ResinReplacement

Ri 75-34.23, Pipe Restraints and Jet Shields Rework forSteam Generator Blowdown Lines


0-6.4.1, Reference ~ilibrium Indicated Axial FluxDifference Determination

40

40

40

40

40

40

40

40

40

905

798

797

891

SN 77-1660.100, Pneumatic Testing of the KSOverpressure Protection System

PT-23, Containment Isolation Valve Leak Rate Testing

A-48, Test Tag Control Program

A-.7, Procedures for Handling Illness or Injuriesat Ginna Station

40

40

40

40

894

892

940

M-67.8, Star Corporation Heat Detector System

QC-1701, Qaulity Assurance Records

M-ll.34.1, Fan Bearing Reaaval and Replacement

40

40

41


989

938

937

953

967

SM 75-50.30, Rework of Jet Shielding for Main SteamBypass Piping and Valves

ET-13.1.5, Flood Valve System Testing —SystemNumbers 3, 4, 5, 6


S-29.1, Prealignment of the Reactor Vessel OverpressureProtection System N2 Supply System

SM 75-34.23, Pipe Restraining and Jet Shields Reworkfor Steam Generator Blowdown Lines

42

43

43

43

43

906 M-ll.8D, Reactor Coolant Pump iWjor Inspection andService — Instrument and Control

43

941

801

802

803

804

805

806

807

808

809

810

811

812

813

814

815

816




ISI-4.1.8, Qaulity Group A Inservice Inspection



ISI-4.2. 2, Quality Gruop A Inservice Inspection


ISI.2.4, Quality Group A Inservice Inspection

ISI.2.5, Quality Group A Inservice Xnspection

ISI.2.6, Quality Group A Inservice Inspection

ISI.2.7, Quality Group A Inserviee Inspection


ISX-.4.2. 9, Quality Group A Inservice Inspection


ISX-4.3. 2, Quality Group A Inservice Inspection


43

43

43

43

43

43

43

43

43

43

43

43

43

43

-40-


817

818

819

820

821

822

823

824

825

826

827

828

829

947

956



ISI-4.3.6, Quality Griup A Inservice Inspection











PR-5, Relay Calibration and Trip Test 4160 VoltAuxiliaries Circuit

0-1.2.1, 1/M Curves

43

43

43

43

43

43

43

43

43

43

43

43

43

43

43

961

881

CP-70. 5, Test Gauge Calibration Procedure


43

43

954 A-30.3, Plant Procedure Content and Format Requirements 43

960

959

958

957

948


A-l.3, Smearing Procedure

S-4.4.1, Spent Resin Package Site Receipt and Shipment

RD, Gas Decay Tank Release

PT-2.1, Safety Injection System Pumps

43

43

43

43

949 PZ-23.5A, Containment Isolation Valve Leak Rate Testing 43Containment Sump Recirculation to "A" RHR Pump

-41-

PCN 5 78 'Procedure a Title Meetin 0 78

950 PT-23.5B, Contain7ent Isolation Valve Leak Rate Testing 43Containment Sump Recirculation to "B" RHR Pump

324,

939

993

944

946

945

SC-3.12, Plan for Recovery from Fire

M-67. 3, Flood Valve System Maintenance —SystemNumbers 3, 4, 5, 6

O-l.2. 2, Critical Rod Position Calculation

GS-26.1, Unoccupied Vital Area Key Control andAccountability

GS-10.0, Security Personnel Actions During a RadiationEmergency

GS-17.0, Accountability of Personnel During EmergencyCondition

43

43

43

43

43

43

943 GS-30.0, threatening Phone Call or Bomb Threat Procedure 43

993

1024

1023

907

908

909

910

911

912

913

914

915

916

PT-34.6, At Power Physics Testing

CP-502.1, Calibration of 1A Emergency Diesel KilowattMeters

CP-502.2, Calibration of lB Emergency Diesel KilowattMeters

ISI-3.1. 5A, Quality Group C Inservice Inspection

ISI-3.1. 6, Quality Group C Inservice Inspection

ISI-3.1.7, Quality Group C Inservice Inspection


ISI-3.1. 9 Quality Group C Inservice Inspection



ISI-3.2.3, Quality Group C. Inservice Inspection



44

44

44

45

45

45

45

45

45

45

44

-42-


917

918

919

920

921

922

923

924

925

926

927

928

929

930

931

932

933

934

935

1027

1030

1021

1019

997

1001


XSI-3.2.7, Quality Group C Inservice Inspection

ISX-3.2.8, Quality Group C Inservice Inspection

ISI-3.2.9, Quality Group C Xnservice Inspection
















0-1.3, Reactor Startup for Training

0-1.2, Plant from Hot Shutdown to Steady Load

PZ-16, Auxiliary Feedwater System


SM 75-34.23, Pipe Restraints and Jet Shields Rework forSteam Generator Blowdown Lines

PZ-6.2, NIS Intermediate Range Channels Channel No.

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

45

-43-


1013

1004

951

952

M-37.38.1, Crosby Safety and Relief Valve Maintenance

M-73.3, Welding on Carbon Steel Piping and Components

S-27.5.3, RCS Loop Sample Valves Isolation

S-27.5.2, Pressurizer Lie@id Space Sample IsolationValves

45

45

45

968

943

974

969

970

971

972

859

1034

1033

1026

E-39.0, Fire at Facility

E-39.1, Containment Vessel Fire

E-39. 2, Relay/Computer Room Fire

E-39.3, Grinnell Deluge System Fire

E-39.4, Smoke Detector Area Fire

E-39. 5, Sprinkler System Fire

E-39.6, Auxiliary Building/Controlled Area Fire


SM 78-1873.1, Pressurizer Jib Crane

SM 78-1888.1, Spray Additive Recirculation Line ShutoffValve Installation

SM 77-02.11, Electric Terminations at Valve 8418 andin Control Room for DI Water to Containment

45

45

45

45

45

45

45

45

45

45

45

1000

999

0-2.4, Plant Shutdown from Hot Shutdwon to Cold Shutdown 45During Blackout

0-2.2, Plant Shutdown from Hot Shutdown to Gold Condition 4S

1015 ET-6.3.3, Power Range Nuclear Instrumentation SystemChannel 43

45

1014

1016

1017

PZ-6.3.4, Power Range Nuclear Instrumentation SystemChannel 44

PZ-6.3.2, Power Range Nuclear Instrumentation SystemChannel 42

PT-6.3.1, Power Range Nuclear Instrumentation SystemChannel 41

45

45

45

-44-


1008

1007

942

1006

1010

1009

1002

1005

PZ-6.1, Source Range NIS

ET.2, NIS Intermediate Range

A-1.2, Air Sampling Procedure

CP-128.3, Charging Line Flow Transmitter FT-128 andLocal Indicator FI-128A

A-2.6, Incore Flux Map Data. Reduction and Review

S-12.4, RCS Leakage Surveillance Record Instructions


CP-128.0, Calibration and/or Maintenance of ChangingLine Flow Channel "128"

45

45

45

45

45

45

45

1012

1020

309

1052

1092

1036

1059

CP-628, RHR Loop Reactor Coolant Test Bypass Flow

SM 75-58.8, Modification of Walkway and RailingsAround the Spent Fuel Pool

SC-3.14.2, Fire Department and Fire Brigade Drill0-6.9, Opeating Limits for Ginna Station Transmission

&I 76-16.1, Eddy Current Wiring Conduits

0-2.1, Normal Shutdown to Hot Shutdown

PZ. 4, 'Excore/Incore Recalibration

45

45

46

46

46

46

1056 SM 77-1498.1, Zaw Power Steam Generator Feedwater ~s 46Control Reification

1055

1053

1044

Rl 78-1048.1, Accumulator Relief Rx3ification forAccumulator Relief Line

SM 76-01.2, Cable Installation for the DC ControlFuse Honitor System

SM 75-41.31, Condensate Polishing System Control BoardOperational Check

46

46

46

1089 a 1043 SM 75-5.40, Standby Auxiliary Feedwater Rework InsideContainment

46

1087 SM 75-34.23, Pipe Restraints and Jet Shields Reworkfor Steam Generator Blowdown Lines

46

PCN I 78

-45-


1083

1042 & 1088 SM 75-5.50 Aux'Aux'.iary Feedwater Hanger AEW-51 Repair

SM 75-58.8, Modification of the Walkwo e ay and Railings

1084 . SM 75-50.30, Rework of Jet Shield'nSM ze mg on Main Steam 46

1085 SM 75-48.30, Rework of the Auxilia'y Feedwater Crossover 46

1086

1050

1049

1041

1040

1028

1048

1054

990

1058

1057

1119

1123

1108

1107

1097

1099

SM 75-47.30 Re, Rework of CVCS Hangers Inside Containment

M-38.3 , 1B Inveiter Maintenance o Reor pair

M 38 ' ia, L~ Inverter Maintenance o Reor paar

M-38.4, 1A Constant Voltaor Repair

ge Transformer Maintenance

M-38.5, 1B Constant Voltaor Repair

ge Transformer Maintenance

0-1.1C, Pre-Critical TechnicalSheet

x ~~cification Check

9 -2701, Quality Assurance Records

0-7 Al 'Alignment and Operation of theOverpressure Prot t 'cion System

e Reactor Vessel

, GS-26.1, Unocc iedup'ital Area Key Control andccountability

T-26, 125 VoI lt DC and Station Battery System

PT-17.3Source

7.3, RMS Channel Response to Po tabr le Radiation

M-11.8K, Reactor Coolant Pump Mototor Minor Inspection

S-17B, Addition of 50% NaOHaOH to the Spray additive Tank

TICP-.l , Test Instrument Calibration Procedure

TICP-2, Test Instrument Calibration Procedure

PT-13.1.9, Halon System Testing and'or(Resetting) Comput Roommpu er Room and Relay Room

PT-13.l. 3 Deluge Valve System Testing Numbe rs 1, 2, ll

46

46

46

46

46

46

46

46

48'8

48

48

48

48


1098

1100

PZ-13.1.7, Alarm Valve System Testing System Numbers12, 13 Warehouse

PZ-13.l.l, Protomatic Deluge Valve System Testing System 48Numbers 7, 8, 9, 10

1122

1121

1156

1155

1117

1116

1115

1114

1110

1113

1112

1101

1102

1109

1118

1126

1120

955

1011

963

M-43.21, Steam Generator Final Cleanup and Inspection





CP-44.1, General Defeat Procedure for N-44


CP-43.1, General Defeat Procedure for N-43


CP-41.1, .General Defeat Procedure for N-41

CP-42.2, Reinstate Power Range Channel 42

CP-42.1, General Defeat Procedure for N-42,

0-5.1, Zoad Reductions

0-5. 2, Zoad Increases

0-6.7, Weekly Alarm Status Check

0-2.4, Plant Shutdown from Hot Shutdown to ColdShutdown During Blackout

HP-5.1, Area Radiation Surveys

SM 78-2160.1, GSM 7 Pipe Supports

A-50.12, Emergency Plan Training Program

ISI-6.0, Inservice Leakage Inspection of QualityGroup C Systems

ISI-5, Eddy Current Testing of Series 44 Steam GeneratorTubes

48

48

48

48

48

48

48

48

48

48

48

48

48

48

48

48

48

48

49

49


1210

1211

1212

1213

1214

1215

1216

1217

1218

1046

1047

1160

1164

1230

1223

1224

1222




ISI-1.3.1, Quality Group A Inseryice Inspection






PZ-23.14, Containment Isolation Valve Leak RateTesting Containment Air Sample Inlet

PT-23.15, Containment Isolation Valve Leak RateTesting Containment Air Sample Outlet

A-53. 0, Preventative Maintenance Program

A-53.2, three bhnth Lubrication and MaintenanceInspection

SM 76-21.7, Battery Room Air Conditioning — Misc.

SM 76-21.4, Battery Rocm Air Conditioning —AirConditioner Discharge Duct South End of Battery Room

PT-13.1.1, Protomatic Deluge Valve System TestingSystem Numbers 7, 8, 9, 10

SM 76-21.6, Battery Rocm Air Conditioning —Air SupplyDuct to the Air Conditioner

49

49

49

49

49

49

49

49

49

49

49

49

49

49

49

49

1221

1162

1163

SM 76-21. 5, Battery Bcxm Air Conditioning —ServiceWater Piping Installation

SC-3, Fire Emergency Plan

A-50.2, R. E. Ginna Health Physics Orientation Program

49

49

49

-48-


1161

1121

1165

964

1153

1151

SM 75.24, MSZ Jet, Shielding Installation Rework


ET-l, Rod Control System

M-43.8 Eddy Current Testing of Series 44 SteamGenerator Tubes

M-64.1, Periodic Surveillance and Minor Maintenanceof Limitorque Rotor Operated Safeguard Valves

M-37.53, RHR Core Deluge Valve 852A, and 852B Isolationand Packing

49

49

49

49

49

49

1152 M-37.55, Spray Additive Tank Discharge Valves HCV-836A/B 49Inspection and Maintenance

1150

1149

1148

M-37.51, Component Cooling Water Surge Tank Local VentValve RCV-017 Repair and Inspection

M-37.50, MOV-721 RHR to "B" Zoop Maintenance andInspection

M-37.49, Level Control Valve from "B" RCS Loop LCV-427Maintenance and Inspection

49

49

49

1147 M-37.48, Component Cooling From RC Pumps MOV-759 and/or 49MVT-759B Isolation and Maintenance

1146 M-37.47, RHR Pump Suction MOV-851A or MOV-851BMaintenance and Inspection

49

1145

1144

M-37.42, MOV-813 and/or MOV-814 Isolation and Maintenance 49

M-37.40, Maintneance cn Wtor Driven Auxiliary Feedwater 49Pumps Discharge Valves —MCV-.4007 or MOV-4008

1154

1143

1142

1141

M-64.2, Limitorque Valve Operator Maintenance andInspection

M-37.36.4, Nuclear Sample System Air OperatedValve Maintenance

M-37.35, Valves 3504 and 3505; Main Steamto Turbine Driven Auxiliary Feed PumpMaintenance

M-37.19, Removal of Limitorque Motorsand/or Repacking of Gate Valves 860,A,B.C,GD

49

49

49

49

PCN 4 78 Procedure & Title

1140

1139

1138

1137

1136

M-37.16J, Inspection and Maintenanceof the Rotor Drive Auxiliary Feed PumpRecirculation Control Valve

N-37.15.1, Inspection and Maintenance of48" Butterfly Valve, Model R-lA8 ValveOperator

M-37.15, Replacing or adjusting Rubber SeatSeat in Purge Supply and Exhaust Valves

N-37.10, Grinnell Diaphragm Valves, Air-Operated, Maintenance

M-37.3, Maintenance on Copes-VulcanDiaphragm Operated Control Valves forAOV

49

49

49

49

49

1131

1129

1128

1127

1134

1132

1135

1133

1130

None

1242

, 1288

M-ll.10, Major Inspection of Service WaterPump

M-ll.14, Inspection and Maintenance ofIngersol Rand Pumps

N-37.0, Repacking of Air Mtor OperatedValves

M-11.15, RHR Pumps Inspection/Maintenance

M-11.5B, Major Mechanical Inspection of theAuxiliary Feed Pumps for Pump

N-ll.5K, Turbine Driven Auxiliary FeedwaterPump Major or Mechanical Inspection

M-11.5C, Minor Mechanical Inspection of theAuxiliary Feed imps for PumpN-11.5E, Pipefitters Inspectxon of NctorDriven Auxiliary Feed Pump for Pump

M-ll.12.1, Safety Injection Pump, MechanicalInaction,A-54.6, Health Physics 'Ibur —week of 6/12/78

ET-16, Auxilairy Feedwater System

S-4.4, Spent Resin Removal to ShippingCasks

49

49

49

49

49

49

49

49

50

50

-50-


1272

1273

1266

1265

1231

1232

M-43.6.1, Installation of "A" Steam GeneratorRing Nozzle Cover In Preparation for ExplosiveTube Plugging

M-43.13.1, Steam Generator Ring Nozzle CoverRemoval After Explosive Tube Plugging

EM-156, Removal of Reactor Trip Itic Relay,RT-3

M-70.1, Steam Generator Level Deviation BistableSetpoint Change

PZ-15, Containment Purge Supply and ExhaustDamper Closure Time

ET-18.1, lA Instrument Air Compressor CapacityCheck

50

50

50

50

50

50

1233

1234

1235

1236

1237

ET-18.2, 1B Instrument Air Compressor AirCapacity Check

PT-18.3, 1C Instrument Air Compressor AirCapacity Check

ET-22, Containment Penetration Leak Rate Testing

PZ 22.22, Fuel Transfer Flange Leak Rate Test

RSSP-2.6, Emergency Diesel Start and Breaker.Closure Time

50

50

50

50

50

1239

1240

1241

1271

1274

1275

1276

RSSP-7.0, Control Rod Drop Test

RSSP-8.0, RTD Cross Calibration Check

PR-5, Relay Calibration and Trip Test 4160Volt Auxiliaries

M-43.31, Hand Hold Gasket Seating SurfaceRepair

M3.29, Steam Generator Inner SleeveRemoval and/or Split Ring Assembly Removal

M-3.2, Reactor Cavity Cleanup and Decontami-nation

M-54.2, Condenser Water Box Leak Testing withFreon

50

50

50

50

50

50

50

-51-

PCN I 78 Procedure & Title Meeting I 78

1277 M-43.27, Steam Generator Secondary SideHandhole Cover Removal

50

1278 M-43.28, Steam Generator SEcondary SideManway Cover Removal

50

1270 M-18.1, Drum Preparation for Waste EvaporatorBottoms

50

1281

1207

M-43. 26, Installation of Steam GeneratorSecondary Manway Cover

S-3.3D, CVCS Cation Demineralizer Bed Opera-tions Using "A" Dekorating D. I. Unit

50

50

1206

1205

S-3.3F, Reactor Coolant System pH Control

S-3.4I, Recirculation of Monitor Tank fornArs or nBss Moni

50

50

1204 S-3.4K, Releasing Monitor Tank to DischargeCanal

50

1203 S-3.4M, b$onitor Tank Recirculation throughEvaporator D. I.

50

1202 S-3.4N, Calculations for Boron RecycleProcess Using 2 HVZ's

50

1201

1200

S-3.4P, Transferring Concentrates fromBoric Acid Evaporator Feed Tank to WasteEvaporator Feed Tank for Drumming

S-3.4R, Transfer of any CVCS HUZ to AnotherCVCS HVZ

50

50

1198

1197

S-3.4T, Regeneration of the Boric AcidEvaporator "B" Condensate D. I.S-3.5, Deborating Demineralizer "B" Regen-eration

50

50

1196 S-4.1F, Waste Condensate Polisher Recircu-lation

50

1195 S-4.1L, Reverse Osmosis Unit Startup andShutdown

50

1194 S-4.1N, Transfer Waste Holdup Tank to "A"Monitor Tank

50

-52-


1193 S-4.1R, Transfer of Chemical Drain Tank toReverse Csmosis Feed Tank

50

1192

1191

1190

1189

1188

1187

1186

1185

S-4.1S, Alternating Waste Evaporator Cart-ridge Demineralizers

S-.4.1T, Alternating Waste Evaporator Conden-sate Polishing Demineralizers

S-4.1U, Velocity Flush of R-18

S-4.1Y, Laundry Tank Release Using ChemicalDrain Pump

S-4.5. 2, Waste Condensate Polishing Deminer-alizer Resin Replacement

S-4.5.4, Boron Recycle Base Reneval D. I.Resin Replacement

S-4.5.5, Boron Recycle Cation D. I., ResinReplacement

S-4.5.6, Spent Fuel Pit, D. I. Resin Replace-ment

50

50

50

50

50

50

50

50

1184

1183

1182

1181

,1199

1180

1179

1178

1177

S-4.5.7, Letdown Mixed Bed D. I. Resin Replace-ment

S-4.5.8, Eetdown Cation D. I. Resin Re-placement

S-5, Nuclear Sample Room Sampling System

S-8, Component Cooling system

S-3.4S, Regeneration of the Boric AcidEvaporator "A" Condensate D. I.S-9J, Blending to EST

S-9K, Transferring Water From Monitor Tankto Spent Fuel Pit

S-9L, Batching Boric Acid and Transferring,to Spent Fuel Pit

S-9M, Adding Reactor Makeup Water to SpentFuel Pit

50

50

50

50

'050

50

50

-53-

PCN I 78 Procedure 6 Title Meetin 5 78

1176

1175

1209

1208

1174

1173

1172

1171

1170

1169

S-10.1, Part Length Rod Control

S-14.2, Determination of the Percent ofTech. Spec. Limits for Radioactive Release

S-3.2C,. Placing and Removing from Service"B" Hot Leg Charing Valve 392A

S-3.3C, H2 or 02 Removal from Primary Systemby Bumping VCT with N2

S-16.3, Vent N2 from the "A" Accumulator

S-16.4, Vent N2 from the "B" Accumulator

S-16.9, Charging of the "A" Accumulator withNitrogen

S-16.10, Charging of the "B" Accumulator withNitrogen

S-16.13, Water Makeup to the Accumulator

S-23.5, Post Accident Charcoal Filter Opera-tion

50

50

50

50

50

50

50

50

50

50

1168

1167

1267

,1260

1259

1258

1257

1018

'1229

1247

1226

S-25. 5, Steam Generator Radioactive Release

S-26.4, Computor Rod Postion Alarm Program

M-57.1, Power Range NIS Detector Replacement

E-29.1, Zass of Normal Feedwater (Not Recover-erable)

E-26.4, Mrbine Trip Without Reactor Trip

E-16.2, High Iodine 1313 in the Plant Vent .

E-13.1, Power Range NIS Malfunction (PR 41,42, 43, 44)


HP-6.2, Posting of Contaminated and AirkarneAreas


PT-2.3.1, Post Accident Charcoal FilterDmtpers

50

50

50

50

50

50

50

50

50

50

50

-54-

PCN N 78 Procedure 6 Title Meeting N 78

1269

1227

1264

1262

1268

1263

1286

1246

1245

1244

1248

1249

1250


HP-1.3, External Exposure Records

M-18, Acid Cleaning of Waste Evaporator


T-7E, Water Treatment-Carbon Filter Backwash

S-4.1D, Drumming Waste Evaporator Bottoms

A.C.-1701, Quality Assurance Records

0-1.2, Plant From Hot Shutdown to Steady Load

0-1.3, Reactor Startup for Training

PZ-34.0, Startup Physics Test Program

PZ-23.16A, Containment Isolation Valve LeakRate Testing "A" Steam Generator Blowdown

PZ-23.16B, Containment Isolation Valve LeakRate Testing "B" Steam Generator Blowdown

PZ 23.17A, Containment Isolation Valve LeakRate Testing Containment Pressure SensingTransmitter PT-945 and PT-946

50

50

50

50

50

50

50

50

50

52

52

52

1251 PZ-23.17B, Containment Isolation Valve LeakRate Testing Containment Pressure SensingTransmitter PT-947 and PT-948

52

1252 ET-23.17C, Containment Isolation Valve LeakRate Testing Containment Pressure SensingTransmitter PT-949 and PT-950

52

1255

1256

1253

1254

PZ-23.18B, Containment Isolation Valve LeakRate Testing "B" Containment Spray Header

ET-23.19, Containment Isolation Valve LeakRate Testing Safety Injection System

ET-23.20, Containment Isolation Valve LeakRate Testing R., C. D. T. Gas Header

PZ-23.21, Containment Isolation Valve LeakRate Testing R. C. D. T. Gas Analyzer

52

52

52

52

-55-


719

1293

1287

1283

1279

1285

1317

1318

1328

1315

1329

1295 .

1348

1347

1343

1032

1323

1322

1342

1341

M-37.57, Containment D. I. Check Valve 8419Mainteannce

&~~9.1, Manipulator Crane

RF-2A, Requirements for Reactor Head Removal

RF-8.1, Step-by-Step Fuel Loading and Maps

M-15.1, "A" or "B" Diesel Generator RemovalFrom Service

M-15.3.1, 1A Diesel Generator Solenoid Valves5907 and/or 5907A Maintenance

HP.3, Air Ejector Gas Sampling

HP-9.2, Primary to Secondary Leakage Detectionand Measurement

PZ-3, Containment Spray Pumps NaOHAdditive System

M-18, Acid Cleaning of Waste Evaporator

0-6.9, Operating Limits for Ginna StationTransmission

S-9M, Adding Reactor Makeup Water to SpentFuel Pit

. W-1701, Quality Assurance Records


= A 37 1 I System Modification Requirements

A-50.9.2, Non-Licensed Staff RetrainingProgram

GS-31.0, Ecor Alarm System

GS-28.0, Inspection of Personnel Vehicles andPackages

A-37.0, Conduct of Operations for Safety-Related Evaluations as related to Facilityor Rxiifications, Special Tests, Experiments

A-50.2, R. E. Ginna Health Physics OrientationProgram,

52

52

52

52

52

52

52

52

52

52

52

53

53

53

53

53

53

53

53


1340 PC-18.3, Determination of Chloride kp Speci-fic Ion Electrode

53

1330 '-40.1, Hydraulic Snubber Reaaval and Rein-.stallation Procedure

53

1324

1326

1325

1354

1355

1356

1357

1358

1359

1360

1361

1362

1363

1364

1366

1368

1367

XT-34.1, Initial Criticality and ARO BoronConcentration

M-40.8, Functional Testing of HydraulicSnubbers

RSSP-12, Testing of Primary and SecondaryRelief Valves in Test Stand

AR-AA-'2, AVT Water Treatment Panel Trouble

AR-AA-4, Standby Auxiliary Feedwater HVACTrouble

AR-AA-5, Standby Auxiliary Feedwater PumpCAR C or D Trip

AR-AA-6, KS Overpressurization Army'InhibitLoop "A" Select

AR-AA-7, RCS Overpressurization Arrq/InhibitLoop "B" Select

AR-AA-9, Condensate Booster Pump Pressuriza-tion Trip

AR-AA-10, Condensate Booster Pump Trip

AR-AA-14, N2 Accumulator, V-801A Tow Pressure

AR-AA-15, N Accumulator, V-801B Imr Pressure

AR-AA-22, KS Overpressurization ProtectionHigh Pressure Train "A"

AR-AA-23, RCS Overpressurization ProtectionHigh Pressure Train "B"

AR-AA-25, Condensate System Low Pressure

AR-AA-29, Condensate +stem Low Pressure Drop

AR-AA-30, Condensate Booster Pump LowSuction Pressure

53

53

53

55

55

55

55

55

55

55

55

55

55

55

55

-57-


1365

1332

1333

1331

1385

1386

. 1387

1388

1389

1390

1391

1392

1336

1337

1338

1339

1370

AR-AA-31, RCS Overpressurization ProtectionHigh Pressure Train "C"

NC-1, A List of Sample Chemical Parametersand Sampling Schedule

HP-7.3, Calibration of Alpha Survey Instruments

GS-41, Photography at Ginna Station

SC-3.17.3, Fire Brigade Drill Records

SC-3.17.1, Planning, Conduct and Evaluationof a Fire Emergency DrillSC-1.10, Planning Conduct and Evaluationof a Radiation Emergency DrillA-50.11.4, General Employee Fire Txaining

A-S0.11.2, Fire Department Familiarization

A-50.11.1, Fire Brigade Training

A-50.11.0, Fire Fighting Organization andTraining Program

A-50.7, Emergency Coordinator Training Program

PZ-6.3.1, Power Range Nuclear InstrumentationSystem, Channel 41

PZ-6.3.2, "System, Channel 42

PT-6.3.3, Power Range Nuclear InstrumentationSystem, Channel 43

PT-6.3.4, Power Range Nuclear InstrumentationSystem, Channel 44

M-ll.8C, Reactor Coolant Pump Major Inspec-tion in Service Electrical

55

55

55

55

55

55

55

55

55

55

55

55

55

1371 M-ll.8B, Reactor Coolant Pump Seal Inspec-tion and Service Mechanical

55

1383 A-30.2, Plant Procedure Classification, Review,Approval and Distribution Requirements

55

-58-


1372

1377

1345

1335

1369

1373

1374

1376

1378

1384

1393

1382

1381.


AR-F-2, Alarm Response Procedure

PL'-2.1, Safety Injection System Pumps


A-60.3, Calibration Surveillance Program forInstrumentation ~ignent or Safety-RelatedComponents

M-15.1, "A" or "B" Diesel Generator RemovalFrom Service

M-15.3.2, Diesel Generator, FLSI, Fuel OilLevel Switch High Maintenance

M-18, Acid Cleaning of Waste Evaporatork

S-4.1C, Liquid Waste Process Operation andShutdown

S-7B, Reactor Coolant Low Pressure Purification


PT-2.10, Check Valve Exercising Test Requirements-Cold/Refueling Shutdown

RSSP-l. 5, Valve Interlock Verification FeedwaterIsolation

55

55

55

55

55

55

55

55

55

55

55

55

1349

13SO

1351

1352

1353

1402

1442

WC-7, Chloride Determination

WC-6, Potentiometric Determination of Boron

WC-S, Ammonia and Organic Nitrogen Determination

WC-3, Anal inity Determination

WC-4, Amelia Determination ky Direct Nessleriza-tion

EM-205, Turbine Runback Relay in RPI SystemReplacement

EM-186, CR-9 Relay in RPI System Replacement

56

56

56

56

56

56

-59-


1417 M-44.10, Isolation of MCC 1K and Restoring toService

1418

1419

1420

M-31, Stator Replacement for Part-Length ControlRod Drive System

M-37.18E, ~ction and Repair of AuxiliaryBuilding Sump Pump Discharge Check Valves

M-37.18F, Inspection and Repair of 1AAuxiliary Building Sump Tank Pump DischargeCheck Valve

56

56

56

1421

1422

1423

1424

M-37. 43, Accumulator Drain Valves 844A and844B Inspection and Repair

M-37.27.1, Testing and Replacement of 1BSteam Generator Blowdawn Sample IsolationValves CV-77 *5736) or Manual Valve 5734

M-ll.26.1, Heater Drain Pump Mechanical SealInspection and Maintenance

M-11.26, Heater Drain Pump Inspection andMaintenance

56

56

56

1425

1426

1427

1428

M-1125, Main Feedwater Pump ~ed IncreaseInspection and Maintenance

M-11. 23, worthington Double-Helical RotaryPump Inspection and Maintenance

M-ll.24, Main Feed Pump Inspection andMaintenance

M-ll.28, Rotary Air Samples Inspection andMaintenance

56

56

56

56

1429

1430

1431

1432

1433

M-S3.1, Containment Air Loc3cs Door GasketReplacement

M-53.2, Containment Air Lock equalizing ValveCleaning and Inspection

M-37.16M, Isolation of V-356 for Maintenance

M-37.18D, Check Valve 1713 Isolation N2 toR.C.D.T.

M-37.20, Inspection and Repair of Main SteamIsolation Valves

56

56

56

56


1434

1435

1436

1397

1143

1444

1445

1446

1447

1443

1403

1405

1406

1407

1408 .

1409

M-37.18C, Inspection of Rockewell Check Valvesin the Waste Gas and Nitrcxjen System

M-37.2.1, Repacking Pressurizer Power ReliefGuard Valves 515 and 516

M-37.44, Immediate Boration Valve MDV-350MaintenanceA-50.9.1, Ginna Station Engineers (Cadet,Assistant Station and Station) TrainingProgram

A-52.2, Control of Locked Valve Operation

KT-5.10, Process Instrumentation ReactorProtection Channel Trip Test (Channel 1)

FZ-5. 20, Process Instrumentation ReactorProtection Channel Trip Test (Channel 2)

PZ-5. 30, Process Instrumentation ReactorProtection Channel Trip Test (Channel 3)

PT-5.40, Process Instrumentation ReactorProtection Channel Trip Test (Channel 4)

KT-16, Auxiliary Feedwater System

KT-6.3. 2, Power Range Nuclear InstrumentationSystem, Channel 42

PZ-23.18A, Containment Isolation Valve LeakRate Testing "A" Containment Spray Header

PZ-23.24, Containment Isolation ValveLeak Rate Testing Reactor Support Goolers(Inlet and Outlet)

PZ-23.26, Containment Isolation Valve LeakRate Testing Auxiliary Coolant System to "A"Reactor Coolant Pump

PT-23.27, Containment Isolation Va1ve Leak.Rate Testing Auxiliary Coolant System to "B"Reactor Coolant Pump

PZ-23.28, Containment Isolation Valve LeakRate Testing Auxiliary Coolant System Frcm "A"Reactor Coolant Pump

56

56

56

56

56

56

'56

56

56

56

58

58

58

58

58

-61-


1410

1411

1455

1450

1449

1451

PZ-23.29, Containment Isolation Valve LeakRate Testing Auxiliary Coolant System From"B" Reactor Coolant Pump

PT-23.30, Containment Isolation Valve LeakRate Testing Auxiliary Coolant System ExcessLetdown (Supply and Return)

A-30.3, Plant Procedure Content and ForematRequirements

AR-K31, Fire System Alarm Panel

M-71. 2, Module Rework/Test Procedure

0-6.2, Main Control Board System StatusVerification

58

58

58

58

58

58

1456

1438

ET-2. 2, Residual Heat Removal System

RSSP-6. 0, Containment Integrated LeakageRate Test

58

58

1334 M-40, Surveillance and Maintenance of HydraulicSnubbers

58

1475 S-7C, Transferring and Purification of ERSTWater Frcm RWST to SFP

58

1489

1496

HP-12.3, Selection of Respirators

HP-7.5, Pocket Dosimeter Accuracy and Leak'est

59

59

1501

1500

1494

P-3, Precautions, Limitations, and Setpoints

P-3 Chemical and Volume Control System

HP-1. 2, External Exposure Limits

M-40, Surveillance and Maintenance of HydraulicSnubbers

59

59

59

1495

1491

1483

S-15.1, Flux Mapping Normal Procedure

AR-F-10, Pressurizer Low Pressure Alarm

0-6.6, Correcting Measured Boron Concen-tration to Reference Full Power ExpectedBoron Concentration

59

59

59

-71-


1704

1705

1613

1614

1615

h

1666

I'708

1747

1728

1729

1785

1787

1783

1782

1781

1780

1778

1777

-- 1776

CP-80.2, Calibration Procedure for InsideMicnxLeters

CP-80.3, Calibration Procedure for Venier Calipers

PZ-13.4.7, Protomatic Deluge Valve System TestingSystem

XT-13.4.8, Protomatic Deluge Valve System Testing'ystem I8

KT-13.4.9, Protomatic Deluge Valve System TestingSystem

, PZ-13.4.10, Protomatic Deluge Valve System TestingSystem 510

S-4.1.22, Waste Evaporator Feed Tank Pump IsolationRestoration

ET-13.1.12, Containment Post-Accident (Recirc)and/or Auxiliary Filter RPD Testing

PZ-23.36, Containment Isolation Valve Leak RateTesting, Purge Exhibit

RSSP-8. 0, RTD Cross Calibration Check

GS-28.1, Electronic Seatch Ekpipment Testing

E-1.2, Loos of Coolant Accident

CP-37.2, law Voltage Power Supply NQ-402Adjustments

CP-35. 3, Intermediate Raneg N-35 Calibration

CP-35.4, Intermediate Range N-35 Bistable RelayDrivers Calibration

CP-36.0, Intermediate Range Channel N-36Calibration and/or Maintenance

CP-36.2 N-36, General Reinstate Procedure

CP-36.3, Intermediate Range N-36 Calibration

CP-36.4, Intermediate Range N-36 Bistable RelayDrivers Calibration

69

69

69

69

69

69

69

69

69

69

69

69

-72-


1775

1774

1773

1772

1771

1770

1769

1768

1767

1766

CP-37.0, Calibration and/or Maintenance of.Comparator Drawer N-37

CP-37.1, Zaw Voltage Polar Supply NQ-401Adjustments

CP-37.3, Low Voltage Power Supply NQ-403Adjustments

CP-37.4, Calibration of Level Trip Bistable RelayDriver NC-401

CP-38.0, Calibration and/or Maintenance ofDetector Current Gomparator Drawer

CP-38.1, Calibration and/or Maintenanoe of PowerSupply NQ-601

CP-38.2, Calibration and/or Maintenance of PowerSupply NQ-602

CP-38. 3, Calibration and/or Maintenance ofAveraging Circuit NM601

CP-38. 4, Calibration and/or Mainenance ofAveraging Circuit %1602

CP-40.0, Calibration and/or Maintenance ofDelta Flux Controllers CHannel 4

69

69

69

69

69

69

69

1765

1764

1763

1754

CP-ill.ll, Reactor Nakeup Water Flow Power SupplyFQ-ill

CP-209.3, Nx3el HFM-3, Hand and Foot MonitorCalibration

CP-210.0, Calibration and/or Maintenance 5KSChannel R-10A or R-10B

CP-212. 0, Calibration and/or Maintenance of MSChannel R-12

69

69

69

69

1750

1730

1732

CP-213.0, Calibration and/or Maintenance of %ISChannel R-13

CP-35. 2, General Reinstate Procedure

CP-40.0, Calibration and/or Maintenance of DeltaFlux Controllers Channel 4

69

69

69

-73-


1733

1734

1735

1736

1737

1738

1739

1740

1741

1742

1743

1744

1745

1751

1752

1760

CP-30.0, Calibration and/or Maintenance of DeltaFlux Controllers, Channel 3

CP-20.0, Calibration and/or Maintenance of DletaFlux Controllers, Channel 2

CP-10.0, Calibration and/or Maitnenance of DeltaFlux Controllers, Channel 1

CP-8.0, Calibration Alignment of T Avg. andDelta T at Zero Power Channel 4

CP-7.0, Calibration Alignment of T Avg. andDelta T at Zero Power Channel 3, Zaop B, Unit 1

CP-6.0, Calibration Alignment of T Avg. andDelta T at Zero Power, Channel 2, Zaop A, Unit 2

CP-5.0, Calibration Alignment pf T Avg. andDelta T at Zero Power, Channel 1, Zaop A, Unit 1

CP-2.20.5, Calibration Alignment of Pulse toAnalog Converter Bank

CP-2.20.4, Calibration Alignment of Pulse toAnalog Converter Bank "C"

CP-2.20.3, Calibration Alignment of Pulse toAna1og Converter Bank "B"

CP-2.20.2, Calibration Alignment of Pulse toAnalog Converter Bnak "A"

CP-2.20.1, Calibration of Pusle to AnalogConverter Power Supply

CP-2.20.0, Calibration and/or Maintenance of RPIPulse to Analog Converter

CP-212.3, Replacement of Detector for BNSChannel R-12


CP-210.3, Replacement of Detector for RMS ChannelR-10A or R-10B

69

69

69

69

69

69

69

69

69

69

1759

1758

CP-211.0, Calibration and/or Maintenance of RESChannel R-llCP-211.1, Calibration of Ratemeter Drawer R-ll 69

-74-

PCN I 78 Procedure a Title Neetin I 78

1757

1756


CP-211.3, Replacement of Detector forR'%hannel.R-ll

69

69

1755 CP-211.4, Check of Flew Control Systen for R-lland R-12

69

1762 CP-210.1, Calibration of Bate Meter Drawer R-10Aor R-10B

69

1761

1779

1731

1753

1701

1905

1906

1907

2022

1788

1789

1790

1791

CP-210.2, Calibration of R-10A or R-10B Detectors

CP-36.1, N-36, General Defeat

CP-35.1, N-35, General Defeat

CP-212.1, Calibration of Batemeter Drawer R-12

Rl 76-17.3, Screen House Intake Heater Cable TrayRework

EM-207, Replacing Splices and Splice Sleevesfor Pressurizer Level and Pressure Channels

B4-208, Containment Recirculation Fan Splices

220209, YDV-852A and 852B Splices

9 IP-30, Visual Examination of Supports

CP-220.3, Replacement of Detector for R1SChannel R-20



CP-220. 0, Calibration and/or Maintenance of EBSChannel R-20

69

69

69

71

71

71

71

72

72

72

72

72

1792

1793

1794

1795

CP-219.3, Replacement of Detector for RMS Channel-R-19



CP.-219.0, CAlibration and/or Maintenance of MSChannel R-19

72

72

72

72

-75-

PCN 5 78 Procedure a Title Meetin N 78

1796

1797

1798

CP-218.3, Replacement of Detector for EHS ChannelR-18


CP-218.0, Calibration and/or Miantenance of Et1SChannel R-18

72

72

72

1799

1800

1801

1802

CP-217.3, Replacement of Detector for EBS ChannelR-17


CP-217.11 Calibration of Ratemeter Drawer R-17

CP-217.0, Calibration and/or Maintenance of NSChannel R-17

72

72

72

72

1803

1804

1805

1806

CP-216.3, Replacement of Detector for RNS ChannelR-16

CP-216.2, Calibration of R-16 Dtector

CP16.1, Calibration of Batemeter Drawer R-16

CP-216.0, Calibration and/or Maintenance ofRMS Channel R-16

72

72

72

72

1807

1808

1809

1810

1811

1812

1813

1814

1815

CP-215.3, Replacement of RIS Channel R-15 Detector


CP-215.0, Calibration and/or Maintenance of MSChannel R-15

CP-214.3, Replacement of Detector for R4S ChannelR-14


CP-214.1, Calibration of Ratemeter Drawer R-14

CP14.0, Calibration and/or Maintenance of %IS" Channel R-14

CP-213.4, Check of R-13 and R-14 Flow ControlSystem

CP-213.3, Replacement of Detector for RMS ChannelR-13

72

72

72

72

72

72

72

72

72

-62-


1482

1476

1479

1478

1457

0-1.2, Plant From Hot Shutdown to SteadyLoad


PT-6.1, Source Range Nuclear Instrumenta-tion System, Channels

PZ-16, Auxiliary Feedwater System

M-40.1, Hydraulic Snubber Removal and Re-installation Procedure

59

59.-

59

59

59

1459

1458

1505

1506

1507

1488

1511

M-73.2, Welding on Stainless Steel Piping orComponents

M-73.3, Welding on Carbon Steel Piping andComponents

RD-9, Preparing Waste for Shipment or Storage


S-9R, Containment Sump "A" Water to SpentFuel Pit and the Return to Normal


SC-1.3A, Site Radiation Emergency (ShiftForeman and Control Rocm

59

59

59

59

59

59

59

1460

1461

1462

1463

1465

1466

1467

M-ll.8F, Reactor Coolant Pump —InternalInspection

M-ll.8H, Reactor Coolant Pump — ImpellerAssembly Decontamination

M-ll.5C, Minor Mechanical Inspection of theAuxiliary Feed Pumps for Pump

M-ll.5B, Major Wchanical Inspection of theAuxiliary Feed Pumps for Pump

M-66.1, Boric Acid Evaporator Feed TankHeater Replacement

M-32, Use of Circuit Reaker Multi-Amp TestUnit

M-56.2, Multi-Cable Electrical PenetrationEpoxy Seal Repair

59

59

59

59

59

59

59


1468

1469

1470

1471

1474

M-51.2, D. C. Voltage Monitor Relays forSafeguard rains

M-71.1, Bistable 431B for Pressure ControllerPRV-431C Replacement

M-72.1, Replacement Primary Zoo RPDp

EM-154, Steam Generator, Handhole CoverGasket Leak Repair Using "Furmanite" Process

M-43.1.1, Steam Generator Insert RemovalSteam Generator

59

59

59

59

1472

1473

M-16.1, Service Water Discharge Header ForTurbine Building Isolation

M-43. 20A IIAI'team Generator Secondary SidePressure Test

59

59

1065 A-2. 1 ReFuel

~ f Re ce iving, Inventory and Sh ipn t fen o 59

1497CheckPL'-31, Safeguard Pump Bearing Temperature 59

1490 HP-7.4ments

, Calibration of Neutron Surve In tey s ru- 59

1352

1508

1509

1549

1562

1558

WC-3, Alkalinity Determination

SC-l. 7F , Emergency Radiation bhnitoringOff-Site Survey Team N9F

SC-1.7H , Emergency Radiation bbnitorinOff-Site Survey Team N9H


InstA-60.3, Calibration Surveillance Program f

trumentation/equipment of Safet Rel edram or

y at Components

FixPZ-13.1.0, Testing and/or Maintenan f th'd Fire Detection and Extinguishi

ceo e

System1ng

59

60

60

60

60

60


1563

1517

1570

1566

1610 61659

1576

1519

1520

1590

ET-13.1.9, Halon System Testing (Resetting)Computer Room and Relay Room

M-40. 6, Steam Generator Hydraulic ShockSuppressors Leakage Test and Inspection

EC-.18. 2, Fluoride Determination

PC-18.1, Chloride Determination

RI-199, Sludge Removal from Waste HoldupTank

NC-7.2, Determination of Chloride ky SpecificIon Electrode

WC-8, Amperometric Determination of Chlorinein Water

WC-8.1, Chlorimetric Determination ofChlorine Water

WC-10.0, Solution pH Determination ky GlassElectrode Method

60

60

60

60

61

62

62

62

62

1602

1605

1604

1603

1609

1610

ET-5.10, Process Instrumentation ReactorProtection Channel Trip Test (Channel 1)

ET-5. 20, Process Instrumentation ReactorProtection Channel'rip Test (Channel 2)

ET-5.30, Process Instrumentation ReactorProtection Channel Trip Test (Channel 3)

ET-5.40, Process Instrumentation ReactorProtection Channel Trip Test (Channel*4)

ET-5.10, Process Instrumentation ReactorProtection Channel Trip Xhst (Channel 1)

EM-199, Sludge Removal from Waste HoldupTank

62

62

62

62

1643

1654

1648

EM-158, Seal Welding MOV-721 RHR to "B"Loop

M-12. 2, Inmdiate-Boration ET 113 GasketsReplacement

M-18.3, Waste Evaporator Inlet Check Valve1769 Replacement

62

62

62

-65-


1649

1647

1645

M-37.1A, Repacking of Pressurizer SprayValves 431A and 431B

M-37.18G, Inspection and Repair of 1BAuxiliary Building Sump Tank Pump DischargeCheck Valve

M-37.18H, Containment Spray Pump DischargeCheck Valve 862A and/or 2B Inspection andMaintenance

62

62

1644

1651

1650

1646

M-37.26.1, Testing and Repair of 1A SteamGenerator Blowdown Sample Isolation ValvesCV6 (5735)

M-37.27, Inspection and Repair of 3B SteamGenerator Blowdown Isolation Valve CV-71(5737)

M-37.47, RHR Pump Suction MOV-851A orMOV-851B Maintenance and Inspection

M-37.48, Component Cooling from RC PumpsMOV-759A and/or MOV-759B Isolation andMaintenance

62

62

62

62

1652

1653

1594

1066

1591

1574

15751573

1598

M-37.49, Level Control Valve From "B" RCSLoop ZCV-427 Maintenance and Inspection

M-37.50, MOV-721 RHR to "B" Loop Maintenanceand Inspection

PC-2, Gross Degassed Beta-Gamma Activity inPrimary Coolant

A-2.8, Special Nuclear Materia1 Inventoey andRecord Requirements

RD-8, Liquid Radwaste Compositing and Analysis

PC-21, Hydrogen Peroxide Analysis

PC-88 Reactor Coolant System Chemical AdditionsXC-10, Radioiodine Determination in PrimaryCoolant Unit T-10A Extraction

RSSP.3, Air Supply for Integrated Leak RateTest

62

62

62

62

62

62

6262

62

-66-


1597

1592

1642

1513

1512

1608

1595

1607

1606

1572

1611

1577

1578

1596

1612

Hone

None

None

None

1695

RSSP-7.3, Reactor Trip logic Relays Drop OutT>i&s

PC-5, Gamma Isotopic Analysis of DegassedPrimary Coolant

RI-157, Repair of Piping Leak on the B. A.Concentrates Holding Tank Pump Discharge

KT-23.25, Containment Isolation Valve LeakRate Testing Purge Supply

Pl'-23.36, Containment Isolation Valve LeakRate Testing Purge Exhaust


HP-12.2, Medical Check, Fitting and Trainingof Personnel Using Respirators

HP-12.5, Maintenance of Respirators

M-53.1, Containment Air Lodges Gasket Re-placement

0.4.1, equilibrium Indicated Axial FluxDifference Determination

0-6.11, Routeine Operations Check List

PC-18.3, Determination of Chloride by SpecificIon Electrode

PI'-2.2, Residual Heat removal System

A-l.l, Locked Radiation Areas

A30.3, Plant Procedure Content and FormatRequirements

GS-1.2, Ginna Station Security Event Report(2) 8/12/78 and 8/18/78

A-54. 4, Duty Engineer Responsibilities8/14/78

A-54.6, Health Physics Tour 8/148

0-6.7, Weekly Alarm Status Check 8/7/78

S-27.348A, Valve 348A, Isolation

62

62

62

62

62

62

62

62

62

62

62

62

62

62

62

65

-67-

PCN I 78 Procedure a Title Meet'in 5 78

1499

1699

1660

1661

1665

1698

1697

1696

1666

1690

PZ-13.1.10, Smoke Detector System Testing

A-30.3, Plant Procedure Content and FormatRetirements

E-l.l, Safety injection System Actuation

E-l.2, Loss of Coolant Accident

E-16.1, High Activity Radiation RonitoringSystem

PZ 6.3.1, Power Range Nuclear InstrumentationSystem, Channel 41

PT-6. 2, N.I.S. Intermediate Range Channels

PZ-6.3. 2, Power Range Nuclear Instrumentation.System Channel 42

M-ll.SB, Major bhchanical Inspection of theAuxiliary Feed Pumps

RF-52, Inspection Procedure for Exxon Nuclear FuelAssemblies at R. E. Ginna

66

66

66

1686

1691

1579

1580

1581

1978

1583

1584


HP-12.6, Issuance, Prayer Use and Return ofRespirators

, ET-23.44, Containment Isolation Valve LeakrateTesting Leakage/Test Depressurization

PT-23.45, Containment Isolation Valve LeakrateTesting Leakage Test/Instrumentation

PT-23.48, ll

Testing Deadweight Tester

PT-23. 49, ContainmentTesting Construction Fire Service Water

PT-23 50A ll ll ll ll

Testing Containment Post Accident Air Sample(Clean Int. Building)

PZ-23.50B, Containment Isolation Valve Leak rateTesting Containment Post Accident Air Sample(Controlled Int. Building)

66

66

66

66

66

66

-68-


1585

1586

1587

1588

1514

1515

1516

1551

1552

1553

1554

1555

PT-23. 50C, II If II

Testing Containnent Post Accident Air Salrple(Auxiliary Building)

PT-23 o 51A, If II I'I

Testing "A" Hydrogen Recombiner (Pilot and Main)

PT-23. 51B, If tl If II

Testing "B" Hydrogen Recombiner (Pilot and Main)

PZ 23 51CI If If II

Testing "A" and "B" Hydrogen Recombiner OxygenMakeup

PT 23 34 tf If It

Testing Depressurization at Power

PZ-23.33,Testing Service Air

ET-23. 32,Testing Instrument Air

PZ-23.43, II n If

Testing Leakage Test Supply Header

ET-23. 42, I'I II II

Testing Leakage Test Depressurization

PZ-23.40, Containment Isolation Valve LeakrateTesting Auxiliary Steam Supply and CondensateReturn

PZ-23.39, Containment Isolation Valve LeakrateTesting Demineralized Water

PT-23.46, Containment Isolation Valve LeakrateTesting Nitrogen to Accumulators

66

66

66

66

66

66

66

66

1556 PT-23.22, "Testing R. C. D. T. Discharge

1557 pg 23 23 If II II II

Testing Sump "A"66

1617

1618

PT-22, Containment

PT-22. 1, Hquipnent

Penetration Leakrate Testing

Hatch Door Seal Leakrate Test 66

-69-

PCN O 78 Procedure a Title Meetin I 78

1619

1620

PZ-22.2, Personnel Hatch Door Seal Leakrate Test

PZ-22.3, Persnel Hatch Between Door VolumeLeakrate Test

66

1621 ~22.4, shipment Hatch Between Door VolumeLeakrate Test

66

1622

1623

1624

1625

PZ-'22.5, Personnel Hatch Canopy Leakrate Test

PZ-22. 6, equipment Hatch

PZ 22.7, Hcpipment Hatch 0-Ring

PZ-22. 8t Mechanical Manifold "A"

66

66

66

1626

1627

1628

,1629

1630

1631

1632

ET-22. 9,

ET-22.10,

PZ-22.11,

PZ-22.12,

PT-22.13,

PT-22.14,

PT-22.15,

II IIBtt II

IICII II

ItEII ft

IIFII ll

IIQII II

IIHI'I II

II1 tl If

66

66

66

66

1633

1634

1635

1636

PT-22.16, Mechanical Manifold "J" Leakrate Test

'Z-22.17, II tfKfl It II

PZ-22.18 Electrical Manifold IX, Leakrate Test

PT-22.19, II II Ngl It If

66

66

66

1637 PZ-22.20, Illl tl 'I 66

1638

1639

1640

1673

1672

PT-22. 21, Mechanical Manifold "L" Leakrate Test

PZ22..22, Fuel Transfer Flange Leakrate Test

PZ-23, Containment Isolation Valve Leakrate Testing

M-73.3, Welding on Carbon Steel Piping or Components

M-73.2, Welding on Stainless Steel Piping orComponents

66

66

66

66

PCN 0 78

-70-


1589

1593

1565

1569

1571

1550

1568

1712

1713

1671

1693

1694

1715

1670

1714

PC-15. 1 , Solution pH Determination ~ GlElectrode Method

ion ass

PC-7, Iine 131, equivalentCalculat'C9.

.0, Determination of Chromate

NC-7.1, Fluoride Determination

WC-9.1, Determination of Total Chromium in Water

HP-l. 5.5, Dosimeter Discrepancy Evaluation

RI 78-1458 nt, Spe Fuel Pat Roughing Filter Frame0

A-30.2, Plant Procedure Clas f''pprovaland Distribution

S-3.4F Bo, Boron Recycle Process Shutdown

SC-1.15, In ct'pe ion of Emergency Ekpipment

PT-ll.l, Heat Traceace Circuitry Functional Check

PZ-ll. 60, Cell Battery Banks "A" and "B"

imitations and SetpointsP-l, PrecautionsL'acr Control and Protection System

HP-12.4, Fitti'ng and Testing of Respirators

Heat Exchanger Valve, HCV 625

66

66

67

67

67

67

1711

1709

1688

1786

1702

1703

GS-34.0, Vital Areas

RF-S.O, Fuel Assembly and Core Co nentment Prerequisites and Prean Precautions

GS-42.0, Site Designated Vehicles

EM-2 1'

Sp ice Covering Removal on the lDtainment Recirculation Fan

e Con-

CP-80.0Cal'eters

ibratxon Procedure for Outs'dr i e Micro-

'on Procedure for MicrometerCP-80.1, Calibration

67

67

67

69


1816

1817

1818

1819

1820

1821

1822

1823

1824

1825

1826

1827

1828

1829

1830

1831

1832

1833


CP-213.1, Calibration of . Ratemeter Drawer R-13

CP-403.5, T Avg (3 Sec) Lag Unit IN-403BB

CP-403.4, T Avg Dana Amplifier PN03A

CP-403.3, T Avg Dual Current Source TT-403

CP-403.2, Reinstate of T Avg Signal for Channel 3

CP-403.1, Defeat of T Avg Signal Channel 3

CP-402.9, T Avg Indicator TI-402

CP-402.8, T Avg Repeater 'IN-402W

CP-402.7, T Avg Repeater 'IN-402C

CP-402.5, T Avg (3 Sec) Lag Unit 'IN-402BB

CP-402.4, T Avg Dana Amplifier IN-402A-

CP-402.3, T Avg Dual Current Source TT-402

CP-402.2, Reinstate T Avg Signal for Channel 2


CP-401.8, T Avg Repeater IN-401W

CP-401.7, T Avg Repeater 'IN-401C

CP-401.6, T Avg Bistable TC-401A

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

1834

1835

CP-401. 5,

CP-401.4,

T Avg (3 Sec) Lag Unit 'IN-401BB

T Avg Dana Amplifier 'IN-401A

72

72

1836

1837

1838

1839

1844

1845

CP-401.3, T Avg Dual Current Source TZ-401


CP-401.2, Reinstate T Avg Signal Channel 1


CP-426.8, Pressurizer Level Indicator LI-426

CP-426.7, Pressurizer Level Repeater LN-426B

72

72

72

72

-77-


1846

1847

1848

1849

1850

1851

CP-426.6, Pressurizer Level Repeater LM-426A

CP-426.5,'ressurizer Level Bistable LC-426A/B

CP-426.4, Pressurizer Level Power Supply LQ-426

CP-426.2, General Reinstate 426 Pressurizer Level

CP-426.1, General Defeat Procedure 426 PressurizerLevel

CP-426.0, Calibration and/or Maintenance of 426Pressurizer Level Channel

72

72

72

72

72

72

1852

1853

1854

1855

1856

1857

1858

1859

1860

1861

1862

1863

1864

1865

CP-416.7, Reactor Coolant Flow Indicator FI416

CP-416.6, Reactor Coolant Flow Repeater FM-416

CP-416.5, Reactor Coolant Flow Bistable FC-416

CP-416.4, Reactor Coolant Flow Power SupplyFQ-416

CP-416.2, General Reinstate Procedure of ReactorCoolant Flow Channel 416

CP-416.1, General Defeat Procedure of ReactorCoolant Flow Channel 416

CP-416.0, Calibration and/or Maintenance ofReactor Coolant Flow Channel 416

CP-415.7, Reactor Coolant FLow Indicator FI-415

CP-415.6, Reactor Coolant Flow Repeater B4-415

CP-415.5, Reactor Coolant Flow Bistable EC-415

CP-415.4, Reactor Coolant FLow Power SupplyFQ15

CP-415. 2, General Reinstate Procedure for ReactorCoolant Flow Channel 415



72

72

72

72

72

72

72

72

72

72

72

72

72

72

-78-

PCN N 78 Procedure a Title Meetin 5 78

1866

1867

CP-414.6, Reactor Coolant Flow Repeater Fill-414

CP-414.5 Reactor Coolant Bistable Flow FC-414

72

72

1868

1869

CP-414.4, Reactor Coolant Flow Power. SupplyFQ14

CP-414.2, General Reinstate Procedure of ReactorCoolant Flow Channel 414

72

72

1870

1871



72

72

1872

1873

1874

1875

1876

CP-413.7, Reactor Coolant Flow Indicator FI-413

CP-413. 6, Reactor Coolant Flow Repeater Fill-413

CP-413.5, Reactor Coolant Flow Bistable PC-413

CP-413.4, Reactor Coolant Flow Polar SupplyFQ13

CP-413.2, General Reinstate Procedure ReactorCoolant FLow Channel 413

72

72

72

72

72

1877 CP-413. 1, General Defeat Procedure ReactorCoolant Flow Channel 413

72

1878 CP-413.0, Calibration and/or Maintenance ofReactor Coolant Flow Channel 413

72

1879

1880

1881

1882

1883

CP-412.7, Reactor Coolant FLow Indicator FI-412

CP-412.6, Reactor Coolant Flow Repeater EH-412

CP-412.5, Reactor Coolant Flow Bistable EC-412


CP-412.2, General Reinstate Procedure ReactorCoolant Flow Channel 412

72

72

72

72

72

1884

1885

CP-412.1, General Defeat Procedure Reactor CoolantFlow Channel 412

CP-412.0, Calibration and/or Maintenance of ReactorCoolant Flow Channel 412

72

72

-79-


1886

1887

1888

1889

1890

CP-411.7, Reactor Coolant Flow Indicator FI-411

CP-411. 6, Reactor Coolant Flow Repeater ETC-411

CP-411.5, Reactor Coolant Bistable EC-411


CP-411. 2, General Reinstate Procedure of ReactorCoolant Flow Channel 411

72

72

72

72

72

1891

1892

1893

1894

1895

1896

1897

1898

1899

1900

1901

1902

1903

1904

1909

1910

1911


CP-411. 0, Calibration and/or Maintenance ofReactor Coolant Flow Channel 411

CP-406.10.1, Defeat of Dleta T Setpoint 1 Channel 2

CP-404.9, T Avg Indicator TI-404

CP-404.8, T Avg Repeater 1H-404W

CP-404.7, T Avg Repeater TM 404C

CP-404.5, T Avg (3 Sec) Lag Unit KM-404BB

CP-404.4, T Avg Dana Amplifier 'IR-404A

CP-404.3, T Avg Dual Current Source TZ-404

CP-404.2, Reinstate of T Avg Signal forChannel 4


CP-403.8, T Avg Repeater 'BI-403W

CP-403.7, T Avg Repeater XK-403C

CP-403.6, T Avg Bistable XC-403A

CP-463.7, Steam Generator Level Repeater LM-463B

CP-463.6, Steam Generator Level Bistable LC-463E

CP-463.5, Steam Generator Level BistableLC-463C/D

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

-80-


1912

1913

CP-463.4, Steam Generator Level Pomr SupplyLQ63

CP-463.2, Reinstate of A Steam Generator LevelChannel 463

72

72

1914

1915

1916

1917

1918

1919

1920

CP-463.1, Defeat of A Steam Generator Level..Channel 463

CP-463.0, Calibration and/or Maintenance ofSteam Generator Level Channel 463

CP-462.8, Steam Generator Level Indicator LI-462

CP-462.7, Steam Generator Level Repeater EM-462

CP-462.5, Steam Generator Level Bistable LC-462A/B

CP-462.4, Steam Generator Level Power Supply~462CP-462.0, Calibration and/or Maintenance of SteamGenerator Level Channel 462

72

72

72

72

72

72

72

1921

.1922

1923

1924

1925

1926

1927

1928

1929

1930

1931

1932

CP-461.8, Steam Generator Level Indicator LI-461

'P-461.7,Steam Generator Level Repeater ZZ-461B

CP-461.6, Steam Generator Level Repeater LM-461

CP-461.5, Steam Generator Level BistableLC-461A/B

CP-461.4, Steam Generator Level Power Supply,LQ-461


CP-449.11, Pressurizer Pressure Indicator PI-449B

CP-449. 9, Pressurizer Pressure Repeater PM-449C

CP-449.10, Pressurizer Pressure Indicator PI-449

CP-449.8, Prewsurizer Pressure Repeater EM-449A


CP-449.5, Pressurizer Pressure Lead/Lag UnitPM49B

72

72

72

72

72

72

72

72

72

72

72

-81-

PCN N 78 Procedure a Titlei

Meetin N 78

1933 CP-449.4, Pressurizer Pressure Power SupplyP~449

72

1934 CP-449. 2, General Reinstate Procedure forPressurizer Pressure Channel 449

72

1935 CP-449.1, General Defeat Procedure forPressurizer Pressure Channel 449

72

1936 CP-449.0, Calibration and/or Maintenance ofPressurizer Pressure Channel 449

72

1937

1938

1939

1940


CP-431.10, Pressurizer Pressure Repeater P4-431C

CP-431.9, Pressurizer Pressure Rpeater PM-431A

CP-431.8, Pressurizer Pressure Bistable PC-431J

72

72

72

72

1941 CP-431. 5, Pressurizer Pressure Lead/Lag UnitPM31B

72

1942 CP-431. 4, Pressurizer Pressure Power Supplyrg-431

72

1943 CP-431. 2, General Reinstate Procedure PressurizerPressure Channel 431

72

1944 CP-431.1, General Defeat Procedure 431 PressurizerPressure Channel 431

72

1945 CP-431.0, Calibration and/or Maintenance ofPressurizer Pressure Channel 431

72

1946

1947

1948


CP-430.9, Pressurizer Pressure Repeater PM-430A


72

72

72

1949 CP-430.5, Pressurizer Pressure Leak/Zag UnitPM-430

72

.1950 CP-430. 4, Pressurizer Pressure Power Supply PQ-430 72

1951 CP-430.2, General Reinstate Procedure 430Pressurizer Pressure Channel

72

1952 CP-430.1, General Defeat Procedure 430 PressurizerPressure Channel

72

-82-

PCN N 78 Procedure & Title Meetin 5 78

1953 CP-430.0, Calibration and/or Maintenance of 430Pressurizer Pressure cannel

72

1954

1955

1956

1957

1958

CP-429.9, Pressurizer Pressure Bistable PC-429E


CP-429.5, Pressurizer Pressure Lead/Lag PM-429B

CP-429.4, Pressurizer Pressure Power Supply

CP-429. 0 Caiibration and/or Maintenance ofPressurizer Pressure Channel 429

72

72

72

72

72

1959 CP-428.0, Calibration and/or Maintenance of Pressurizer 72Pressure Channel 428

1960

1961

1962

1963

1964

1965

1966

1967

1968

1969

CP-427. 7, Pressurizer Level Indicator LI-427

CP-427. 6, Pressurizer Level Bistable LC-427A/C

CP-427.5, Pressurizer Level Bistable LC-427A/C

CP-427.4, Pressurizer Level Power Supply ZQ-427

CP-427.0, Calibration and/or Maitnenance ofPressurizer Level Channel 427

CP-427.1, Defeat of 427 Pressurizer Level

CP-427.2, Reinstate 427 Pressurizer Level

CP-428.1, Defeat of 428 Pressurizer Level

CP-428.2, Reinstate 428 Pressurizer Level

CP-429. 2, General Reinstate Procedure ofPressurizer Pressure Channel 429

72

72

72

72

72

72

72

72

72

72

1970 CP-429.1, General Defeat Procedure ofPressurizer Pressure Channel 429

72

1987

1988

1989

1990

CP-466.4, Feedwater Flow Power Supply FQ-466

CP-466.2, Reinstate of A Feedwater Flow Channel 466

CP-466.1, Defeat of A Feedwater Flow Channel 466

CP-466.0, Calibration and/or Maintenance of FeedwaterFlow Channel 466

72

72

72

72

-83-


1991

1992

1993

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

2005

2006

2007

2008

2009

2010

1982

1984

1985

1840

CP-465.11, Steam Flow Recorder FR-465

CP-465.10, Steam Flow Indicator FI-465

CP-465.9, Steam Flow Repeater PR-465D

CP-465.8, Steam Flow Repeater ER-465C

CP-465.7, Steam Flow Square Root Extractor PR-465B

CP-465.6, Steam Flow Multiplier/Divider FM-465A

CP-465.5, Steam Flow Bistable FC-465A

CP-465.4, Steam Flow Power Supply FQ-465

CP-465.2, Reinstate of A Steam Flow Channel 465

CP-465.1, Defeat of A Steam Flow Channe; 465

CP-464. 9, Steam Flow Repeater FN-464D

CP-464.8, Steam Flow Repeater EN-464C

CP-464.7, Steam Flow Square Root ExtractprFM-464B

CP-464. 5, Steam Flow Bistable FC-464A

CP-464.4, Steam Flow Power Supply FQ-464

~ CP-464.2, Reinstate 'of A Steam Flow Channel 464

CP-464.1, Defeat of A Steam Flow Channel 464

CP-463.8, Steam Generator Level Indicator LI0463

CP-466.5, Feedwater Flow Square Root ExtractorFM-466A

PZ-28, Control Room Air Handling Unit EfficiencyTest of HEPA and Charcoal Filter Banks in theAccident Axle

PT-29.1, Auxiliary Building HEPA and CharcoalFilter Efficiency 'I@st

ET-29.2, Controlled Access HEPA and Charcoal FilterEfficiency 'Ihst

PC-7, Iodine 131 Calculation

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

72

-84-


1841

2011

1980

1843

PC-6, E Total Activity and Maximum Acitivityin the Primary Coolant

RD-5, Ventilation System Releases

P 9g Precautions, Limitations and Setpoints, P-9gRadiation Honitoring System

A-54.5, Bulk Storage of Ccanbustible Materials andTheir Use

72

72

72

72

1976

1842

1977

1981

FT-16, Auxiliary Feedwater System

A-60.1, Ginna Station Technical SpecificationSurveillance Program

M-67.1, Protomatic Deluge Valve System MaintenanceSystem Numbers 7, 8, 9, 10

M-37.13, Inspection and Maintenance of A loopAccumulator Discahrge Check Valve V-842B

72

72

72

72

1986 A-54, Ginna Station Administrative and Enginering Staff 72Responsibilities

1974 PT-18.3, 1C Instrument Air Gompressor Air CapacityCheck

72

1975

1973

1972

1971

1994

1983

1908

1784

~18.2, 1B Instrument Air Gompressor Air CapacityCheck

PT-20.1, Control Air System Integrity for SteamLine Power Relief Valves

PZ6, Containment Fan Recirculation Unit HEPAFilter Bank 'lbsting


RSSP-2. 4, Containment Recirculation Fan ServiceMater Flow Test

XT-29, Containment Purge and Exhaust A and BEfficiency Xhst of HEPA and Charcoal Filter Banks


SM 75-34.24, Rework of Hanger SGB-19

S-12.2, Operator Action in the Event of Indicationof Significant Increases in Leakage — Items a-i

72

72

72

72

72

72

72

72

72

-85-

PC@ 4 78 Procedure & Title Meetin N 78

2039

2040

2019

2014

2015

2016

2017

2018

2020

2038

A-20, Control Room Logs

A-3, Containment Access

SC-1.12C, Specialized Call List

SC-l, Radiation Emergency Plan

SC-l. 7E, Emergency Radiation monitoring On-SiteSurvey Team 59E

SC-1.7G, Emergency Radiation monitoring On-SiteSurvey Team 59G

SC-1.3B, Site Radiation Emergency (EmergencyCoordinator and Survey Center Assignees)

SC-1.15, Inspection of Bnergency equipment

SC-l. 11A, Immediate Re-entry

CP-429. 2, General Reinstate Procedures ofPressurizer Pressure Channel 429

73

73

73

73

73

73

73

73

73

73

2024 CP-430.1, General Defeat Procedure 430Pressurizer Pressure Channel

73

2026

2027

CP-429.1, General Defeat Procedure ofPressurizer Pressure Channel 429

CP-429.2, General Reinstate Procedure ofPressurizer Pressure Channel 429

73

73

2028

2029

CP-449.1, General Defeat Procedure forPressurizer Pressure Channel 449

CP-449.2, General Reinstate Procedure forPressurizer Pressure Channel 449

73

73

2030

2031

CP-431.1, General Defeat Procedure 431Pressurizer Pressure Channel

CP-431. 2, General Reinstate Procedure PressurizerChannel 431

73

73

2043

2042

2044 .

HP-12.1, Usage of Respirators

HP-12.4, Fitting and Testing of Respirators

HP-12.2, Medical Check Fitting and Training ofPersonnel Using Respirators

73

73

73

-86-


2041

2035

2037

2033

2013

2034

2032

2045

2073

HP-12.3, Selection of Respirators

RD-7, Liquid Waste Release

HP.1, Controlled Area Entry

QC-1502, Non-Conformance Report

E-6.1, Loss of Component Coolaing During PowerOperation

S-3.4P, Transferring Concentrates frcm BoricAcid Evaporator Tank to Waste Evaporator FeedTank for Dnzraning

PT-2. 3, Safeguard Valve Operation

SN 75-10.28, Service Water Piping to Air HandlingUnits for Auxiliary Building Addition Remrk

CP-467.0, Calibration and/or Maintenance ofFeedwater Flow Channel 467

73

73

73

73

73

73

73

73

74

2072

2063

2064

CP-467.1, Defeat of A Feedwater Flow Channel

CP-468.11 Defeat of A Steam Generator PressureChannel 468

CP-468.0, Calibration and/or Maintenance ofSteam Generator 468

74

74

74

2046 CP-471. 0, Calibration and/or Maintenance ofSteam Generator Level Channel 471

74

2159

2152

2151

2138

2139

CP-471.1, Defeat of Steam Generator LevelChannel 471


CP-472.1, Defeat of Steam Generator LevelChannel 472


CP-473.1, Defeat of B Steam Generator LevelChannel 473

74

74

74

74

74

-87-


2133

2124

2113

CP-474.1, Defeat of B Steam Flow Channel 474

CP-475.0, Calibration and/or Maintenance of SteamFlow Channel 475

CP-476.0, Calibration and/or Maintenance of BFeedwater Flow Channel 476

74

74

74

2112 CP-477.0, Calibration and/or Maintenance ofFeedwater Flow Channel 477

2103

2123

CP-477.1, D feat of B Feedwater Flow Channel 4

CP-475.1, General Defeat Procedure Steam FlowChannel 475

74

74

2055

2091

2162

2161

2084

2168

2163

2164

2165

2077

2166

2086

2087

2088

2089

2167

CP-469.1, Defeat of A Steam Generator PressureChannel 469

S-1BB Shutdown of Rx3 Drive Motor Generator Sets

HP-12.6, Issuance, Proper Use and Return ofRespirators

HP.3, Work Permit Use



E-1.2, Zass of Coolant Accident

E-1.3, Steam Line Break Accident

E-1. 4, Steam Generator Tube Rupture Accident


ET-6.1, Source Range Nuclear InstrumentationSystem

PT-2.3, Safeguard Valve Operation

PZ-2.4, Gold/Refueling MOV's Surveillance

PZ-2.5, AOV's Quarterly Surveillance

PZ-2.6, Gold/Refueling AOV's Surveillance

ET-30, Containment Spray Nozzle Check of A & BRings

74

74

74

74

74

74

74

74

74

74

74

74

74

74

74

-88-


2090

2048

PZ-16.1, Auxiliary Feedwater System Flow Balance

EM-. 210, Auxiliary Building Main Crane Replacementof Driver Axle

74

74

2180

2160

2083

2190

2191

2192

RI-211, Replacing Splices and Splice Sleeves forPressurizer Level and Pressure Channels

S-3A, Startup of Rxl Drive Wtor Generator Sets

EN-190, Repair of Auxiliary Feedwater Hanger,FNH-39

M-40.4, Visual Leakage Inspection of High EnergyPiping

E-4.1, Safeguard Buses Low Voltage Condition

E-9, ?leakage Into the Component Cooling Loop

E-23.2, Malfunction of N2 Reactor Coolant PumpSeal

74

74

74

74

76

2193 E-23.3, Malfunction of N3 Reactor Coolant PumpSeal

2194

2195

2196

2197

2198

2188

2021

2187

2185

E-23.4, Zass of Reactor Coolant Pump SealInjection Supply

E-26.1, Erergency Shutdown Resulting from aReactor Trip from 8.5% Power or Less

E-26.2, Emergency Shutdown Resulting from aReactor Trip When Between 50% and 8.5% Power

E-31, Automatic Turbine Load Runback

E-36, orator Actions to be Taken in the Eventof Alarm Conditions on the Turbine Vibration Instruments

M-40.6, Steam Generator Hydraulic Shock SuppressorsLeakage Test and Inspection

SC-1.12A, Immediate Call List

S-15.3, Incore Wvable Detector Alignment

A-54.3, Cpen Flame, Welding and Grinding Permit

76

76

76

76

76

76

76

76

-89-


2183

2189

2199

A-52.1, Shift Organization Relief and Turnover

M-25, Adjustment Procedure for thermallyCompensating Supports cn Main Steam Header SafetyValves and Power Operated Relief Valves

O-l.l, Plant Heatup from Cold Shutdown to HotShutdown

76

76

2203

2170

2171

2172

2173

HP-10.3, Flow Rate Calibration of High Volume AirSamples

GS-l.l, Security Cgerations Plan

GS-7.0, Security Officer's Report

GS-14.0, Security Guard Response to Trespassers

GS-15.0, Security Guard Action if There is a PortalMonitor Alarm

76

76

2174

2175

2176

2177

2178

2179

2023

2217

1560

1498

2212

2216

GS-16.0, Property Removal

GS-21.1, Site Access Control (Security) forEmergency Situations

GS-21.1, Unoccupied Vital Area Access Control

GS-24. 0, Security Surveillance Requirements andProcedures

GS-28.0, Search of Personnel, Vechiles, andPackages

GS-21. 0, Door Alarm System

A-50.9.3, Health Physics Technician Trainingand Responsibility Limits

SC-1.12D, Management Call List

XT-13. 5, Fire Spray System External Header/NozzleInspection

PT-13.1.14, Fire Barrier Penetration Seals


RSSP-l. 1, Interlock Verification Residual HeatRemoval System

76

76

76

76

76

76

76

77

78

,78

78

78

-90-


2215

2220

ET-2.10.2, RHR System Core Deluge Check Valves

A-17, Plant Operations Review Committee OperatingProcedure

78

78

2219

2221

2182

2225

2233

2232

2231

2230

2229

S-4.1S, Lictuid Waste Process Operation and Shutdown

S-4. 1E, Waste Condensate Releases

PT-2.5.1, Air Operated Valve Quarterly Surveillance(Containment)

S-4.2.9, Nitrogen Backup Supply to AuxiliaryBuilding

S-2. 1A, Pre-Startup Lineup of Reactor CoolantPump

S-3. 3B, Hydrogen Concentration Control

S-4.2.2, 1A Waste Gas Compressor Startup

S-4.2.4, Gas Decay. Tank Opeations

S-4.2.6, Isolating Reactor Coolant Drain Tankfrom Vent Header

78

78

78

79

79

79

79

79

79

2228

'224

2251

2252

2247

2235

2237

2241

2242

S-6, Nuclear Instrumentation System

S-14, Area and Process Radiation Monitoring System

- ~ KT-23.37, Containment Isolation Valve LeakrateTesting —Reactor Compartment Cooling Unit A

PT-23.28, Containment Isolation Valve LeakrateTesting —Reactor Compartment Cooling Unit B

P-4, Precautions, Limitations and SetpointsAuxiliary Coolant System

PZ-29.3, Auxiliary Building Ventilation MainHEPA Filter Bank 'lhsting

RSSP-2. 2, Diesel Generator Load and SafeguardSequence Test

RSSP-2.1A, Safety Injection Functional TestAlignment

RSSP-1. 3, Valve Interlock Verification —ChemicalVolume and Control System

79

79

79

79

79

79

79

79

79

-91-

PCN 5 78 Procedure s Title Meetin 5 78

2261 EM-190, Repair of Auxiliary Feedwater Hanger,FNH-39

79

2262

2263

2264

2265

2269

2254

EM-206, Spl-ice Covering Removal on the 1DContainment Recirculation Fan

EM-207, Replacing Splices and Splice Sleeves forPressure Level and Pressure Channels

EM-208, Containment Recirculation Fan Splices

EM-209, MOV-852A and 952B Splices

HP-8.4, RAdioactive Source Inventory

S-15. 2, Flux Mapping Emergency and CalibrationProcedure

79

79

79

79

79

79

2250

2255

2256

2257

2259

2260

2249

2248

2270

2271

2244

2245

2234

2236

PZ-31, Safeguard Pump Bearing Temperature Check

PZ-2.1, Safety Injection System Pumps

~2. 2, Residual Heat Reaaval System


PT-3, Containment Spray Pumps and NaOH Additive.System


. A-60.3, Calibration Surveillance Program forInstrumentatio@+uipnent of Safety Related Components

M-45. 4, Safeguard Motors Inspection

HP-12.6, Issuance Proper Use and Return ofRespirators

SM 75-7.25, HVAC Backfits Rework

RF-2, Reactor Refueling .Outage Cgerations andActivities



ET 9, Undervoltage and Underfrequency Protection11A and 11B 4160 Volt Buses

79

79

79

79

79

79

79

79

79

79

79

79

79

-92-


2238

2239

2240

2243

2252

2267

RSSP-13.1, Hydro cn CVCS Class C SafetyRelated Piping, Part 1

RSSP-13.2, Hydro on CVCS Class C Sagety BelatedPiping, Part 2

BSSP-14.1, Condenser Steam Dump Interlock ZoicTest

RSSP-1. 2, Valve Interlock Verification —SafetyInjection System

PT-13.1.1, Protomatic Deluge Valve System TestingSystem Numbers 7, 8, 9, 10

CP-70.6, West Pyrometer Calibration or MaintenanceSerial No.

79

79

79

79

79

79

2213

1655

2200

2202

1477

2246

2268

2137

2306

2303

2302

2312

2315

HP-1.6, Neutron Exposure

M-73.4, Welding of Carbon Steel Piping or Componentsto Stainless Steel Piping or Components

WC.1, Bed+en DU-2 Calibration Procedure

SC-3.16.15, Charging of Air Pak CylindersCompressor or Cascade Method

SM 75-50.31, Jet Shielding Rework, Main Steamand Feedwater

M-40.8, Functional Testing of Hydraulic Snubbers

9 -1601, Corrective Action

EM-212, Repair of Boric Acid Cation DI Bad>washDrain Valve V-1163

0-6.11, Routine ~rations Check

A-52.8, Ginna Station Curve Book Directions

HP.5, Pocket Dosimeters Accuracy/Leak Rate Test

PZ-6.3.1, Polar Range Nuclear InstrumentationSystem, Channel 41

PZ-6.3.2, Power Range Nuclear InstrumentationSystem, Channel 42

79

79

79

79

79

79

79

80

81

81

81

81

81

-93-

PCN I 78 Procedure & Title Neetin I 78

2314

2313

2310

2309

2323

2266

2036

2324

2327

2328

2304

2331

PT.3. 3, Power Range Nuclear InstrumentationSystem, Channel 43

PT.3.4, Power Range Nuceear InstrumentationSystem, Channel 44

N-38.4, lA Constant Voltage Transformer Maintenance

'P-250.6,Calibration and/or Maintenance ofWind Speed Voltage Signal Conditioner

PT-13.4.10, Protomatic Deluge Valve System TestingSystem 510A (412A Transformer)

PZ-2.5.2, Air Operated Valves, QuarterlySurveillances (Valves 112B and 112C)

KT-35, Welding Rod Oven 'Ihermmeters

PZ-13.4.10A, Protomatic Deluge Valve SystemTesting System 10A (512A Transformer)

S-4.5.4, Boron Recycle Base Removal DI ResinReplacement

S-4.5.5, Boron Recycle Cation DI Resin Replacement

O-l.2. 2, Critical Rod Position Calculation

SC-13.15.15, Emergency Fire shipment LockerInventory and Inspection

81

81

81

81

81

81

81

81

81

81

81

2369 M-38. 9,Repair

Battery Charger Maintenance and/or 82

2333

2326

2359

2316

2373

2329

2353

2354

A-20, Control Room Zags

N-56.1, Placement of Ceramic Fiber PenetrationSeals

RD-2, Containment Purge Releases

T-32C, Velocity Flush of the Fire Water System

T-32C, Velocity Flush of the Fire Water System

HP. 2, Self-Reading Dosimeter Use

PC-22, Hydrazine Determination

PC-15. 2, Specif ic Conductance

83

83

83

83

83

, 83

83

83

-94-


2357

2367

2360

2358

PC-13, Dissolved Oxygen Determination

CP-250. 7, Calibration and/or Maintenance ofSynchro to DC Converter

A-l.1, Locked Radiation Areas

K',-l.l, Primary Coolant Anaylsis Schedule andLimits

83

83

83

83

2347

2273

2273

2339

2342

2343

2344

2361

2345

M-37.38.1, Crosby Safety and Relief ValveMaintenance for Valve No.

A-30. 2, Plant Procedure Classif ication, Review,Approval and Distribution Requirements


RD-6, Gas Decay Tank Releases

CP-424.1, Calibration and/or Maintenance ofPressurizer Liquid Temperature +I Converter

CP-425. 3, Calibration and/or Maintenance ofPressurizer Vapor Temperature Indicator TI-425

CP-425.1, Calibration and/or Maintenance ofPressurizer Vapor Temperature +I Concerter

PC-16, Solids Determination

ZN-211, Replacing Splices and Splice Sleeves forPressurizer Level and Pressure Channels

83

83

83

83

83

83

83

83

83

2346

2335

2236

2330

2372

2305

ZM-212, Review of B. A. Recycle Cation DIBackwash Drain Valve 1163

QCIP-21, Shipping Package LL-50-100 Inspection

QCIP-22, Shipping Package HN-100 Series 1Inspection

WC-2. 0, Metrohm E-415 Titractor Calibration

&I 75-5.43, Final Reowrk for Standby AuxiliaryFeedwater


83

83

83

83

83

84

-95-


2463

2456

2457

2458

2459

2451

2452

2453

2454

2375

2383

2382

2381

2378

2379

2380

2377

2376

2386

2394

SM 75-5.38, Standby Auxiliary Feedwater SystemOperational Testing

CP-103. 0, Calibration and/or Maintenance ofBoric Acid Temperature Controller TIC-103

CP-104.0, Calibration and/or Maitenance ofBoric Acid Tank ~rature Indicator TI-104

CP-105.0, Calibration and/or Maintenance ofBoric Acid Tank lhmgerature Indicator TI-105

CP-107.0, Calibration and/or Maintenance of BoricAcid Tank ~rature Controller TCI-107

S-4.4.1, Spent Resin Package —Site Receipt andShigrent


A-50.10, Operator Incident Review


RD-S, Waste Water Composite Calculations



Pl.3.1, Power Range Instrumentation SystemChannel 41ET.3. 2, Power Range Instrumentation SystemChannel 42

PT-6.3.3, Power Range Instrumentation SystemChannel 43

PX 6.3. 4 Power Range Instrumentation SystemChannel 44

RF-8.1, Step by Step Fuel Loading and Maps


CP-934. 1, Accumulator Level Transmitter LT-934

CP-920.1, Placing of Refueling Water StorageTank Level Channel 920 Out of Service

84

84

84

84

84

84

84

84

84

84

84

84

84

84

84

84

84

84

-96-


2413

2434

2441

2448

2348

2322

2341

2364

2362

2351

2355

2356

2363

CP-485.1, Defeat of Turbine First Stage PressureChannel 485

CP-482.1, Defeat of A Steam Generator PressureChannel 482

CP-479.1, Defeat of B Steam Gnerator PressureChannel 479

CP-478.1, Defeat of B Steam Generator PressureChannel 478

HP-7.7, Calibration of Beta Survey Instruments

M-43.16.1, Steam Generator Tube Sheet Photo-Mapping

PC-1.4, Operation of Gamma Analyser

WC-3. 1, Sodium Sulfate Determination

WC-3. 2, Solids Determination

WC-3. 3, Hardness Determination

WC-10.1, Specif ic Conductance

WC-12.0, Dissolved Oxygen Determination

WC 12 1 g Dissolved Oxygen Determination AZIDEMethod

84

84

84

84

84

84

84

84

84

84

84

84

84

2352

2350

2365

2366

2349

2384

2385

2387

W-13.0, Hydrazine Determination

NC-13.1, Free Hydroxide Determination

WC-13. 2, Silica Determination

WC-13. 3, Phosphate Determination

WC-14.0, Oil and Grease Determination

QC-801, PDR Control of Accepted Materials,Parts 85 and Components

CP-934.3, Accumulator Level ~ Indicator LI-934

CP-934.2, Accumulator Level Bistable LC-934

CP-920.7, Hefueling Water Storage Tank LevelIndicator LI-920

84

84

84

84

84

86

86

,I

a.J

-97-

PCN I 78 Procedure & Title Meetin " 78

2389 CP-920.6, Refueling Water Storage Tank Level3istable LC-920C

86

2390

2391

2392

2393

CP-920.5, Refueling Water Storage Tank LevelBistable LC-9203/B

CP-920.4, Refueling Water Stroage Tank LevelPower Supply LQ-920

CP-921.0, Calibration and/or Maintenance P~urefor Refueling Water Storage Tank Level Indicating Alarm

CP-920.2, Placing of Refueling Water Storage TankLevel Channel 920 In Service

86

86

86

2395 CP-626.9, Residual Heat Removal Flow ChannelController FC-626A

86

2396

2398

CP-626. 8, Residual Heat Removal Flaw Channel

CP26.7, Residual Heat Removal Flow IndicatorFI-626

86

86

2399

2400

2401

2402

2403

2404

CP-626. 6, Residual Heat Removla Flow SquareRoot Extractor 2K-626

CP-701Turbine Driven Auxiliary Feedwater PumpOil Pressure Regulator Adjustment

CP-626.5, Residual Heat Removal Flow ChannelBistable PC-626B

CP-626. 4, Residual Heat Removal Power SupplyFQ-626

CP-486.2, Reinstate carbine First Stage PressureChannel 486

CP-486.9, Turbnie First Stage Pressure IndicatorPI-4

86

86

86

86

86

86

2405

2406

2407

CP-486.1, General Defeat Procedure Channel 486First Stage Pressure

CP-486.8, Turbine First Stage Pressure TransmitterRepeater M-486A

CP-486.7, Turbine First Stage Pressure BistablePC-486B

86

86

86

OTHER CHANGES, TESTS AND EXPERIMENTS

-98-


2408 CP-486.6.6, Turbine First Sl'age Pressure I—'nitPM-486B

.,~se

2409

2411

CP-486.5PC-486~C

.5, TUrbine First Stage Pressure B'ablis e

CP-486.4.4, Turbine First Stage Pressure PowerSupply PQ-486

86

2412

2414

2415

CP-485.9,PI-485CP-485.8,

CP-485.7,PM-485A

Turbine First Stage Pressure Indicator

Turbine First Stage Pressure Repeater PM-485B

Turbine First Stage Pressure Re tpea er 86

2416PC-485CCP-485.6, Turbine First Stage Pressure B'ablis e 86

2417

2418

2419

2420

2421

2422

CP-485.5PC-48~

, Turbine First Stage Pressure B'ablis e

CP-485.4 , Turbine First Stage Pressure PowerSupply PQ-485

CP-483.9, Steam Generator Pressure IndicatorPI-483 and PI-483B

CP-4PM-483C

83.8, Steam Generator Pressure Re tpea er

~ CP-483..7, Steam Generator Pressure Repe tPM-483B

pea er

CP-483. 6 S.PC-483A

, Steam Generator Pressure Bistabl PC8e 3A

86

86

86

86

86

2423 CP-483.5, Steam Generator Pressure Lead~~"Unit PM-483A

a g~g 86

2424

2425

2426

CP-483.4, Steam Generator Pressure PowerSupply PQ-483

Channel 483CP-483.2, Reinstate of B Steam Generator Pror essure

CP-482. 9, Steam Generator Pressure IndicatorPI-482A and Remote PI-4828

86

86

-99-

PCN 5 78 Procedure 6 Title Meetin I 78

2427 CP-478.8, Steam Generator Pressure RepeaterPM-478C

86

2428 CP-483.1, Defeat of B Steam Generator PressureChannel 483

86

2429 CP-482.7, Steam Cinerator Pressure RepeaterPM-482B

86

2430 CP-482. 6, Steam Generator Pressure BistablePC-482A

86

2431 CP-482.5, Steam Generator Pressure Lead/LagUnit PM-482A

2432

2433

CP-482.4, Steam Generator Pressure PowerSupply PQ-482

CP-482.3, Steam Generator Pressure TransmitterPT-482

86

86

2435 CP-479. 8, Steam Generator Pressure IndicatorPI-479

2436 CP-479.7, Steam Generator Pressure RepeaterPM-479B

2437 CP-479.6, Steam Generator Pressure BistablePC-479A

86

2438 CP-479. 5, Steam Generator Pressure Lead/LagUnit PM-479A

86

2439

2440

CP-479.4, Steam Generator Pressure PowerSupply FQ-479

CP-479.2, Reinstate of B Steam Generator PressureChannel 479

86

2442 CP-478.10, Steam Generator Pressure IndicatorPI-478

86

2443 CP-478.8, Steam Generator Pressure RepeaterPi<1-478C

86

2444

2446

CP-478.7, Steam Generator Pressure RepeaterPM-478B

CP-478.6, Steam Generator Pressure BistablePC-478A

86

86

-100-

PCN I 78

2447

Procedure & Title

CP-478.5, Steam Generator Pressure Lead/LagUnit Pi4-478A

Meetin I 78

86

2449

2448

CP-478.4, Steam Generator Pressure Power SupplyPQ-478

CP-478.1, Def at of B Steam Generator PressureChannel 478

2441 CP-479.1, Defeat of B Steam Generator PressureChannel 479

2434

2413

2394

CP-482.1, D feat of A Steam Generator PressureChannel 482

CP-485.1, Defeat of Turbine First Stage PressureChannel 485

CP-920.1, Placing of Refueling Water Storage TankLevel Channel 920 Out of Service

86

86

86

2386

2450

2445

2410

2397

2388

CP-934.1, Accumulator Level Transmitter LT-934

CP-478.0, Calibration and/or Maintenance of SteamGenerator Pressure Channel 478

CP-479.0, Calibration and/or Maintenance ofSteam Generator Pressure Channel 479

CP.-486. 0, Calibration and/or Maintenance ofTurbine First Stage Pressure Channel 486

CP-920.0, Calibration and/or Maintenance of920 Refueling Water Storage Tank Level Channel

CP-934.0, Calibration and/or Maintenance P~ure ofAccumulator Level Channel 934

86

86

86

86

86

86

2485

2464

2340

2370

2374

2362

Rl 75-5.39, Standby Auxiliary Feedwater +stemRework

RI 75-14.1, Batch Tank Recirculation Heat TraceInstallation

M-2.2, Calibration of Specific Ion Electrodes

M-38.8, lA Battery Charger Maintenance or Repair

WC-14.1, Oil Film Thickness Determination

WC-3.2, Solids Determination

86

86

86

86

86

86

-101-


2461

2462

M-43.0, Steam Generator Maintenance Test andRepair Procedures

M-43.16, Steam Generator Explosive Tube PluggingSteam Generator

86

86

2467

2483

2484

2371

2085

2334

2471

2307

2492

2493

2494

2496

2495

2497

2486

2487

HP-7.5, Pocket Dosimeter/Accuracy and Leak T st

XT-13. 5, Fire Spray System External Header/h7ozzleInspection

ET-2.9. 2, Accumulator Discharge Check ValvesQuarterly Exercising

SC-3.3.3, Fire Brigade Recall List

SC-3.15.6, Fire Hose Reel Assembly Inspection

S-12.4, RCS Leakage Surveillance RecordInstructions

S-12. 4, RCS Leakage Surveillance RecordInstructions

~13.1.9, Halon System Testing (Resetting)Computer Room and Relay Bxxn

SC-3.3.1, Immediate Fire Notification

SC-3. 15. 2, Fire Protection shipment Impairment

SC-3.16. 6, Operating Instructions —Fusible LinkSprinkler System

SC-3.16.7, Operating Instructions, AutomaticDeluge System

SC-3.16. 8, Operating Instructions, ManualDeluge Systems

SC-3.16. 9, Operating Instructions, Halon 1301Systems

PP-20.1, Control Air System Integrity forSteam Line Pawer Relief Valve

PZ-5.10, Process Instrumentation ReactorProtection Channel Trip Test (Channel 1)

86

86

86

86

87

87

87

87

87

87

87

87

87

87

-102-


2488

2489

2490

2472

2479

2538

2537

2543

2512

2525

2526

2527

2517

2518

2519

2520

2521

2499

2540

ET-5. 20, Process Instrumentation ReactorProtection Channel Trip Test (Channel 2)

FZ-5. 30, Process Instrumentation ReactorProtection Channel Trip Test (Channel 3)

ZT-5. 40, Process Instrumentation ReactorProtection Channel Trip Vest (Channel 4)

PT-13.7, Fire Hose Reel Assembly Inspection

A-30.3, Plant Procedure Content and FormatRetirements

HP-l. 1, Issuing Personnel Dosimeters

HP-l. 3, External Exposure Records

HP-2.2, Whole Body Counter Operation

HP-11.4, High Volume Air Sampling

AR/Fl, High Condenser Pressure or Lossof Both Recirculating Water Pumps

AR/H, High Condenser Pressure

AR/K-17, Zaw Vacuum Trip

PT-23.17A, Containment Isolation Valve LeakRate Testing Containment Pressure Sensing

~ Transmitterr PT45 and PZ 946

PZ-23.17B, Containment Isolation Valve LeakRate Testing Containment Pressure SensingTransmitter, PT 947 and PZ48

FT-23.17C, Ctainment Isolation Valve LeakRate Testing Containment Pressure SensingTransmitter, PT49 and PT50

PZ 23.19, Containemtn Isolation Valve Leak, Rate Testing Safety. Injection System

PT3.21, Containment Isolation Leak RateTesting RCDZ to Gas Anaylser

S-27. 365A, V-365A Isolation

0-6, Cperation and Process Nonitoring

87

87

87

87

88

88

88

88

88

88

88

88

88

88

88

88

88

88

88

-103-


2513

2500

2501

2514

2544

2522

2531

2532

2533

2524

2535

2536

2542

2523

2535

'2515

RD-1.3, Tritium in Containment Air Sampling. and Analysis

RD-3, Plant Vent Iodine and ParticulateReleases Sampling and Anylysis

RD-6, Gas Decay 'ink Releases

RD-12, Tritium in Air Sampling and Analysis

GS-8.0, Detex Tours ky Security Guards

CP-134.0, Zetdown Line Flaw Iaop 134Calibration and/or Maintenance

CP-501.1, Voltmeter Calibration for 480VCircuit Bus 513

CP-S01.2, Voltmeter Calibration for 480VCircuit Bus 315

CP-501.3, Voltmeter Calibration for 480VCircuit Bus 114 (Safeguard)

CP-501.4, Voltmeter Calibration for 480VCircuit Bus 117

CP-501.5, Voltmeter Calibration for 480VCircuit Bus 116 Safeguard Device NN

CP-501.6, Voltmeter Calibration for 480VCircuit Bus 118 (Safeguard)

CP-2030.0, 1B Mtor Driven Auxiliary FeedwaterPump Discharge Pressure Loop 2030

PC-13, Dissolved Oxygen Determination

PC-1.4, Cperation of Gamma Analyzer

PC-l.l, Analysis Schedule and Limits, PrimaryCoolant

88

88

88

88

88

88

88

88

88

88

88

88

88

88

88

88

2473 6 2455 A-l, Radiation Control Manual 88

2528

2529

T-6.1, Regeneration of the Condensate PolishingMixed Bed Demineralizer Unit

T-6.2, Air Bump and Rinse Cleaning of theCondensate Polishing Mixed Bed Demineralizer Units

88

88

-104-

PCN 4 78 Procedure a Title Meetin O 78

2516

2503

2504

2505

2506

2475

2476

2477

2482

2637

2636

2633

2632

2629

2628

2627

2626

T-6.1, Regeneration of the CondensatePolishing Mixed Bed Demineralizer Unit

PV-6.3. 1, Power Range Nuclear InstrumentationSystem, Channel 41

PZ-6.3. 2, Power Range Nuclear InstrumentationSystem, Channel 42

PZ 6.3.3, Power Range Nuclear InstrumentationSystem, Channel 43

PZ-6.3. 4, Power Range Nuclear InstrumentationSystem, Channel 44

PT-13.4.12, Alarm Valve System Testing FireSystem 512, Turbine Island Sprinkler

PZ-13.4.13, Alarm Valve System Testing FireSystem f13 Service Building Sprinkler

PZ-13.4.15, Alarm Valve System Testing, FireSystem 515 Warehouse

Rl 74-28.1, Installation of i~cup Linesto Condensate Storage Tanks

CP-2093.3, Atmospheric Relief Valve 1B(CV-57) Control Pressure Switch 2093

CP-2093. 2, General Reinstate Procedure 2093Ahnospheric Relief Valve 1B (CV-57) Control

CP-2092.3, Atmosheric Relief Valve 1A (CV-56)Control Pressure Switch 2092

CP-2092.2, General Reinstate 2092Atmospheric Relief Valve 1A (CV-56) Control

CP-950.7, Containment Pressure IndicatorPI-950

CP-950.6, Containment Pressure RepeaterPM-950

CP-950. 5, Containment Pressure BistablePC-950k/8

CP-950.4, Containment Pressure Power SupplyPQ-950

88

88

88

88

88

88

88

88

88

90

90

90

90

90

90

90

90

-105-

PCN N 78 Procedure a Title Meetin g 78

2625 " CP-950. 3, Containment Pressure TransmitterPT-950

90

2624

2621

2620

2619

2618

2617

2616

2613

2612

2611

2610

2609

2608

2605

2604

CP-950. 22 Reinstate of B-3 ContainmentPressure Channel 950

CP-949. 7, Containment Pressure IndicatorPI-949

CP-949. 6, Containment Pressure RepeaterPM-949

CP-949. 5, Containment Pressure BistablePC-949A/8

CP-949. 4, Containment Pressure Power SupplyPQ-949

CP-949.3, Containment Pressure TransmitterPT-949

CP-949. 2, Reinstate of B-1 ContainemntPressure Channel 949


CP-948.6, Containment Pressure RepeaterPM-948

CP-948. 5, Containment Pressure BistablePC-94~


CP-948. 3, Containment Pressure TransmitterPT-948

CP-948. 2, Reinstate of B-2 ContainmeytPressure Channel 948


CP-947. 6, Containment Pressure RepeaterPN-947

90

90

90

90

90

90

90

90

90

90

90

90

90

90

90

-106-


2603

2602

2601

2600

CP-947.5, Gontainment Pressure BistablePC-947~

CP-947. 4, Containment Pressure Power SupplyPQ-947


CP-947.2, Reinstate A-3 Containemnt PressureChannel 947

90

90

90

90

2597 CP-946. 7, Containment Pressure IndicatorPI-946

90

2596

2595

2594

2593

2592

2589

2588

2587

2586

2585

2584

2635


CP-946. 5, Gontainment Pressure BistablePC-946A/8


CP-946. 3, Containment Pressure Transmitter~946

CP-946.2, Reinstate of A-2 Containment PressureChannel 946

CP-945. 7, Containment Pressure IndicatorPI-945


CP-945. 5, Containment Pressure BistablePC-945A/B



CP-945.2, Reinstate of A-1 Containment PressureChannel 945

CP-2093.1, General Defeat Procedure 2093Atmospheric Relief Valve 1B (CV-57) Control

90

90

90

90

90

90

90

90

90

90

90

90

-107-


2631

2623

2615

2607

CP-2092.1, General Defeat Procedure 2092. Atriaspheric Relief Valve,lA (CV-56) Control

CP-950.1, Defeat of B-3 Containment PressureChannel 950



90

90

90

90

2599

2591

2583

2582

2581

CP-947.1, Defeat of A-3 Containment PressureChannel 947



CP-945. 0, Calibration and/or Maintenance ofContainment Pressure Channel 945

CP-941.4, Accumulator Pressure Local IndicatorPI-941

90

90

90

90

90

2580

'579

2578

CP-941.3, Accumulator Pressure BistablePC-94~

CP-941.2, Accumulator Pressure Power SupplyPQ-941

CP-941. 1, Accumulator Pressure TransmitterPT-941

90

90

90

2576 CP-940. 4, Accumulator Pressure ~Indicator PI-940

90

2575

2574

CP-940.3,PC-940~

CP-940.2,PQ-940

Accumulator Pressure Bistable

Accumulator Pressure Power Supply

90

90

2573 CP-940.1, Accumulator Pressure TransmitterPT-940

90

-108-


2571 CP-939. 3, Accumulator Level IndicatorLI-939

90

2570

2569

CP-939. 2, Accumulaotr Level BistableLC-939A/8

CP-939.1, Accumulator Level TransmitterLT-939

90

90

2567 CP-938. 3, Accumulator Level IndicatorLI-938

90

2566

2565

CP-938. 2, Accumulator Level BistableLC-938A/B

CP-938. 1, Accumulator Level TransmitterLT-938

90

90

2563 CP-937. 4, Accumulator Pressure IndicatorPI-937

90

2562

2561

2560

CP-937.3, Accumulator Pressure BistablePC-937~

CP-937. 2, Accumulator Pressure Power SupplyPQ-937

CP-937.1, Accumulator Pressure TransmitterPT-937

90

90

90

2558 CP-936.4, Zoop A Accumulator Pressure LocalIndicator

90

2557

2556

2555

2553

2552

2551

CP-936. 3, Accumulator Pressure ChannelBistable PC-936Ajh

CP-936.2, Accumulator Pressure Power SupplyPQ-936

CP-936.1, Accumulator Pressure TransmitterPT-936

CP-935.3, Accumulator Level Indicator LI35

CP-935. 2, Accumulator Level BistableLC-935~

CP-935. 1, Accumulator Level TransmitterLT-935

90

90

90

90

90

90

-109-


2630

2634

2622

CP-2092.0, Calibration and/or Maintenance of2092 Atmospheric Belief Valve 1A (CV-56) Control

CP-2093.0, Calibration and/or Maintenance of2093 Atmospheric Relief Valve 1B (CV-57) Control

CP-950.0, Calibration and/or Maintenance ofContainment Pressure Channel 950

90

90

90

2614 CP-949.0, Calibration and/or Maintenance ofContainment Pressure Channel 949

90

2590 CP-946.0, Calibration and/or Maintenance ofContainment Pressure Channel 946

90

2598 CP-947.0, Calibration and/or Maintenance of-Containment Pressure Channel 947

90

2606

2550

CP-948.0, Calibration and/or Maintenance ofContainment Pressure Chanenl 948

CP-93S.0, Calibration and/or Maintenance ofAccumulator Level Channel 935

90

90

2554 CP-936.0, Calibration and/or Maintenance ofAccumulator Pressure Channel 936

90

2559

2564

CP-937.0, Calibration and/or Maintenance ofAccumulator Pressure Channel 937

CP-938.0, Calibration and/or Maintenance ofAccumulator Level Channel 938

90

90

2568 CP-939.0, Calibration and/or Maintenance ofAccumulator Level Channel 939

90


90


90

2546

2639

2646

CP-920. 0, Calibration and/or Maintenance 920Refueling Water Storage Tank Level


S-12.4, BCS Leakage Surveillance RecordInstructions

90

90

90

-110-


2545

2548

2641

2644

2645

2643

S-26.1, Gomputer Program Check

M-38.9, 1B1 Battery Charger Maintenance orRepair

PT-5. 40, Process Instrumentation ReactorProtection Channel Trip Test (Channel 4)

RD-2, Containment Purge Release

HP-10.1, Quality Control of Counting Systems

HP-10.6, Calibration of the LiquidScintillation Counter

90

90

90

90

90

90

2649

2549

2647

2640

2654

2655

2530

2507

2511

2508

2510

2509

2638

HP-7.4, Calibration of Neutron SurveyInstruments

HP-1.2, External Exposure Limits

A-19, Changes in Written Procedures

M-51.3, Non-Controlling Relay Replacementfor K',39X

T-14A, Feedwater Heaters Valve Alignment

T-5A, Condensate System Lineup, Chargingand Venting

T-6.9, Condensate Polishing Mixed BedDemineralizer Units: Bed Startup Operationand Bed Removal frcm Service Operation

CP-209.5, Calibration and/or Maintenance ofRMS Ratemeter for Channels R-8, R, and R-23 through R-28

CP-222.0, Calibration and/or Maintenance ofRMS Channel

CP-222.1, Calibration of Ratemeter DrawerR-22


CP-222.3, Replacement of Detector for R4SChannel R-22

SM 78-1657.1, Installation of 42" Duct forControl Room Ventilation

90

90

90

90

90

90

90

90

90

90

90

90

90

PCN 5 78

f

Procedure a Title Meetin N 78

2671 M-ll.4.10, Charging Pump Gear ReducerInspection

91

2704 PZ-2. 5, Air Operated Valves, QuarterlySurveillance

93

All of the above items were reviewed by the Committee with respect to theTechnical Specifications and the Committee has determined that no TechnicalSpecification changes or violations were involved in the changes and there areno unresolved safety questions.

-112-

S stem Modification SM 77-1449

System Modification SM 77-1449, Diesel Fire Pump Heater. This rxx3ificationinvolved installation of a water heater on the Diesel driven Fire Pump.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is not necessary.

S stem Modification SM 75-9.24

System Modification SM 75-9.24, EST Jet Shielding Installation Rework. Thisprocedure included the steps necessary to rework the jet shields near theRefueling Water Storage Tank for GSM-14.



System Modification SM 77-1474, RC Pump Seal Bypass. This mxlificationincluded the relocation of the RC Pump Seal Bypass lines as recommended kyWestinghouse.

A Safety Evaluation was performed .and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating Technical-Specifications is not necessary.


System Modification 75-47.30, Rework of CVCS Hangers Inside Containment. Thisprocedure involved the reworking of the CVCS Hangers for GSM-3.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is mt recessary.


System Modification SM 75-5.40, Standby Auxiliary Feedwater System. ReworkInside Containment. This procedure involved reworking of the pipe supports onthe 3" Standby Auxiliary Feedwater Piping, in mnjunction with: procedureSM-75-5.24.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is not racessazy.

-113-


System Modification SM 77-1498.1, Low Power S/G Peedwater Bypass ControlModification. This procedure included modifying the feedwater bypass valvecontrol circuitry for low power steam generator level control.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecif ications is not necessary.


System Modification SM 78-1485, Dillon Load Cell Stand. This rmdificationinvolved installation of the Dillon Load Cell Stand.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecif ications is not rmcessary.


System i%ddification SM 78-1845, Guide Stud Storage Rack. This edificationinvolved installation of a new Guide Stud Storage Rack in the reactor cavity.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant ~rating TechnicalSpecifications is not recessary.


System Modification 78-'1865, "A" Steam Generator Air &ver Restraint. Thismodification involved installation of an "A" Steam Generator Air MoverRestraint.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant ~rating TechnicalSpecifications is not necessary.


System Modification SM 78-1480, "A" Reactor Coolant Pump Handrails. Thismodification involved the installation of the "A" Reactor Coolnat PumpHandrails


/I

I

/

-114-


System Nodification SN 78-1464, Volume Control Tank and Accumulator Level.This nodification involved installation of h ~roved Volte Control Tank andAccumulator Level control instruments.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not incre'ased. A change in the Plant Operating TechnicalSpecif ications is not necessary.


System Modification SM 78-2160, GSM 7 Pipe Supports. This rxxlificationinvolved the installation of the GSM 7 Pipe Supports on the AuxiliaryFeedwater Piping.



System Modification SM 77-1877, RCP Anti-Rotation Pins. This mxiificationinvolved the installation of the RCP Anti-Rotation Pins.



System Modification 77-13.2, Inspection of Containment Antenna Coaxial Cable.This procedure involved inspection of the Containment antenna maxial cablewhich has already been installed.



System Modification SN 78-1873, Pressurizer Jib Crane Extension. Thismodification involved installation of the Pressurizer Jib Crane Extension.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Cperating TechnicalSpecifications is not necessary.

-115-


System Modification SM 77-10.3, Containment Personnel Hatch Hinge AssemblyModification Inner Hatch Door. This procedure required adding bearingsupports to the upper main hinge shaft of the Inner Personnel and EquipmentHatch dcors of the Containment Vessel.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is not necessaxy.


System Modification SM 76-21.5, Battexy Room Air Conditioning —Service WaterPiping Installation. This procedure involved installation of the servicewater piping and associated hangers for the battexy room air conditioner.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is not necessaxy.


System Modification 76-21.4, Battery Rxm Air Conditioning —Air ConditionerDischarge Duct South End of Battery Room. This procedure involvedinstallation of the hangers, ductwork and danpers required for the dischargeof the air conditioning unit.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant ~rating TechnicalSpecifications is not necessaxy.


System Modification SM 76-21.6, Battexy Room Air Conditioning —Air SupplyDuct to the'Air Conditioner. This procedure involved installation of thehangers, ductwork and dampers required for the air supply to the airconditioner. This installation was for the ductwork in the air handling roomup to and including the fire damper in the wall between this room and theturbine building.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is .not increased. A change in the Plant Cperating TechnicalSpecifications is not necessary.

S stem Modification. SM 77-1623.1

System Modification SM 77-1623.1, Charging Pump Monorail Installation. Thisprocedure involved installation of the mnorails above the three chargingpumps to facilitate removal and installation of the pumps.

A Safety Evaluation was performed and it was determined that the possibilityof an, accident is not increased. A change in the Plant Operating TechnicalSpecif ications is not necessary.

-116-

S stem Modification SM 77-1832A.lI

System Modification SM 77-1832A.1, Circuit Separation Fuse Installation. Thisprocedure involved installation of fuses to protect electrical circuits frcmadjacent fires.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is mt increased. A change in the Plant Operating TechnicalSpecifications is not necessary.


System Modification SM 77-1057.1, Relocation of the Charging Pump Filter Vent.This procedure involved the relocation of the charging pump filter vent fromthe inlet side of the 3" hypos valve to the discharge side.


S stem Mcdification SM 78-1048

System Modification 78-1048, Accumulator Relief, WR 1048. This rmdificationinvolved installation of a new hanger on relief lines from the accumulators.



System Modification SM 77-1660.23, RCS Overpressure Protection Loop 452 HackR2 Instrumentation Installation and Wiring. This procedure included theinstallation and wiring of the 452 loop power supply, alarm, test points,lights and test switches in the R2 protection rack.



System Modification SM 77-1660.24, RCS Overpressure Protection Loop 455 HackW2 Instrumentation Installation and Wiring. 'Ihis procedure included theinstallation and wiring of the 455 loop power supply, alarm, test point, testswitch and light in the W2 protection rack.


-117-


System Modification SM 77-1660.25, KS Overpressure Protection Loop 456 RackR2 Instrumentation Installation and Wiring. This procedure included theinstallation and wiring of the 456 loop power supply, alarm, test point, testswitch and light in the R2 protection rack.



System Modification SM 77-1660.26, BCS Overpressure Protection Loop 409 RackRCS 2 Instrumentation Installation and Wiring. This procedure included theinstallation and wiring of the 409 loop alarm bistable in the RCS 2 rack.



System Modification 77-1660.27, RCS Ovexpressure Protection Loop 410 Rack KS2 Instrumentation Installation and Wiring. This procedure included theinstallation and wiring of the 410 loop alarm bistable in the KS 2 rack.



System Modification SM 77-1660.28, KS Overpressure Protection Modification ofthe Relay Racks. This procedure included the installation and wiring of therealy racks to be used for the overpressure protection rrodification.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is mt necessary.


System Modification R4 77-1660.29, BCS Overpressure Protection bkx3ificationAnnunciator Termination. This procedure included the installation and wiringof the annunciators which will be used for the overpressure protectionmodification.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant ~rating TechnicalSpecifications is mt necessary.

-118-


System Modification SM 77-1660.21, RCS Overpressure Protection Loop 450 RackB2 Instrumentation Installation and Wiring. This procedure included theinstallation and wiring of the 450 lcop power supply, alarm, test point, testswitch and light in the B2 protection rack.



System bkxlification SM 77-1660.22, KS Overpressure Protection Loop 451 RackW2 Instrumentation Installation and Wiring. This procedure included theinstallation and wiring of the 451 loop power supply, alarm, test points,lights and test switches in the W2 proctection rack.



System Modification 76-26.4, Installation of 7.5 KVA Floor Wunted ConstantVoltage Transformer 1B. This procedure involved replacing the existingconstant voltage transformer with new solid state controls unit using existinginstalled wiring.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating Techriical

" Specifications is not necessary.


System Modification SM 76-21.7, Battery Room Air Conditioning —Miscellaneous.This procedure involved pouring the concrete pad, installing dampers andmaking necessary wiring connections.



System Modification SM 76.26.2, Installation of 1B Inverter and AlternatePower Supplies. This procedure involved replacing the existing inverter andmanual transfer alternate power supply with a new solid state inverter/staticswitch, automatic transfer to C.V.T. alternate power supply (and maintenancesupply to instrument Bus 1B, if applicable).

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant ~rating TechnicalSpecifications is mt necessary.

-119-


System Modification SM 76-26.3, Installation of 7.5 KVS Flow Mounted Constant,Voltage Transformer 1A. This procedure involved replacing the existingconstant voltage transformer with new solid state controls unit using existinginstalled wiring.

A Safety Evaluation was performed and it was determined that the possibilityof an'accident is not increased. A change:in the Plant Operating TechnicalSpecif ications is not. necessary.


System Modification SN 76-26.1, Installation of 1A Inverter and AlternatePower Supplies. This procedure involved replacing the existing inverter andmanual transformer alternate power supply with a new solid stateinverter/static switch, automatic transfer to C.V.T. alternate power supply(and maintenance supply to Instrument Bus lA, if applicable).



System Modification 77-1682.1, Penetration Testing Rxlification —Penetration304. This procedure involved the installation of hanger PA 401 and necessarypiping modifications on Penetration 304.


S stem Modification-SM 76-27.1

System Modification SM 76-27.1, Penetration 332 Modification. 'his procedureinvolved installing hanger PA 401 and necessary piping mx3ifications onPenetration 332.


S stem Modification SM 76-11.10f.

System Modification SM 76.11.10, No. 12B Auxiliary Transformer Deluge SystemTie-In. This procedure involved installing the tie-in to the "B" DelugeHeader for the No. 12 Auxiliary Transformer deluge system. 'Ibis tie-inincludes the elbow, the "6" pipe, the blind flanged 6" x 4" x 6" tee and the4" gate valve.


-120-


System edification R4 77-1682.4, Penetration Testing Modification Penetration107. This procedure involved installing hangers PA 407 and PS 408, andnecessary piping nadifications on Penetration 107.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is mt increased. A change in the Plant Operating TechnicalSpecifications is not necessary.


System Modification SM 77-1682.2, Penetration Testing Modification Penetration202. This procedure involved installing hangers PA 409 and PA 410 andnecessary piping rmdifications on Penetration 202.



System edification 77-1682.3, Penetration Testing Modification —Penetration210. This procedure involved the installation of hangers PA 402,PG 403 and PA404 and necessary piping modifications on Penetration 210.



System Modification SM 77-1660.2, Overpressurization Mechanical Package. Thisprocedure involved installing piping, valve piping hangers and accumulatorvessels for the RCS overpressurization modification.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased., A change in the Plant Operating TechnicalSpecif ications is not accessary.


System Modification SM 76-01.1, Safeguard Buses DC Gontrol Voltage Ronitor.This procedure involved installation of necessary relays and terminations forthe safeguard buses DC Control Voltage 8onitor.


-121-


System Modification SM 77-1660.10, RCS Overpressurization ProtectionElectrical Conduit and Wiring. This procedure involved installation andfabrication of mnduit, conduit supports and wire/cable .excluding terminationsfor RCS Overpressurization Protection. System.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is mt necessary.


System Modification SM 77-2.10, D.I. Water Containment Isolation —ElectricalConduit and Wiring. This procedured involved fabrication and installation ofconduit, conduit supports and wire/cable excluding terminations for the D.I.Water Containment Isolation Valve.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is mt increased. A change in the Plant Operating TechnicalSpecifications is mt necessary.


System Modification 78-2273.1, Armor Plate on the East Wall of the ControlRoom. This procedure involved the installing anger plate and necessarystructural steel on the east wall of the Control Rocm.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecif ications is not rmcessary.


System Modification SM 77-02.1, D.I. Water to Contaiment i%ddificationMechanical. This procedure involved installing valves, piping and pipinghangers on the demineralized water line going to Containment.


S stem Mcdification SM 78-1048.1

System Modification SM 78-1048.1, Accumulator Relief Modification. Thisprocedure involved installation of a new hanger on the 1" relief line fromboth accumulators and cut off the relief valve discharge lines before theelbow.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is mt increased. A change in the Plant Cperating TechnicalSpecifications is not recessary.

-122-


System Modification SM 78-2273, Armor Plate —East Wall of Control Room.This reification involved installation of armor plate on the East Wall of theControl Room.

A Safety Evaluation was per'formed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is not necessary.


System Modification SM 78-1875.1, "A" Feedwater Venturi Monorail. Thisprocedure involved fabrication and erection of a nnnorail above the "A"Feedwater Venturi.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecifications is not accessary.

S stem Mcdification SM 78-1480.1

System Modification 78-1480.1, "A" RCP Ladder and Handrail Installation.This procedure involved erection of handrails, ladders and miscellaneous steelby the "A" Reactor Coolant Pump.



System Modification SM 78-1890.1, Feedwater Line Drain Valves Before theContainment Check Valves. This rxxlification involved the installation of adrain line and valve on each feedwater line before vlaves 3992 and 3993.



System Modification SM 77-1474.1, RCP Seal Bypass Modification. Thisprocedure involved relocating the 41 Seal ~s piping and necessary hangerson the Reactor Coolant Pumps.


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System Modification SM 75-14, Boric Acid Batch Tank Recirculation Piping andSupports. '1%is modification involved installing the necessary piping, valvesand hangers to allow the transfer of boric acid from either storage tank tothe batch tank.



System Modification SM 78-1485.1, Dillon Cell Storage Frame. 'Ibis procedureinvolved the fabrication and installation of platform aadifications for theDillon Cell Storage frame.

A Safety Evaluation was performed and it was determined 'that the possibilityof an accident is=not increased. A change in the Plant Cgerating TechnicalSpecifications is not necessary.


System Modification 78-1845.1, Guide Stud Storage Racks. This procedureinvolved the fabrication and installation of the Guide Stud Storage Racks onthe wall of the Refueling Cavity.



System Modification SM 78-2160.1, GSM-7 Pipe Supports. This rxdificationinvolved the fabrication and installation of the GSM-7 Pipe Supports on theAuxiliary Feedwater Piping.



System Modification SM 76-28.2, Flange Installation on Feedwater Flow Venturis— "A" Feedwater,Line. This procedure involved installation of flangesupstream and downstream of the main feedwater flow venturis on the "A"Feedwater line.


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System Modification SM 75-5.50, Auxiliary Feedwater Hanger AEN-51 Repair.This procedure involved repairing Hanger AEW-51, including rermval of someexisting structural rremkers and replacement with new materials.



System Modification SM 76-01.2, Cable Installation for the DC Control Fuses.This procedure involved installation of the cable for the D.C. Control Fusesexcluding terminations.



System edification 77-1660.15, Instrumentation Tie-Ins for RCSOverpressurization. This procedure involved miscellaneous instrumentationinstallation on the new RCS overpressurization N2 piping to describe the stepsnecessary to make the tie-.in to the instrument air in mntainment and todescribe the steps necessary to make the tie-ins for the new loop pressuretransmitters onto the exis'ting flow transmitter takeoffs.


S stem Mcdification SM 78-1865'.1

System Modification SM 78-1865.1, Steam Generator "A" Air lUver Installation.This procedure involved fabrication and installation of the air naver holdingframe.



System Modification SM 78-1873.1, Pressurizer Jib Crane. This procedureinvolved fabrication and installation of the Pressurizer Jib Crane Extension.


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System Modification SM 77-1660.11, RCS Overpressurization Protection—Electrical Terminations in the Control Room and in the Field. This procedureinvolved instructions necessary to make, cable terminations on new eguipnentinstalled in the field and on new equip"ent installed in the Control Room.This does not include terminations in the racks.



System Modification SM 77-02.2, Hydrostatic Testing and Initial Service LeakTest of the Demineralized Water to Gontainment Modification. Wis prooedureinvolved testing the new piping installed using SM 77-02.1.


S stem Modification SN 77-1682.10

System Modification 77-1682.10, Hydrostatic Testing of Penetration 143 PipingModification.. This procedure involved testing the piping mxiificationsinstalled using SM 77-1682.5.



System Nodification SM 77-02.12, Cemineraalized Water Containment Isolation.This procedure involved rmunting relay C14X, install rack wiring in SIA2 andSIB2 racks, and terminate field wires at SIA2 and SIB2 racks.



System Nodification SN 77-1660.100, Pneumatic Testing of the KS OverpressureProtection System. This procedure involved performing pneumatic tests on theRCS oyerpressure protection system.


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System Modification SM 77-02.20, Checkout Testing of the Containment DI WaterAutomatic Isolation Valve 8418. This procedure involved verifying properoperation and installation of valve 8418.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Cgerating TechnicalSpecifications is not necessary.


System Modification SM 77-02.15, Air Tie-In for the DI Water to Containment.This procedure involved tying in the instrument air for Valve 8418.



System Modification 77-02.11, Electric Termination of Valve 8414 and in theControl Room for DI Water to Containment. This procedure involved making theelectrical terminations at the Containment DI Automatic Isolation Valve 8418and to describe the steps necessary to install necessary switch and lights inthe control board and make necessary terminations. This does not includeterminations covered kp B4 77-02.12.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecif ications is rmt necessary.


System Modification SM 78-1888.1, Spray Additive Tank Recirc. Line ShutoffValve Installation. This procedure involved installation of a shutoff valveand nipple on an existing plug connection for the spray additive tank recirc.line.



System Modification SM 76-26.5, Installation of 7.5 KVA Floor Munted ConstantVoltage Transformer Backup Supply for Instrument Buses A-B-C a D. Thisprocedure involved replacing the existing transformer with new solid statecontrols unit using the existing installed wiring.


l)

II

I

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System Modification SM 75-50.30, Rework of Jet Shielding for Main Steam BypassPiping and Valves. This procedure involved rework of the jet shielding forthe main steam ~s piping and valves.



System Modification SM 77-1020.1, Neutralizing Tank Modification. Thisprocedure involved allowing recirculation mde of the neutralizing tank pumpand to prevent discharge from the neutralizing tank when there is a pH alarmfrom the retention tank.



System Modification 77-1449.1, Diesel Fire Pump Heater. This procedureinvolved installing an engine coolant heater and an engine coolant filter tothe Diesel Fire Pump.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating, TechnicalSpecifications is not necessary.


System Modification SM 78-1458.1, Spent Fuel Pit Roughing Filter Frame.This procedure involved the installation of spent fuel pit roughing filterframes.



System Modification SM 77-1405.1, Installation of Conduit for Security System.This procedure involved installation of conduit for the Security System andprovided a procedure to control Q.A. aspects of the rredification.


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System Modification SM 76-17.3, Screenhouse Intake Heater Cable Tray Rework.This procedure involved installation rework of Hilti Fastenings to NuclearSafety-Related structural steel by a power actuated fastening tool perNCR~78-57

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecif ications is not. necessary.


System Modification SM 76-18.1, Waste Condensate Pumps, Monitor Tank Pump andLaundry Pump Rotor Controller Nx3ification. This procedure involvedmodifications to ensure that a liquid release is terminated if R-18 Monitordetects high activity.



System Nxlification 77-2110.1, Chem Lab D.I. Storage Tank Cable Routing. Thisprocedure involved providing tank level indication at the D.I. Plant ControlPanel.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant ~rating TechnicalSpecifications is not necessary.


System Modification SM 75-50.31, Jet Shielding Rework, Main Steam andFeedwater. This procedure involved documenting the work required to correctopen items from NCR~77-139. These were incomplete items from SM 75-50.21for GSM-8.



System Modification RI 77-1836.3, Relocation of Hangers SWXH 38 and 39. Thisprocedure involved relocating Service Water Hangers BFJH 38 and 39.

A Safety Evaluation was performed and it was determined that the possibilityof an accident is- not increased. A change in the Plant Operating TechnicalSpecif ications is not necessary.

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System Modification SM 76-11.21, 12B Transformer Grinnel Valve Alteration.This procedure involved altering the position of Grinnel Multi-matic ValveModel A-4 for. the 12B Auxiliary Transformer Deluge System so that lockingwater is on the inlet side of the O.S. a Y. Valve.



System Modification SM 75-5.43, Final Rework for Standby Auxiliary Feedwater.This procedure involved resolving all known remaining deficiencies associatedwith the installation of GSM-16, Standby Auxiliary Feedwater System. Also,this describes the rework necessary to completely resolve NCR~77-131.



System Modification 75-14.1, Batch Tank Recirculation Heat Trace Installation.This procedure involved installation of a permanent heat trace on the BoricAcid Batch Tank Recirculation Piping.

A Safety Evalu'ation was performed and it was determined that the possibilityof an accident is not increased. A change in the Plant Operating TechnicalSpecif ications is not necessary.

S stem Modification SN 74-28.1

System Modification SN 74-28.1, Installation of Makeup Lines to CondensateStorage Tanks. This procedure involved installation and return to service ofthe new makeup line for the Condensate Storage Tank.



,System i~ification .SN 78-1657.1, Installation of 42" Duct for Control RoomVentilation. This procedure involved fabrication of hangers and installationof the 42" duct for Control Rocm Ventilation.


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System Modification SN 77-1663.1, Spent Fuel Pit Wall Temperature hhnitor.This procedure involved installation of a temperature nanitor for the SpentFuel Pit/Refueling Canal Wall.


Annual Operating Rept 1978.

Documents

Transcript of Annual Operating Rept 1978.