ML17244A797

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Annual Operating Rept 1978
ML17244A797
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/31/1978
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17244A798 List:
References
NUDOCS 7909050478
Download: ML17244A797 (172)


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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@

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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

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PCN 4 78 Procedure a Title Meetin g 78 Ol QC-1502, Nonconformance Reports 02 02 QC-1701, Quality Assurance Records 02 05 QC-401, Control of Procurement Documents for 02 Purchased Material, Parts, Components and Services 04 ET-19, Test of Accoustical Leak Monitoring 03 System for Ginna Safety Injection Piping 03 PZ-2.3, Safeguard Valve Operation 03 06 A-30. 2, Plant Procedure Classification Review, 03 Approval and Distribution Requirements 22 M-55.5, Full Length Rod Control System Drive 04 Mechanism Operating Coils Polarity Check 27 M-51.4 Performance Check of Latch Mechanism for 04 Relay LC-171CX 31 EM-197, Repair of Weld on "B" Charging Pump 05 Discharge Line to Relief Valve 284 17 A-52.4, Control of Limiting Conditions for 06 Operating Equipment M-ll.4.4, Charging Pump Varidrive Belt Reneval 07 and Installation 07 ~

EM-19 Inspection and Maintenance on 14" Pratt 07 Butterfly Valve Operator Only Valve 4562 (Containment Recirculation System Cooling Water Return Line) 21 M-18.2, Waste Evaporator Feed Tank Float Valve 07 Maintenance 32 E-l.l, Safety Injection System Actuation 07

,23 A-50.11.3, Fire Watch/Escort Training 07 29 A-50.11.4, General Employee Fire Training 07 14 A-50.3, Preventive Maintenance Program 07 0-6-7-1, Plant Alarm Panels Test 07 18 0-6.4, Core Quadrant Power Tilt Calculation 07

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PCN I 78 Procedure 6 Title Meetin I 78 15 0-6.1 Plant Operation with S/G Tube Leak Indi- 07 cation 24 S-3.2G, Transfer of Boric Concentrates 07 SC-3.17.1, Planning Conduct and Evaluation of 07 a Fire Emergency Drill 28 QC-401, Control of Procurement Documents for 07 Purchased Material, Parts, Components and Services 19 RSSP-2.3, Emergency D/G Annual Trip Testing 07 34 O-l. 1C, Pre-Critical Technical Specif ication 07 Check Sheet 12 (g-1021, Calibration and Control of Test +uip- 07 ment 08 GS-21.0, Site Access Control (Security) and 07 Personnel Identification 33 A-61, Method of Evaluation for Reporting Require- 07 ments in Basic Components Under 10 CFR 21 35 M-55.5, Full Length Rod Control System Drive Mechan- 07 ism Operating Coils Polarity Check 36 GS-31. 0, Door Alarm System 07 09 GS-20.0, Classification of Ginna Station Photo 07 ID Cards and Non-Photo Badges 37 PT-4, Residual Heat Removal Loop Annual Hydro 07 Test of Law Pressure Piping 40 CP-44.2, General Reinstate Procedure for N-44 08 41 PT-16, Auxiliary Feedwater System 08 26 M-ll.4.9, Charging Pump Varidrive Belt Removal and Installation 08 39 SC-1.12B, Station Call List 08 43 M-37.16A, Manually Cperated Grinnell Diaphragm 08 Valve Maintenance

PCN 0 78 Procedure & Title Meetin 578 30 RSSP-12, Testing of Primary and Secondary Relief 08 Valves on Test Stand 47 RD-9, Preparing Waste for Shipment or Storage 08 48 RD-10, Shipping Radioactive Material 08 46 0-5.2, Load Increases 08 79 0-1.1C,'re-Critical Technical Specif ication 09 Check Sheet None SM 78 1458 g Auxiliary Building Holding Frame 10 Filter None SM 78-1845, Guide Stud Storage Rack 10 None SM 78-1865, "A" Steam Generator Air Mover 10 Restraint None SM 78-1480, Auxiliary Reactor Coolant Pump 10 Handrails None SM 78-1464, Volume Control Tank Level 10 (Accumulator Level)

None SM 78-2160, GSM 7 Pipe Supports 10 81 S-25.4, Processing Water from Either S/G 10 62 & 65 S-4.5, Sluicing Water Condensate Polishing 10

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Demineralizer Spent Resin to Shipping Cask 63 CP-930.0, Calib. and/or Maint of Spray Additive 10 Tank Inlet Flow Transmitter Loop 64 CP-424.3, Calib. and/or Maint. of Pressurizer 10 Liquid Temp. Indicator TI-424 51 HP 4.3, Work Permit Use 10 42 PC-18.3, Determination of Chloride ky Specific 10 Ion Electrode 45 S-27.294/296/392A, Isolation Procedure for AOV-294, 10 AOV-296 or AOV-392'P-12.6, 77 Issuance, Proper Use and Return of Respira- 10 tors

PCN 5 78 Procedure 6 Title Meetin 5 78 60 A-52.4, Control of Limiting Conditions for Operating 10 Equipment 52 A-53.1, Equipment Inspection Period and Lubricant 10 List 54 A-53.0, Preventive Maintenance Program 10 69 A-49, Station Security 10 53 A-53.2, three &anth Lubrication and Maintenance 10 Inspection 55 PT-2.8, Component Cooling Water Pump System 10 74 PT-13.1.13, Deluge Valve System Testing System 10 Numbers 1, 2, 11 ~

75 PI'-13.1.5, Flood Valve System Testing System 10 Numbers 3, 4, 5, 6 82 PT-17.1, Area Radiation Monitors 10 84 A-58, Installation of Power, Control or Instru- 10 mentation Cables at Ginna 44 M-37. 3, Maintenance on Copes-Vulcan Diaphragm 10 Operated Control Valves for AOV-58 a 59 GS-18.1, Conduct of cn-the-job Training of 10 Guards 61 GS-9.0, Walkie-Talkie Procedure for the Security 10 Force 67 GS-30.0, 'Ihreatening Phone Call or Bomb 10 Threat'rocedure 68 GS-32. 0, Civil Disturbance Procedure 10 66 GS-3.0, Security Call List 10 76 PC-14.1, Boron in WEFI and WHVZ Waters 10 None Liquid Waste Release 567 70 0-6.10, Plant Operation with Steam Generator Tube Leak Indication 81 S-25.4, Processing Water from Either Steam Generator

PCN I 78 Procedure a Title Meetin I 78 91 103

'Z-2. SN 5, Air Operated Valves, Quarterly Surveillance 77-13.2, Inspection of Containment Antenna 12 Coaxial Cable Q=-603, Control of Drawings 12 88 A-55.1, Field Change Requests to Engineering 12 Documents 109 (g-105, Indoctrination and Training of Modifica- 12 tion Project Personnel 108 QC-402, Control of Procurement Documents for 12 Materials and Services Purchased by the Ginna Modification Project 85 QC-606, Control of Engineering Documents 12 123 QC-304, Control of Modification Activities by the 12 Ginna Modification Project 87 9 -202, Modification Project Organization 100 0-1.1, Plant Heatup From Cold Shutdown to Hot 12 Shutdown 101 PZ-7, Hydro Test of Reactor Coolant, System 12 102 0-2.2, Plant Shutdown From Hot Shutdown to Cold 12

. Shutdown 104 RD07, Liquid Waste Release 12 138 EH-154, Steam Generator Handle Cover 12 Gasket Leak Repair Using "Furmanite" Process 139 T-7C, Regeneration of Cation-Anion DI Unit 12 94 S-3.3A, Coolant Chemistry Addition Tank 12 97 EM-198, Replacement of the Buchanan Terminal 12 Blocks for Pressurizer Pressure and Level Trans-mitters Terminations with a Westinghouse Style N542247 Terminal Block 106 PZ-2.4, Cold Refueling Motor Operated Valve Sur- 12 veillance

PCN ¹ 78 Procedure 6 Title Meetin ¹ 78 107 S-2.4A, Draining the Pressurizer (RCS Degassed) 12 24 S-3.3A, Coolant Chemistry Addition Tank 12 121 W-101, Ginna QA Program Implementation 12 95 GS-l. 2, Security Event Report 12 83 A-30.3, Plant Procedure Content and Format 12 Requirements 0-6.11, Routine Operations Check Sheet 12 110 E-1.2, Zass of Coolant Accident 12 90 PT-2. 6, Cold/Refueling Shutdown Air Operated Valve Surveillance 89 PZ-2.5, Air Operated Valves, Quarterly Sur- 12 veillance 105 PT-6. 2, NIS Intermediate Range Channels 12 98 PT-23.14, CV Air Sample Inlet 12 99 PT-23.20, BC'as Header 12 49 M-29, Decontamination of R-18 Liquid Sampler 12 126, 129 & 0.2, Main Control Board System Status 12 141 Verification S-27.2776, Isolation of Valve 2276 13 114 S-3.1M, Isolation of Batching System 13 120 S-27.2, Isolation of CVCS Letdawn Demineralizers 13 and Associated Valves 119 S-27.164SA, Isolation of Waste Evaporator Return 13 Valve 1654A 115 S-3.2J, Isolation of Reactor Coolant Filter and 13 Associated Grinnell Diaphragm Valves (249, 250, 251, 248A 248B) 118 S-27.245, Isolation of Mixed Bed Demineralizer Bypass 13 Valve 245

Procedure a Title Meetin I 78 S-27.1610B, Isolation of Demineralizer Drain 13 Valve 1610B 153 GS-26.1, Unoccupied Vital Area Key Control and 13 Accountability 132 S-3.1G, Isolating, Flushing and Draining the 13 "A" Boric Acid Storage Tank for Major Valve Tank or Piping Maintenance and Inspection 131 0-2.2, Plant Shutdown for Hot Shutdown to Gold Shutdown 130 0-2.4, Plant Shutdown from Hot Shutdown to Cold 13 Shutdown During Blackout 128 0-5.1, Load Reductions 127 0-5.2, Load Increases 0-6.9, Operating Limits for Ginna Station Trans- 13 mission 149 M-37.3.2, AOV-296, Auxiliary Spray to Pressurizer 13 Maintenance 155 M-37.3.1, Maintenance Isolation Procedure for V-294 Charging Line to Cold Leg Loop "B" 140 S-3.4, Boron Recycle Process Operation 13 148 HP-3.1, Exposure Reports to Individuals and 13 NRC 152 HP-8. 4, Radioactive Source Inventory 13 151 PT-2.3.1, Post Accident Charcoal Filter Damgers 136 M-53, Containment Air Locks Inspection 13 135 M-40. 7, Steam Generator, Snubber Maintenance Snubber 5

144 M-37.2, Maintenance of Pressurizer Relief Valve 13 Guards 162 GS-21.2, Unoccupied Vital Area Access Control 13 161 GS-5.0, Security Guard General Instructions 13

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PCN 0 78 Procedure a Title Meetin 5 78 147 RF.O, Site Removal of New Fuel Assemblies 13 from Shipping Containers and Handling of Shipping Containers 157 HP-1.1, Issuing Personnel Dosimeters 14 158 HP-1.3, External Exposure Records 150 T-27.6, Diesel Fuel Oil Transfer Pump Isolation 14 145 T-27.4, Diesel Generator Operation 14 170 M-73.3, Welding on Carbon Steel Piping and Com- 14 ponents 183 PT-16, Auxiliary Feedwater System 14 173 a Reinstallation of Steam Generator Blowdown 14 175 Restraint, SGB-28 165 SM 76-21.5, Battery Room Air Conditioning-Service 14 Water Piping Installation 156 SM 76-21.4, Battery Room A'ir Conditioning-Air 14 Conditioner Discahrge Ducts, end of Battery Room 169 SM 76-21. 6, Battery Room Air Conditioning-Air 14 Supply Duct to the Air Conditioner 187A SM 77-1832. 1, 24 179 CP-31.0, Calibration and/or Maintenance of Source 14 range N-31 178 CP-32.0, Calibration and/or Maintenance of Source 14 Range N-32 160 SC-1.12A, Immediate Call List 14 159 SC-1.12B, Station Call List 14 174 A-61, Method of Evaluation for Reporting Requirements 14 in Basic Corrponents Under 10 CFR 21 172 HP-6.2, Posting of Contaminated and Airborne Areas 14

PCN 5 78 Procedure 6 Title Meetin 5 78 181 CP-31.3, Calibration of Source Range N-31 14 180 CP-32.3, Calibration of Source Range N-32 14 166 PC-l.l, Analysis Schedule and Limits Primary 14 Coolant 189 A-54.3, Open Flame, Welding and Grinding Permit 78 SM 77-1057.1, Relaocation of the Charging Pump 15 Filter Vent 167 M-48.3, Isolation and Restoration of Bus e15 15 176 T-35F, Steam to Auxiliary Building, Screen House 15 or Diesel Generators and Oil Room 184 T-31.8, Turbine Generator Bearing Drain Vapor Extractor 15 Vent-Hydrogen Loss Calculation 93 HP-12.2, Medical Check, Fitting and Training of 15 Personnel Using Respirators 113 M-11.4.6, Charging Pump Stuffing Box Maintenance 15 112 M-11.4.7, Charging Pump Stuffing Box Assembly Inspection 15 and Maintenance 197 M-37.IA, Repacking of Pressurizer Spray Valves 43IA and 15 431B 192 . M-37.16B, Isolation of Batching System Grinnel 15 Diaphragm Valves 190 M-37.16N, Repair of Demineralizer Drain Valve 1610B 15 191 M-37.16P, Repair of Valve 2276 15 188 GS-5.0, Security Guard General Instructions 15 195 GS-28, Inspection of Personnel, Vehicle and Packages 15 194 , GS-21.0, Site Access Control (Security) and Personnel 15 Identification 193 GS-41. 0, Employee Screening Program 15 154 QC-304, Control of Modification Activities by the 15 Ginna Modification Project

PCN I 78 Procedure & Title Meetin 5 78 194 a GS-21..0, Site Access Control (Security) and Personnel 16 230 Identification 231 GS-5.0, Security Guard General Instructions 16 177 A-60.3, Calibration Survey Program for Instrumentation/ 16 Equipment of Safety Related Components 186 RSSP-15.7, Inservice Inspection Hydro Test of Class B 16 Safety Related Piping 205 .M-37.16Q, Isolation of CVCS Letdmm Demineralizers and 17 Associated Grinnell Diaphragm Valves 206 M-37.16K, V-245 (Mixed Bed Demineralizer Bypass Valve) 17 Isolation Draining and Restoration to Service 204 M-37.16G, Isolation of Waste Evaporator Return Valve 17 1654A 203 M-37.16F, Isolation of Reactor Coolant Filter and 17 Associated Grinnell Diaphragm .Valves 257 T-27.2, lB Emergency Deisel Generator Pre-Start 17 Alignment 250 SM 76-21.5, Battery Room Air Conditioning Service 17 Water Piping Installation 249 QCIP-15, Visual Inspection During Hydro-Static and 17 System Pressure Testing 238 GS-21.0, Site Access Control (Security) and Personnel 17 Identif ication 220 PT-2.7, Service Water System 17 228 GS-26.0, Security Key and Lock Controls 17 223 HP-9.1, Steam Generator Blowdawn Activity 17 221 RD-3, Plant Vent Iodine and Particulate Releas'e 17

-Sampling and Analysis 235 A-l, Radiation Control Manual 17 210 AR/C-3, Accumulator IA Level 17 211 ~C-4, Accumulator 1B Level 17

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PCN O 78 Procedure & Title Meetin 0 78 207 AR/E-27, NIS Power Range Single Channel Lo Range 17 Alert 213 AR/D-20, Pressurizer Lo Pressure 17 208 ~~15, Reactor Coolant Lo Flow Undervoltage 17 Underfrequency Zaop A 214 ~M23, Reactor Coolant Lo Flow Undervoltage 17 Underfrequency Loop B 209 AR/D-10, NIS Power Range Lo Range Reactor Trip 17 215 ~~19, Pressurizer Lo Pressure and Level 17 200 M-73.3, Welding on Carbon Steel Piping or Components 17 201 M-73.2, Welding on Stainless Steel Piping or Components 17 243 QCIP-3, Receiving Inspection of New Fuel 19 242 QCIP-2, Pre-closure Core Verification 19 237 Coor Alarm Assessment and Response

'S-31.1, High 19 Radiation Areas 185 PR-7, Protective Relay Calibration and Trip Test 512A 19 Transformer, 34KV and 4KV Bus Relaying 262 SM 76-21.6, Battery Room Air Conditioning Air Supply 19 Duct to the Air Conditioner 297 PT-7, Hydro Test of Reactor Coolant System 19 300 SM 76-21. 4, Battery Room Air Conditioning Air 19 Conditioner Discharge Duct South End of Battery Room 292 S-3.4B, Gas Stripper Startup 19 266 CP-2.3, Rod Position Indication System "Shutdown" Bank 19 Hot Shutdown Alignment 266 CP-2.3.1, Rod Position Indication System "Shutdown" 19 Bank at Power Alignment

~ 289 A-30.2, Plant Procedure Classification, Review Approval 19 and Distribution Requirements 264 GS-20.0, Classification oj Ginna Station Photo 19 ID Cards and Non-Photo Bactges

PCN N 78 Procedure a Title Meetin N 78 251 A-17, Plant Operations Review Committee Operating 2rocedure 4

240 A-30.3, Plant Procedure Content and Format Requirements 19 288 A-50.11.3, Firewatch/Escort Training 19 270 CP-2.5.0, Bod Position Indication System "A" Bank 19 Hot Shutdown Alignment 269 CP-'2.4.1, Rod Position Indication System "Part Length" 19 Bank at Power Alignment 268 CP-2.4.0, Rod Position Indication System "Part Length" 19 Bank at Hot Shutdown Alignment 265 CP-2.0, Calibration and/or Maintenance of the Rod 19 Position Indication System 299 PT-17.1, Area Radiation Honitors Rl-R9 19 259 PT-13, Fire Pump Operation and System Alignment 19 258 SC-3.15.15, Emergency Fire equipment Locker 19 Inventory and Inspection 279 CP-2.10, Rod Position Indication System Maintenance 19 Calibration Check.

296 CPO. 2, Rotameter Calibration 19 256 RF-8.4, Fuel and Core Component Mvement in the 19 Spent Fuel Pit 305 RSSP-6.0, Containment Integrated Leakage Rate Test 19 283 PT-16, Auxiliary Feedwater System 20 343 A-30.2, Plant Procedure Classification, Review, Approval 20 and Distribution Requirements 344 A-.30.3, Plant Procedure Content and Format Requirements 20 310 SC-3.15.6, Fire Hose Reel Inspection 20 329 A-60.1, Ginna Station Technical Specif ication 20 Surveillance Program

PCN I 78 Procedure a Title Meetin I 78 334 S-3.4J, Transferring Monitor Tank to RMÃ Tank 20 307 E-1.2, Loss of Coolant Accident 20 308 A-25.1,, Ginna Station Event Report 20 312 E-23.5, Reactor Coolant Pump No. 1 Seal Leak-off 20 Lmr Flow or Off 314 ('-8,-Loss of Reactor Coolant Flow 20 313 E-23.1, Malfunction of Il Reactor Coolant Pump Seal 20 298 CP-218.2, Calibration of R-18 Detector 20 395 M-15, Diesel Generator Maintenance 20 30Ci RF-9.8.1, Part Length Control Rod Drive Shaft 20 Unlatching 306 RF-l, Refueling Organization 20 GS-26.1, Unoccupied Vital Area Key Control and 20 Accountability 182 A-l.l, Locked Radiation Areas 20 322 A-5.1, Protective Clothing Locker 20 Locat'P-215.2, 218 Calibration of R-15 Detector 20 336 RSSP-6.1, Integrated Leakage Rate Test Valving Align- 20 ment 337 RSSP-6.2, Presurization Monitoring of Penetration 20 Free Volumes During CV ILRT 143 QC-1402, System and Equipnent Operating Status Control 20 245 QCIP-5, Cleanliness Inspection of Components 20 335 S-3.3G, CVCS Deborating Demineralizer Bed Operation 20 Using "B" Deborating Unit 237 GS-31.1, Door Alarm Assessment and Response Controlled 20 346 ISI-1.8, Quality Control A Inservice Inspection 20 347 ISI-2.6, Quality Control B Inservice Inspection 20

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' PCN N 78 Procedure 6 Title Meetin N 78 348 ISI-3. 5, High Energy Inservice Inspection 20 241 QCIP-1, Quality Control Inspection Procedure Steam 20 Generator (Primary Side) Preclosure Inspection 244 QCIP-4, Quality Control Inspection Procedure Receiving 20 Inspection of NG-6 Type Relays 246 QCIP-9, Quality Control Inspection Procedure Pressurizer 20 Preclosure Cleanliness Inspection 247 QCIP-13, Quality Control Inspection Procedure Material 20 Receiving Inspection of Chemicals and Radio-Chemical Laboratory Supplies 234 RSSP-13.6, Inservice Inspection Hydro Test of Class "C" 20 Safety Related Piping (Auxiliary Feedwater Pumps Discharge Piping) 239 RSSP-15.8, Inservice Inspection Hydro Test of Class "B" 20 Safety Related Piping (Charging Pump Suction excluding VCT) 229 SM 76-16.1, Eddy Current Wiring Conduits 20 395 Rl-200, Replacement or Rework of Solenoid Valves 21 for CV Purge Exhaust Valve 5879 362 S-2.5A, Burping the Reactor Goolant Drain Tank (To Be 21 Opened to Atmosphere) 363 . S-2.5B, Restoring Reactor Coolant Drain Tank to Service 21 After Maintenance 364 S-4.2.10, Burping the Pressurizer Relief Tank and 21 Reactor Goolant Drain Tank and Isolating from the Vent Header 361 SM 76-17.2, Screen House Intake Heater Cable Tray 21 353 SM 76-21.5, Battery Room Air Conditioning Service 21 Water Piping Installation

PCN 5 78 Procedure & Title Meetin " 78 383 SN 77-1660.23, RCS Overpressure Protection Loop 452 21 Rack R2 Instrumentation Installation and Wiring 384 SN 77-1660.24, RCS Overpressure Protection Loop 455 21 Rack=W2 Instrumentation Installation and Wiring 385 B4 77-1660.25, RCS Overpressure Protection Loop 456 Rack R2 Instrumentation Installation and Wiring 386 &1 77-1660.26, RCS Overpressure Protection Loop 409 21 Rack RCS2 Instrumentation Installation and Wiring 387 SM 77-1660.27, RCS Overpressure Protection Loop 410 21 Rack RCS2 Instrumentation Installation.and Wiring 388 SM 77-1660. 28, Overpressure Protection Rxlification 21 of the Relay Racks 389 SN 77-1660.29, Overpressure Protection Rx3ification 21 Annunciator Termination 381 SN 77 1660 21 g Overpressure Protection Loop 450 21 Rack B2 Instrumentation Installation and Wiring 382 SM 77-1660.22, RCS Overpressure Protection Loop 451 Rack W2 Instrumentation Installation and Wiring 399 'lCIP-10, Test Instrument Calibration Procedure 22 412 CP-625.1, Residual Heat Reaaval Heat Exchanger Outlet 22 Valve HCV-625 Isolation 410 PR-6, Protective Relay Calibration and Trip Test 19KV 22 and 115KV Relaying 411 CP-624.1, Residual Heat Removal Heat Exchanger Outlet 22 Valve HCV-624 Isolation 396 RSSP-10.2, Main Steam Safety Valve Test 22 355 S1 75-58.8, Modification of the Walkway and Railings 22

, Around the Spent Fuel Pool 263 A-60.2, Control of Inservice Inspection Status 22 222 PR-2, Protective Relay Calibration and Trip Test 22 1A Emergency Diesel PR-3, Protective Relay Calibration and Trip Test 1B Emergency Diesel

PCN N 78 Procedure a Title Meetin N 78 372 CP-2019.0, Turbine Driven Au-iliary Feeawater Pung 22 Discharge Pressure Loop 2019 374 CP-2030.0, 1B Wtor Driven Auxiliary Feedwater Pump 22 Discharge Pressure Loop 2030 373 CP-2029.0, 3A Motor Driven Auxiliary Feedwater Pump 22 Discharge Pressure Loop 2029 293 M-15.3, Diesel Fuel Oil Transfer Pump Maintenance 22 294 M-15.4, Diesel Startup Air Compressor Maintenance 22 403 M-40.7, Steam Generator Snubber Maintenance 22 406 A-53.2, three anth Lubrication and Maintenance 22 Inspection 413 A-35, Prime Mover Holding and Markup Requirements 22 400 RF-8.1, Step ky Step Fuel Loading and Maps 22 332 GS-12.0, Security Guard Actions During a Fire 22 345 GS-31.0, Door Alarm System 22

'I 380 GS-21.0, Site Access Control (Security) and Personnel 22 Identification 356 GS-28.0, Search of Personnel, Vehicles and Packages 22 354 . PT-5.20, Channel

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Reactor Protection 22 353 RSSP-15.7, Inservice Inspection Hydro Test of Class "B" 22 Safety Related Piping (Charging Pumps Discharge Piping) 342 RSSP-12, Testing of Primary and Secondary Relief 22 Valves on Test Stand 349 Fire Pump Ceration and System Alignment 22 341 SC-1.12A, Inmdiate Call List 22 338 HP-4.1, Controlled Area Entry 22 340 SC-1.12B, Station Call List 22 CP-209, Calibration of Area 8onitors, TA-62 22 Detectors (Rl-R9)

PCN 5 78 Procedure & Title Meetin 5 78 303 RF-2, Reactor Refueling Outage Operations and 22 Activities 302 RF-10, Fuel Transfer System Checkout and Demonstration 22 Procedure 351 A-50.11.4, General Employee Fire Training 22 376 SM 76-26.4, Installation of 7.5KV Floor Mounted 22 Constant Voltage Transformer lB 277 SN 76-21.7, Battery Room Air Conditioning Misc. 22 317 RSSP-13.8, Inservice Inspection Hydro Test of Class IICI1 22 Safety Related Piping (Service Water Piping- Loop A) 260 RSSP-13.7, Inservice Inspection Hydro Test of Class "C" 22 Safety Related Piping (CVCS Holdup Tank Inlet Piping, Gas Stripper Pumps Discharge Piping Including Base Removal and Cation Ion Exchangers Piping) 248 QCIP-14, Quality Control Inspection Procedure Material 22 Receiving Inspection of Mechanical Measuring Tools 252 HP-12.1, Usage of Respirators 22 290 A-54.6, Health Phsyics Tour 22 377 SN 76-26.2, Installation of 1B Inverter and Alternate 22 Power Supplies 375 SN 76-26.3, Installation of 7.5KVS Floor Wunted 22 Constant Voltage Transformer 1A 378 SN 76-26.1, Installation of 1A Inverter and 22 Alternate Power Supplies 321 SM 77-1682.1, Penetration Testing Modification 22 Penetration 304 325 SN 76-27.1, Penetration 332 Modification 22 318 SN 77-1682.4, Penetration Testing Modification 22 Penetration 107 320 SN 77-1682.2, Penetration Testing Reification 22 Penetration 202 319 SM 77-1682.3, Penetration Testing Modification 22 Penetration 210

PCN I 78 Procedure a Title Meetin I 78 394 SM 77-1660.2, Overpressurization Mechanical Package 22 291 B4 76-01.1, Safeguard Buses DC Control Voltage bhnitor 22 425 SN 77-1660. 10, RCS, Overpressurization Protection 22 Electrical Conduit and Wiring 426 RI 77-2.10, DI Water Containment Isolation 22 Electrical Conduit and Wiring 409 SM 78-2273.1, Armor Plate on the East Wall of the 22 Control Room 408 Rl 77-1836.1, Turbine Building Pressurization and 22 Security Wall 398 B4 77-02.1, DI Water to Containment Modification 22 Mechanical 359 RSSP-15.9, Inservice Inspection Hydro Test of Class "B" Safety Realted Piping (Service Water Loop B) 327 SM 78-1048.1, Accumulator Relief Modification 24 438 M-52.3, Incore Thimbles Cleaning 24 447 A-17, Plant Operations Review Committee Operating 24 Procedure 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 Modification 24 of the Relay Backs 433 M-73.3, Welding on Carbon Steel Piping or Components 24 440 S-2.5A, Burping RCVZ (To Be Opened to Atmosphere) 24 441 S-2.3B, Burping the Pressurizer Relief Tank (To be 24 Opened to Atmosphere) 417 S-2.3B, Burping the Pressurizer Relief Tank (To be 24 Opened to Atmosphere) 414 TCIP-9, Test Instrument Calibration Procedure 24 443 S-2.4A, Draining the Pressurizer (RCS Degassed) 24

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PCN 5 78 Procedure 6 Title Meetin 5 78 418 6 437 S-2.5A, Burping Reactor Coolant Drain Tank 24 432 M-65.0,. Main Steam Line Weld Repairs (Outside of 24 Containrent) 405 SN 78-1875.1, "A" Feedwater Venturi Monorail 25 407 SN 78-1480.1, ".A" RCP Ladder and Handrail Installation 404 SM 77-1474.1, RCP Seal Bypass Modification 397 SN 75-14, Boric Acid Batch Tank Recirculation Piping 25 and Supports 402 SN 78-1485.1, Dillon Cell Storage Frame 25 459 SN 77-1660.2, Overpressurization Mechanical Package 25 458 SN 77-02.1, Demineralized Water to Containment 25 Modification Mechanical 463 RD-6, Gas Decay Tank Releases 25 462 M-ll.8B, Reactor Coolant Pump Seal Injection and Service Mechanical 464 SN 77-1623.1, Charging Pump Mnorails 25 350 SC-3.15.16, Fire Protection System Inspections and Tests 358 CP-70.5, Test Gauge Calibration Procedure 26 366 . CP-617.0, Component Cooling Water Pumps Discharge 26 Pressure PIC-617 367 CP-628.0, RHR Loop Reactor Coolant Test Bypass Flow 26 i

368 CP-2033.0, Service Water Flow From "3A" Vent Cooler Flowmeter FIA-2033 369 CP-2034.0, Service Water Flow From "lB" Vent Cooler 26 Flowmeter FIA-2034 370 CP-2035.00 Service Water Flow From "lC" Vent Cooler 26 Flowmeter FIA-2035 371 CP-2036.0, Service Water Flow Frcm "1D" Vent Cooler 26 Flowmeter FIA-2036 255 HP-10.7, Flow Calibration of Low Volume Air Samplers 26

PCN 4 78 Procedure 6 Title Meetin 5 78 323 PR-7.2, Protective Relay Calibration and Trip Test 26 512B Transformer 34KV Relaying 448 A-19, Change in Written Procedures 26 449 RSSP-6.1, Integrated Leakage Rate Test Valving 26 Alignment 435 RSSP-6. 0, Containment Integrated Leakage Rate Test 454 M-37.24A, Main Steam Safety Valve Maintenance Valve No.

450 M-37.24A, Main Steam Safety Valve Maintenance Valve No. 26 457 SM 77-1660.28, Overpressure Protection Modification of 26 the Relay Racks 456 S-4.1U, Velocity Flush of R-18 26 424 A-35, Prime Hover Holding and Markup Requirements 428 ISI-1.8, Quality Group A Inservice Inspection 26 429 ISI-2.6, Quality Group B Inservice Inspection 26 430 ISI-3.5, High Energy Inservice Inspection 26 445 O-l. 1C, Pre-Critical Technical Specif ications Check 26 Sheet 427 HP-12.4, Fitting and Testing of Respirators 26 444 A-52.4, Control of Limiting Conditions for Operating 26 Equipment 439 GS-41. 0, Employee Screening Program 26 202 , A-58, Installation of Power, Control or Instrunentation Cables at Ginna Station 442 A-54. 4, Empty Engineer Responsibilities 26 360 M-43.15, Installation of Steam Generator Manway Insert 451 SM 76-28.1, Flange Installation on Main Feedwater 26 Flow Venturis Ginna Station Feedwater Line 469 &1 78-1845.1, Guide Stud Storage Racks 27 505 SM 78-2160.1, GSM-7 Pipe Supports 27

PCN I 78 Procedure & Title Meetin 5 78 470 SM 77-1682.5, Penetration Testing Modification 27 Penetration 143 510 SM 76-28.2, Flange Installation on Feedwater Flow 27 Venturis A Feedwater Line 460 SM 75-5.50, Auxiliary Feedwater Hanger APW-51 Repair 27 455 RF-51, Reactivity Insertion Computation 27 513 ISI-2.1.6, Quality Group B Inservice Inspection 27 512 ISI-1.1.8, Quality Group A Inservice Inspection 27 508 SM 76-26.1, Installation of 1A Inverter and.Alternate 27 Power Supplies 465 0-2.3.1, Draining the Reactor Coolant System 27 S-3.2J, Isolation of Reactor Coolant Filter and 27 Associated Grinnel Diaphragm Valves (249, 250, 253, 251, 248A, and 248B) 517 M-37.24A, Main Steam Safety Valve Maintenance Valve No. 27 474 S-3.2J, Isolation of Reactor Coolant Filter and 27 Associated Grinnell Diaphragm Valves (249, 250, 253, 251, 248A, and 248B) 473 M-43.1, Steam Generator Manway Cover Rermval Steam 27 Generator 511 EN-201, B Steam Generator Secondary Side Peripheral Tube 27 Removal 476 RSSP-15.9, Inservice Inspection Hydro Test of Class "B" 27 Safety Related Piping (Service Water Loop B) 516 SM 75-14, Boric Acid Batch Tank Recirculation Piping 27 and Supports 466 SM 77-2.10, DI Water Containment Isolation Electrical 27 Conduit and Wiring 518 RF-2E, Draining of Refueling Canal 27 509 SM 77-1682.4, Penetration Testing Modification 27 Penetration 107 452 E-1.2, Zoss of Coolant Accident 27 GS-1.2, Ginna Station Security Event Report 27

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PCN 5 78 Procedure & Title Meetin 5 78 548 SM 76-26.2, Installation of 1B Inverter and Alternate 28 Pawer Supplies 542 A-54.3, Open Flame, Welding and Grinding Permit 28 558 S-27.209, Isolation of CVCS Relief Valve 209 28 559 a 546 RSSP-13.8, Inservice Inspection Hydro Test of Class "C" 28 Safety Related Piping (Service Water Piping Loop A)

P 521 RSSP-15.8, Inservice Inspection Hydro Test of Class "B" 28 Related Piping (Charging Pump Suction Excluding 'afety VCT) 520 RF-10, Fuel Transfer System Checkout and Demonstration 28 Procedures 520 M-11.8.3, Reactor Coolant Pump Seal Inspection and 28 Service Mechanical 552 B4 77-1057.1, Relocation of the Charging Pump Filter 28 Vent 551 RSSP-14.8, ISI Hydro Test of Class "C" Safety Related 28 Piping (Service Water Piping Loop A) 561 M-38.5; 1B Constant Voltage Transformer Maintenance 28 554 RSSP-12, Tiesting of Primary and Secondary Relief Valves 28 on Test Stand GS-21.0, Site Access Control (Security) and Personnel 28 Identification 553 S-27.209, CVCS Relief Valve 209 Isolation 28 562 S-27.1, Volume Control Tank Grinnell Diaphragm Valves 28 Isolation 545 A-50.6, R.'. Ginna Operator Requalification Program 28 550 M-ll.8A, Reactor Coolant Pump 5 Removal from Service 28 for Pump Maintenance 471 S-2.1B, Reactor Coolant Pumps Isolation for Naintenance 28 522 , PZ-2.5, Air Operated Valves, Quarterly Surveillance 28 515 A-36, Station Holding Rules 28

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PCN 4 78 Procedure 6 Title Meetin 5 78 543 CP-429.7, Pressurizer Pressure Bistable PC-429A 28 519 M-15.5, lA Deisel Startup Air Compressor Maintenance 28 316 QC-1403, Inspection and Test Status Control 28 507 0-2.3.1, Draining the Reactor Coolant System 28 472 M-15.6, 1B Deisel Fuel Oil Transfer Pump Maintenance 28 330 0-6.4, Core Quadrant Power Tilt Calculation 28 540 CP-410.0, Reactor Coolant Temperature Gold Leg 28 "410B" Calibration and/or. Maintenance 538 CP-409, Reactor Coolant Termperature Cold Leg 28 "409B" Calibration and/or Maintenance 541 CP-410.3, Reactor Coolant Temperature Cold Leg 28 Bistable TC-410A/B 539 CP09.3, Reactor Coolant Temperature Cold Leg 28 Bistable TC-409A/B 532 CP-455.0, N2 Accumulator Pressure Low Loop 455 28 533 CP-455.'1, N2 Accumulator Pressure Lear Zoop 455 28 Transmitter 534 CP-455.2, N2 Accumulator Pressure Low Loop 455 28

. Bistable Power Supply and Indicator 535 CP-456.0, N2 Accumulator Pressure Low Xaop 456 28 536 CP-456.1, N2 Accumulator Pressure Lcm Eaop 456 28 Transmitter 537 CP-456.2, N2 Accumulator Pressure Low Eoop 456 28 Bistable Power Supply and Indicator 531 CP-452.2, Overpressure Protection Loop 452 Power 28 Supply and Bistable 526 CP-451. 0, Overpressure Protection Loop 451 28 527 CP-451.1, Overpressure Protection Loop 451 Transmitter 28 528 CP-451.2, Overpressure Protection Loop 451 Power Supply 28 and Bistable

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PCN N 78 Procedure & Title Meetin N 78 529 CP-452.0, Overpressure Protection Loop 452 28 530 CP-452.1, Overpressure Protection Loop 452 Transmitter 28 524 CP-.450.1, Overpressure Protection Loop 450 Transmitter 525 CP-450.2, Overpressure Protection Loop 450 Ewer Supply 28.

and Bistable CP-450.0, Overpressure Protection Loop 450 28 514 QCIP-20, Verification of Accuracy for Mechanical 28 Measuring Tools 477 ISI-1.1.9, Quality Group A Inservice Inspection 28 478 ISX-1.2.1, Quality Group A Inservice Inspection 28 479 ISI-1.2. 2, Quality Group A Inservice Inspection 28 480 ISI-1.2.3, Quality Group A Inservice Inspection 28 481 ISX-1.2.4, Quality Group A Inservice Inspection 28 482 ISI-1.2.5, Quality Group A Inservice Inspection 28 483 ISI-l.2. 6, Quality Group A Inservice Inspection 28 484 ISI-1.2.7, Qaulity Group A Inservice Inspection 28 485 ~ ISI-1.2.8, Quality Group A Inservice Inspection 28 486 ISI-1.2.9, Quality Group A Inservice Inspection 28 487 ISI-1.3.1, Quality Group A Inservice Inspection 28 488 ISI-1.3. 2, Quality Group A Inservice Inspection 28 489 ISI-1.3.3, Quality Group A Inservice, Inspection 28 490 ISI-1.3.4, Quality Group A Inservice Inspection 28 491 ISI-'1.3.5, Quality Group A Inservice Inspection 28 492 ~

ISI-1.3.6, Quality Group A Inservice Xnspection 28 493 ISI-l.3. 7, Quality Group A Inservice Inspection 28 494 ISX-1.3. 8, Quality Group A Inservice Inspection 28

PCN 5 78 Procedure 6 Title Meetin 5 78 495 ISI-1.3.9, Quality Group A Inservice Inspection 28 496 ISI-1.4.1, Quality Group A Inservice Inspection 28 497 ISI-1.4.2, Quality Group A Inservice Inspection 28 498 ISI-1.4.3, Quality Group A Inservice Inspection 28 499 ISI-1.4.4, Quality Group A Inservice Inspection 28 500 ISI-1.4.5, Quality Group A Inservice Inspection 28 501 ISI-1.4.6, Quality Group A Inservice Inspection 28 502 ISI-1.4.7, Quality Group A Inservice Inspection 28 503 ISX-1.4.8, Quality Group A Inservice Inspection 28 504 ISI-1.4.9, Quality Group A Inservice Inspection 28 A-54.6, Health Physics Tour 28 597 EM-202, Safety Injection Sequence Timing Relay 29 Replacement 557 SM 76-01.2, Cable Installation for the DC Control 29 Fuses 565 SN 77-1660.15, Instrumentation Tie-Ins for RCS 29 Overpressurization 544 SN 78-1865.1, Steam Generator "A" Air Mver Installation 29 603 S-27.348B, Valve 348B Isolation 30 604 EN-201, "B" Steam Generator Secondary Side Peripheral 30 Tube Removal 608 S-3. 1K, 1A Boric Acid Transfer Pump Isolation/RestOration 30 574 SM 77-1682. 2, Penetration Testing lkx3ification- 30 Penetration 202 579 SM 77-1682.3, Penetration Testing Modification 30

.Penetration 210 598 RF-51, Reactivity Insertion Computation 30 566 PT-2.10.2, RHR System Core Deluge Check Valves 853A 30 and 853B

PCN 5 78 Procedure & Title Meetin N 78 564 . N-32.1, KS-25, CG-50 and DB-75 Circuit Breaker 30 Maintenance and Overcurrent Trip Device Test and/or Replacement 569 SM 75-5.40, Standby Auxiliary Feedwater Rework Inside 30 Containment 576 M-37.2.1, Inspection and Repair of Hain Steam Check 30 Valves 575 A-54.6, Health Physics Tour 30 572 A-30.3, Plant Procedure Content and Format Requirements 30 580 A-13, Maintenance Record Requirements 30 601 A-l, Radiation Control Manual 30 609 A-30.2, Plant Procedure Classification, Review, Approval 30 and Distribution Requirements 584 SM 78-1873.1, Pressurizer Jib Crane 31 611 Rl 77-1660.11, RCS Overpressurization Protection 31 Electrical Terminations in the Control, Room and in the Field 610 EM-203, Repair of Valve 4738 Service Water to Motor 31 Coolers 643 ~

S-27.2, Isolation of CVCS Letdown Demineralizers and 31 Associated Valves 642 M-37.46, Reactor Compartment Cooler Service Water 31 Outlet Valve 4758 Maintenance and Inspection 617 GS-10.1, Security Guard Action During a Local 31 Radiation Emergency 621 QC-1701, Quality Assurance Records 31 613 RF-2D, Filling the Refueling Canal 31 582 CP-950.3, Containment Pressure Transmitter PT-950 31 581 CP-949.3, Containment Pressure Transmitter PT-949 31 605 M-43. 24.1, Inspection of Steam Generator Secondary 31 Side Upper Internals

PCN I 78 Procedure & Title Meetin I 78 602 PZ-2.7, Service Water System 31 600 S-27.887, Safety Injection Relief Valve 887 Isolation 31 583 T-17J, Generator Bearing Drain Vapor Extractor 31 Normal Lineup and Operation 570 PZ-7, Hydro Test of Reactor Coolant System 31 560 PT-22.10, Mechanlical Manifold "C" Leak Rate Test 31 563 SC-1.12B, Station Call List 31 591 PZ-23.45, Containment Isolation Va1ve Leak Rate Testing 31 Leakage Test Instrumentation 593 PZ-23.51A, Containment Isolation Valve Leak Rate Testing 31 "A" Hydrogen Recombiner (Pilot and Hain) 594 PZ-23.S1B, Containment Isolation Valve Leak Rate Testing 31 "B" Hydrogen Recombiner (Pilot and Main) 595 PZ-23.51C, Containment Isolation Valve Leak Rate Testing 31 "A" and "B" Hydrogen Recombiner Oxygen Makeup 589 ~23.23, Containment Isolation Valve Leak Rate Testing 31 Sump "A" Discharge 587 PT-23.22, Containment Isolation Valve Leak Rate Testing 31 RCDZ Discharge l

622 A-20, Control Room Its 31 624 A-25.1, Ginna Station Event Reports 31 620 S-14.1, Radiation Honitoring and Related Systems 31 Daily Plot Hequirements 590 PT-23.29, Containment Isolation Valve Leak Rate Testing 31 Demineralized Water 592 PZ-23.46, Containment Isolation Valve Leak Rate Testing 31 Nitrogen to Accumulators 596 PZ-23A, Containment Isolation Valve Test Connection 31 Boundary Control 567 M-ll.27, Corrtponent Cooling Pump Inspection and 31 Maintenance

PCN I 78 Procedure a Title Meetin I 78 637 SN 77-02.2, Hydrostatic Testing and Initial Service 32 L'eat Test of the Deraineralized Water to Containment Modification 636 SN 77-1682.10, Hydrostatic Testing of Penetration 143 32 Piping Modification 658 SN 78-1048.1, Accumulator Relief Rx3ification for 32 Accumulator Relief Line 657 SM 77-1682.4, Penetration Testing Modification 32 Penetration 107 659 SN 77-1832.1, Flame Retardant Cable Coating in the 32 East Cable Vault 666 SN 75-47.50, Rework of CVCS Hangers Inside Containment 32 665 SM 77-1660.15, Instrumentation Tie-ins for RCS 32 Overpressurization 668 & 670 SN 77-1660. 2, Overpressurization Mechanical Package 32 650 EM-194, Repair of CVCS Hanger CH54 32 664 N-37.38.1, Crosby Safety and Relief Valve Maintenance 32 650 N-48.5, Isolation of Bus 17 32 663 RSSP-15.7, Inservice Inspection Hydro Test of Class "B" 32 Safety Related Piping (Charging Pumps Discharge Piping) 674 SN 77-1057.1, Relocation of the Charging Pump Filter 32 Vent QC-105, Indoctrination and Training Modification 32 Program QC-301, Work Start Authorization 32 QC-304, Control of Modification Activities by the 32 Modification Project 644 SN 77-1660.100, Pneumatic Testing of the Containment 33 DI Water Automatic Isolation Valve 8418 653 S-27.861, Relief Valve 861 Isolation 33 654 S-27.1817, Relief Valve 1817 Isolation 33 645 SN 77-02.15, Air Tie-in for the DI Water to Containment 33

PCN I 78 Procedure & Title Meeting I 78 673 RF-2, Reactor Refueling Outage Operations and Activities 33 679 SM 76-27.1, Penetration 332 Modification 33 678 SM 77-1682.4, Penetration Testing Modification 33 Penetration 107 677 SM 76-27.1, Penetration 332 Modification 33 676 Rl 77-1682.1, Penetration Testing Modification 33 Penetartion 304 683 RSSP-13.6, Inservice Inspection Hydro Test of Class "C" 34 Safety Related Piping 682 SM 77-1660.15, Instrumentation Tie-ins for RCS 34 Overpressurization 686 SM 78-1485.1, Dillon Cell Storage Frame 34 685 SN 78-1480.1, A RCP Ladder and Handrail Installation 34 687 SN 78-1865.1, Steam Generator "A" Air Mover Installation 34 699 M-37.11, Repair and Inspection of Pressurizer Power 34 Operated Relief Valves 430 and 431C 634 SN 78-1888.1, Spray Additive Tank Recirculation Line 34 Shutoff Valve Installation 684 SN 76-26.5, Installation of 7.5 KVA Floor Munted 35

. Constant Voltage Transformer Backup Supply for Instrument Busses A, B, C, and D 612 PT 32.2, Initial Checkout of the KS Overpressure 35 Protection System 700 SN 77-1660.24, KS Overpressure Protection Loop 455 35 Rack W2 Instrumentation and Wiring 635 S-12.4, RCS Leakage Surveillance Record Instructions 35 655 RF-2, Reactor Refueling Outage Operations and Activities 35 649 RF-2E, Draining of Refueling Canal 35 691 RF-14.4.1, Relaxing and Removing Reactor Vessel Head 35 Studs, Stud Hole Plugs and Guide Stud Installation 690 RF-14.412, Removing Reactor Vessel Guide Studs and Stud 35 Hole Plugs, Installating and Tensioning Head Studs

PCN 4 78 Procedure & Title Meetin N 78 688 HP-4.1, Controlled Area Entry 35 706 S-SA, Component Cooling Water System Startup and 35 Normal Opeation Valve Alignment 697 M-47.1, Inspection of Pressurizer Internals 35 627 M-44.2, Isolation and Restoration of Motor Control 35 Center 1A 647 CP-924.0, Calibration and/or Maintenance of Safety 35 Injection Flow Loop "B" 648 CP-925.0, Calibration and/or Maintenance of Safety 35 Injection Flaw laop "A" 662 BSSP-15.7, Inservice Inspection Hydro Test of Class "B" 35 Safety Related Piping (Charging Piping) 675 S-4.5.9, Letdown Deborating DI (A or B) Resin 35 Replacement 672 GS-17.0, Accountability of Personnel During Emergency 35 Conditions 660 GS-31.0, Door Alarm System 35 669 RF-2; Reactor Refueling Outage Operations and Activities 35 707 RF-8. 2, Fuel Handling Instruction Pre-Loading and 35 Periodic Valve Test 705 0-1.1B, Establishing Containment Integrity 35 704 RF-2B, Recpired Valve Line-.Up for Reactor Head Removal 35 671 HP-4.3, Work Permit Use 35 628 0-2.5, Plant Shutdown from Hot Shutdawn to Cold Shutdown 35 When Condenser Steam Dump is Unavailable 629, 0-2.4, Plant Shutdown from Hot Shutdown to Cold Shutdown 35 During Blackout 623 0-2.2, Plant Shutdawn fram Hot Shutdown to Cold Condition 35 696 PT-16, Auxiliary Feedwater System 35

PCN 5 78 Procedure a Title Meetin I 78 694 PT-2.7, Service Water System 695 PT-3, Containment Spray Pumps and NaOH Additive 35 System 693 PZ-2.2, Residual Heat Removal System 35 692 PT-2.1, Safety Injection System Pumps 35 703 PT-2. 4, Cold/Refueling Motor Operated Valve 35 Surveillance 651 RSSP-1.1, Valve Interlock Verification Residual 35 Heat Removal System 702 RSSP-3.0, Verification of Emergency Start 35 Logic Auxiliary Feedwater Pumps 701 PT-2. 5, Air Operated Valves Quarterly Surveillance 35 698 SC-3, Fire Emergency Plan 35 315 QC-1003, Control of Inservice Inspection Activities 35 640 QC-103, Periodic Review of Quality Control Procedure 35 638 a 639 QC-201, Ginna Quality Control Organization 35

.QC-303, Control of System Modification Activities 35 S-3.1N, Isolation of Miscellaneous Valves in the 36 652'20 Boric Acid Storage Tank Room SM 77-1682. 2, Penetration Testing Modification 36 Penetration 202 714 SM 75-14, Boric Acid Batch Tank Recirculation Piping 36 and Supports 710 &I 76-28.2, Flange Installation on Feedwater Flow 36 Venturis A Feedwater Line 721 CP-455.0, N2 Accumulator Pressure Low Loop 45S 36 711 S-3.2A, Charging and Volume Control Systen Pre-Startup 36 Alignment 713 P-8, Precautions, Limitations and Setpoints Waste 36 Disposal System

PCN 0 78 Procedure a Title Meetin 4 78 715 S-13A, RHR System Lineup for Safety Injection 36 709 S-3.1K, lA Boric Acid Transfer Pump Isolation/Restoration 36 723 EM-155, Safeguard Rack Relays VI and/or CI Replacement 36 722 M-81, Safeguard Rack Ventillation and Containment 36 Isolation Relays Replacement A-54.6, Health Physic's Tour 767 S-2.3B, Burping the Pressurizer Relief Tank with N2 37A (Not to ke Opened the Atmosphere) 774 M-40.1, Hydraulic Snubber Unit Removal and Reinstallatio 37A Procedure 766'24 RF-2, Reactor Refueling Outage Operations and Activities 37A ISI-2.1.7, Quality Group B Inservice Inspection 37 725 ISI-2.1.8, Quality Group B Inservice Inspection 37 726 ISI-2.1.9, Quality Group B Inservice Inspection 37 727 ISI-2.2.1, Quality Group B Inservice Inspection 37 728 ISI-2.2. 2, Quality Group B Inservice Inspection 37 729 ISI-2.2. 3, Quality Group B Inservice Inspection 37 730 ISI-2. 2. 4, Quality Group B Inservice Inspection 37 731 ISI-2.2.55 Quality Group B Inservice Inspection 37 732 ISI-2.2.6, Quality Group B Inservice Inspection 37 733 ISI-2.2.7, Quality Group B Inservice Inspection 37 734 ISI-2.2.8, Quality Group B Inservice Inspection 37 735 ISI-2.2. 9, Quality Group B Inservice Inspection 37 736 ISI-2.3.1, Quality Group B Inservice Inspection 37 737 ISI.3.22 Quality Group B Inservice Inspection 37 738 ISI-2.3.3, Quality Group B Inservice Inspection 37 739 ISI-2.3.4, Quality Group B Inservice Inspection 37

PCN I 78 Procedure 6 Title Meetin I 78 740 ISI-2.3.5, Quality Group B Inservice Inspection 37 741 ISI-2.3.6, Quality Group B Inservice Inspection 37 742 ISI-2.3.7, Quality Group B Inservice Inspection 37 743 ISI-2.3.8, Quality Group B Inservice Inspection 37 744 ISI-2.3. 9 Quality Group B Inservice Inspection 37 745 ISI-2.4.1, Quality Group B Inservice Inspection 37 746 ISI-2.4.2, Quality Group B Inservice Inspection 37 747 ISI-2.4.3, Quality Group B Inservice Inspection 37 748 ISI-2.4.4, Quality Group B Inservice Inspection 37 749 ISI-2.4.5, Quality Group B Inservice Inspection 37 750 ISI-2.4. 6, Quality Group B Inservice Inspection 37 751 ISI-2.4.7, Quality Group B Inservice Inspection 37 680 S.5.11, "B" Letdown Deborating DI Replacement 37 681 S-4.5.10, "A" Letdown Deborating DI Resin Replacement 37 789 PT-23A, Containment Isolation Valve Test Connection 37 Boundary Control 771 RF-2, Operations and Activities 37 784 T-16A, Turbine Pre-Statup 37 768 O-l. 1B, Establishing Containment Integrity 37 712 T-41A, Alignment of Auxiliary Feedwater System Prior 37 to Power Operation 752 O-l. 1B, Establishing Containment Integrity 37 716 S-2.5B, Restoring Reactor Coolant Drain Tank to Service 37 After Maintenance 791 PZ-7, Hydro Test of Reactor Coolant System 37 780 ISI-1.1.8, Quality Group A Inservice Inspection 37

PCN -5 78 Procedure & Title Meetin I 78 782 ISI-3.1.5, High Energy Inservice Inspection 37 781 ISI.1.6, Quality Group B Inservice Inspection 37 785 PT-13.1.1, Protomatic Deluge Valve System Testing Systen 37 Number 7, 8, 9, 10 787 PZ-7, Hydro Test of Reactor Coolant System 37 777 ET-23.3, Containment Isolation Valves Leak Bate Testing 37 Makeup Water to Pressurizer Relief Tank Line 795 FT-32.2, Initial Checkout of the RCS Overpressure 37 Protection System 794 ISI-1.1.9, Quality Group A Inservice Inspection 37 793 0-6.2, Main Control Board System Status Verification 37 718 M-7.3, Boric Acid Concentrates and Ion Exchanger Filter 37 Replacement 778 M-48.3, Isolation and Restoration of Bus 115 37 769 PC-1.3, Daily Chemistry Analysis Results 37 788 HP-11.2, Iodine in Air-Charcoal Cartridge Method 37 770 ISI-3.1.5, High Energy Inservice Inspection 37 753 A-52.2, Control of Locked Valve Operation 37 708 A-36, Station Holding Rules 37 779 0-2.3.1, Draining the Reactor Coolant System 37 717 T-34A, Generator Seal Oil System Startup 37 790, M-40.8, Functional Testing of Hydraulic Snubbers 37 783 R1-201, "B" Steam Generator Secondary Side Peripheral 37 Tube Removal 786 RSSP-13.8.1, Hydro Test of Loop A Underground Service 38 Water Piping 796 EM 204 I Seal Welding MOV-700 RHR from Loop A 38 799 &1 76-01.1, Safeguard Buses DC Control Voltage Mnitor 38

PCN 5 78 Procedure a Title Meetin 5 78 800 RSSP-1.4, Valve Interlock Verification - Reactor 38 Coolant System 830 PT-32.2, Initial Checkout of the RCS Overpressure 38 Protection System 831 0-1.2, Plant from Hot Shutdcam to Steady Load 38 840 S-29.1, Prealignment of the Reactor Vessel Overpressure 39 Protection System N2 Supply System 841 S-29.2, Charging the Reactor Vessel Overpressure 39 Protection System Accumulators With N2 842 0-7, Alignment and Operation of the Reactor Vessel 39 Overpressure Protection System 899 EN-204, Seal Welding MOV-700 RHR "A" Loop 39 883 0-2.5, Plant Shutdown from Hot Shutdown to Cold Shutdown 39 When Condenser Steam Dump is Unavailable 792 O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 39 839 O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 39 838 0-2.2, Plant Shutdown from Hot Shutdown to Gold Condition 39 837 0-2.3, Plant at Gold Shutdown 39 834 Filling and Venting the Reactor Coolant System 39 836 Plant Blackout from Hot Shutdown to Cold Shutdown 39 During Blackout 835 0-2.5, Plant Shutdown from Hot Shutdown to Cold Shutdown 39 When Condenser Steam Dump is Unavailable 888 A-l.1, Locked Radiation Areas 39 896 QC-1404, Test Status Control 39 897 O-l.2.2, Critical Rod Position Calculation 39 898 0-3.1, Boron Concentration for the Hot Xenon Free 39 Shutdown Margin 887 ISI-4.1. 5, High Energy Inservice Inspection 40 844 &1 75-14, Boric Acid Batch Tank Recirculation Piping 40 and Supports

PCN 4 78 Procedure & Title Meetin I 78 845 SN 76-11.10, No. 12B Auxiliary Transformer Deluge 40 System Tie-in 846 SM 76-26.1, Installation of 1A Inverter and Alternate 40 Power Supplies I

847 SN76-26.2, Installation of 18 Inverter and Alternate 40 Power Supplies 848 SN 76-26.3, Installation of 7.5KV Floor Mounted Constant 40 Voltage Transformer 1A 849 SN 76-26.4, Installation of 7.5KV Floor Mounted Constant 40 Voltage Transformer 1B 850 SN 76-26.5, Installation of 7.5KV Floor Haunted Constant 40 Voltage Transformer Backup Supply for Instrument Buses A, B, C and D 851 RI 76-27.1, Penetration 332 Modification 40 852 SN 76-28.2, Flange Installation on Feedwater Flow 40 Venturis A Feedwater Line 853 RI 77-02.1, Demineralized Water to Containment 40 Modification Mechanical 854 SN 77-02.2, Hydrostatic Testing and Initial Service 40 Leak Test of the Demineralized Water to Containment Modification 855 SM 77-2.10, DI Water Containment Isolation Electrical 40 Conduit and Wiring 856 SN 77-02. 12, Demineralized Water Containment Isolation 40 857 SN 77-02.15, Air Tie-in for the DI Water to Containment 40 858 SM 77-1057.1, Relocation of the CHarging Pump Filter 40 Vent 860 SN 77-1660.10, RCS Overpressurization Protection 40 Electrical Conduit and Wiring 861 SN 77-1660.11, RCS Overpressurization Protection 40 Electrical Terminations in the Control Room and in the Field 862 SN 77-1660.15, Instrumentation Tie-Ins for RCS 40 Overpressurization

PCN 5 78 Procedure & Title Meetin I 78 863 SN 77-1660.21, BCS Overpressure Protection Loop 450 40 Rack B2 Instrumentation Installation and Wiring 864 SM 77-1660.22, RCS Overpressure Protection Loop 451 40 Rack W2 Instrumentation Installation and Wiring 865 SN 77-1660.23, KS Overpressure Protection Lcop 452 40 Rack R2 Instrumentation Installation and Wiring 866 SN 77-1660.24, BCS Overpressure Protection Loop 455 40 Rack W2 Instrumentation Installation and Wiring 867 SN 77-1660.25, RCS Overpressure Protection Loop 456 40 Rack R2 Instrumentation Installation and Wiring 868 SN 77-1660.26, BCS Overpressure Protection Loop 409 40 Rack RCS2 Instrumentation Installation and Wiring 869 SM 77-1660.27, KS Ovezpressure Protection Loop 410 40 Rack RCS2 Instrumentation Installation and Wiring 870 SN 77-1660. 28, Overpressure Protection Rx3ification 40 of .the Belay Backs 871 SN 77-1660.29, Overpressure Protection Rx3ification 40 Annunciator Wiring 872 SN 77-1682.1, Penetration Testing Modification '40 Penetration 304 873 SN 77-1682.2, Penetration Testing Modification 40 Penetration 202 874 B4 77-1682.3, Penetration Testing Rx3ification 40 Penetration 210 875 SM 77-1832.1, Flame Retardant Cable Coating in the 40

'I East Cable Vault 876 SN 77-1480.1, "A" RCP Ladder and Handrail Installation 40 877 SM 78-1485.1, Dillon Cell Storage Frame 40 878 SM 78-1865.1, Steam Generator "A" Air Mover Installation 40 879 Rf 78-1890.1, Feedwater Line Drain Valves Before the 40 Containment Check Valves 887 ISI-4.1.5, High Energy Inservice Inspection 40

PCN 5 78 Procedure a Title Neetin 5 78 880 M-ll.10, Major Inspection of Service Water Pump 40 890 A-52.2,'ontrol of Locked Valve Operation 40 901 N-40.3, Inspection and Maintenance of Spring Hangers 40 895 PZ-2.2, Residual Heat Removal System 40 902 EK-203, Repair of Valve 4738, Service Water to Mtor 40 Coolers 900 M-40.3, Inspection and Naintenance of Spring Hangers 40 884 SM 77-1660.2, Overpressurization Mechanical Package 40 882 S-3.1N Isolation of Miscellaneous Valves in Boric Acid 40 Storage Tank Boom 843 SM 77-1660.2, Overpressurization Mechanical Package 40 885 M-ll.15, RHR Pumps Inspection/Maintenance 40 889 S.5.2, Waste Condensate Polishing Demineralizer Resin 40 Replacement 893 Ri 75-34.23, Pipe Restraints and Jet Shields Rework for 40 Steam Generator Blowdown Lines 904 O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 40 903 0-6.4.1, Reference ~ilibrium Indicated Axial Flux 40 Difference Determination 905 SN 77-1660.100, Pneumatic Testing of the KS 40 Overpressure Protection System 798 PT-23, Containment Isolation Valve Leak Rate Testing 40 797 A-48, Test Tag Control Program 40 891 A-.7, Procedures for Handling Illness or Injuries 40 at Ginna Station 894 M-67.8, Star Corporation Heat Detector System 40 892 QC-1701, Qaulity Assurance Records 40 940 M-ll.34.1, Fan Bearing Reaaval and Replacement 41

PCN 4 78 Procedure a Title Meetin 5 78 989 SM 75-50.30, Rework of Jet Shielding for Main Steam 42 Bypass Piping and Valves 938 ET-13.1.5, Flood Valve System Testing System 43 Numbers 3, 4, 5, 6 937 RSSP-13.8.1, Hydro Test of Loop A Underground Service 43 Water Piping 953 S-29.1, Prealignment of the Reactor Vessel Overpressure 43 Protection System N2 Supply System 967 SM 75-34.23, Pipe Restraining and Jet Shields Rework 43 for Steam Generator Blowdown Lines 906 M-ll.8D, Reactor Coolant Pump iWjor Inspection and 43 Service Instrument and Control 941 RSSP-13.8.1, Hydro Test of Loop A Underground Service 43 Water Piping 801 ISI-4.1.6, Quality Group A Inservice Inspection 43 802 ISI-4.1.7, Quality Group A Inservice Inspection 43 803 ISI-4.1.8, Qaulity Group A Inservice Inspection 804 ISI-4.1.9, Quality Group A Inservice Inspection 43 805 ISI-4.2.1, Quality Group A Inservice Inspection 43 806 ISI-4.2. 2, Quality Gruop A Inservice Inspection 807 ISI-4.2.3, Quality Group A Inservice Inspection 43 808 ISI.2.4, Quality Group A Inservice Inspection 43 809 ISI.2.5, Quality Group A Inservice Xnspection 43 810 ISI.2.6, Quality Group A Inservice Inspection 43 811 ISI.2.7, Quality Group A Inserviee Inspection 43 812 ISI-4.2. 8, Quality Group A Inservice Inspection 43 813 ISX-.4.2. 9, Quality Group A Inservice Inspection 814 ISI-4.3.1, Quality Group A Inservice Inspection 43 815 ISX-4.3. 2, Quality Group A Inservice Inspection 43 816 ISI-4.3.3, Quality Group A Inservice Inspection 43

PCN 4 78 Procedure 6 Title Meetin 5 78 817 ISI-4.3.4, Quality Group A Inservice Inspection 43 818 ISX-4.3.5, Quality Group A Inservice Inspection 43 819 ISI-4.3.6, Quality Griup A Inservice Inspection 43 820 ISI-4.3.7, Quality Group A Inservice Inspection 43 821 ISX-4.3.8, Quality Group A Inservice Inspection 43 822 ISX-4.3.9, Quality Group A Inservice Inspection 43 823 ISX-4.4.1, Quality Group A Inservice Inspection 43 824 ISI-4.4.2, Quality Group A Inservice Inspection 43 825 ISI-4.4.3, Quality Group A Inservice Inspection 43 826 ISI-4.4.4, Quality Group A Inservice Inspection 43 827 ISI-4.4. 5, Quality Group A Inservice Inspection 43 828 ISX-4.4.6, Quality Group A Inservice Inspection 43 829 ISX-4.4.7, Quality Group A Inservice Inspection 43 947 PR-5, Relay Calibration and Trip Test 4160 Volt 43 Auxiliaries Circuit 956 0-1.2.1, 1/M Curves 43 961 CP-70. 5, Test Gauge Calibration Procedure 43 881 HP-1.1, Issuing Personnel Dosimeters 43 954 A-30.3, Plant Procedure Content and Format Requirements 43 960 A-l, Radiation Control Manual 43 959 A-l.3, Smearing Procedure 43 958 S-4.4.1, Spent Resin Package Site Receipt and Shipment 43 957 RD, Gas Decay Tank Release 948 PT-2.1, Safety Injection System Pumps 43 949 PZ-23.5A, Containment Isolation Valve Leak Rate Testing 43 Containment Sump Recirculation to "A" RHR Pump

PCN 5 78 'Procedure a Title Meetin 0 78 950 PT-23.5B, Contain7ent Isolation Valve Leak Rate Testing 43 Containment Sump Recirculation to "B" RHR Pump 324, SC-3.12, Plan for Recovery from Fire 43 939 M-67. 3, Flood Valve System Maintenance System 43 Numbers 3, 4, 5, 6 993 O-l.2. 2, Critical Rod Position Calculation 43 944 GS-26.1, Unoccupied Vital Area Key Control and 43 Accountability 946 GS-10.0, Security Personnel Actions During a Radiation 43 Emergency 945 GS-17.0, Accountability of Personnel During Emergency 43 Condition 943 GS-30.0, threatening Phone Call or Bomb Threat Procedure 43 993 PT-34.6, At Power Physics Testing 44 1024 CP-502.1, Calibration of 1A Emergency Diesel Kilowatt 44 Meters 1023 CP-502.2, Calibration of lB Emergency Diesel Kilowatt 44 Meters 907 ISI-3.1. 5A, Quality Group C Inservice Inspection 908 ISI-3.1. 6, Quality Group C Inservice Inspection 45 909 ISI-3.1.7, Quality Group C Inservice Inspection 45 910 ISI-3.1.8, Quality Group C Inservice Inspection 45 911 ISI-3.1. 9 Quality Group C Inservice Inspection 45 912 ISI-3.2.1, Quality Group C Inservice Inspection 45 913 ISI-3.2.2, Quality Group C Inservice Inspection 45 914 ISI-3.2.3, Quality Group C. Inservice Inspection 915 ISI-3.2.4, Quality Group C Inservice Inspection 45 916 ISI-3.2.5, Quality Group C Inservice Inspection 44

PCN I 78 Procedure a Title Meetin I 78 917 ISI-3.2.6, Quality Group C Inservice Inspection 45 918 XSI-3.2.7, Quality Group C Inservice Inspection 45 919 ISX-3.2.8, Quality Group C Inservice Inspection 45 920 ISI-3.2.9, Quality Group C Xnservice Inspection 45 921 ISI-3.3.1, Quality Group C Inservice Inspection 45 922 ISI-3.3.2, Quality Group C Inservice Inspection 45 923 ISI-3.3.3, Quality Group C Inservice Inspection 45 924 ISI-3.3.4, Quality Group C Inservice Inspection 45 925 ISI-3.3.5, Quality Group C Inservice Inspection 926 XSI-3.3.7, Quality Group C Inservice Inspection 45 927 ISI-3.3.8, Quality Group C Inservice Inspection 45 928 XSI-3.3.9, Quality Group C Inservice Inspection 45 929 ISI-3.4.1, Quality Group C Inservice Inspection 45 930 ISI-3.4.2, Quality Group C Inservice Inspection 45 931 ISI-3.4.3, Quality Group C Inservice Inspection 45 932 ISI-3.4.4, Quality Group C Inservice Inspection 933 ISI-3.4.5, Quality Group C Inservice Inspection 45 934 ISI-3.4.6, Quality Group C Inservice Inspection 935 ISI-3.4.7, Quality Group C Inservice Inspection 45 1027 0-1.3, Reactor Startup for Training 45 1030 0-1.2, Plant from Hot Shutdown to Steady Load 45 1021 PZ-16, Auxiliary Feedwater System 45 1019 O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 45 997 SM 75-34.23, Pipe Restraints and Jet Shields Rework for 45 Steam Generator Blowdown Lines 1001 PZ-6.2, NIS Intermediate Range Channels Channel No.

PCN I 78 Procedure & Title Meetin I 78 1013 M-37.38.1, Crosby Safety and Relief Valve Maintenance 45 1004 M-73.3, Welding on Carbon Steel Piping and Components 45 951 S-27.5.3, RCS Loop Sample Valves Isolation 952 S-27.5.2, Pressurizer Lie@id Space Sample Isolation 45 Valves 968 E-39.0, Fire at Facility 45 943 E-39.1, Containment Vessel Fire 45 974 E-39. 2, Relay/Computer Room Fire 45 969 E-39.3, Grinnell Deluge System Fire 45 970 E-39.4, Smoke Detector Area Fire 45 971 E-39. 5, Sprinkler System Fire 45 972 E-39.6, Auxiliary Building/Controlled Area Fire 45 859 SM 77-1660.2, Overpressurization Mechanical Package 45 1034 SM 78-1873.1, Pressurizer Jib Crane 45 1033 SM 78-1888.1, Spray Additive Recirculation Line Shutoff 45 Valve Installation 1026 SM 77-02.11, Electric Terminations at Valve 8418 and 45 in Control Room for DI Water to Containment 1000 0-2.4, Plant Shutdown from Hot Shutdwon to Cold Shutdown 45 During Blackout 999 0-2.2, Plant Shutdown from Hot Shutdown to Gold Condition 4S 1015 ET-6.3.3, Power Range Nuclear Instrumentation System 45 Channel 43 1014 PZ-6.3.4, Power Range Nuclear Instrumentation System 45 Channel 44 1016 PZ-6.3.2, Power Range Nuclear Instrumentation System 45 Channel 42 1017 PT-6.3.1, Power Range Nuclear Instrumentation System 45 Channel 41

PCN 4 78 Procedure a Title Meetin I 78 1008 PZ-6.1, Source Range NIS 45 1007 ET.2, NIS Intermediate Range 45 942 A-1.2, Air Sampling Procedure 45 1006 CP-128.3, Charging Line Flow Transmitter FT-128 and 45 Local Indicator FI-128A 1010 A-2.6, Incore Flux Map Data. Reduction and Review 45 1009 S-12.4, RCS Leakage Surveillance Record Instructions 45 1002 A-36, Station Holding Rules 1005 CP-128.0, Calibration and/or Maintenance of Changing 45 Line Flow Channel "128" 1012 CP-628, RHR Loop Reactor Coolant Test Bypass Flow 45 1020 SM 75-58.8, Modification of Walkway and Railings 45 Around the Spent Fuel Pool 309 SC-3.14.2, Fire Department and Fire Brigade Drill 46 1052 0-6.9, Opeating Limits for Ginna Station Transmission 1092 &I 76-16.1, Eddy Current Wiring Conduits 46 1036 0-2.1, Normal Shutdown to Hot Shutdown 46 1059 PZ. 4, 'Excore/Incore Recalibration 46 1056 SM 77-1498.1, Zaw Power Steam Control Reification Generator Feedwater ~s 46 1055 Rl 78-1048.1, Accumulator Relief Rx3ification for 46 Accumulator Relief Line 1053 SM 76-01.2, Cable Installation for the DC Control 46 Fuse Honitor System 1044 SM 75-41.31, Condensate Polishing System Control Board 46 Operational Check 1089 a 1043 SM 75-5.40, Standby Auxiliary Feedwater Rework Inside 46 Containment 1087 SM 75-34.23, Pipe Restraints and Jet Shields Rework 46 for Steam Generator Blowdown Lines

PCN I 78 Procedure a Title Meetin I 78 1042 & 1088 SM 75-5.50 Aux' Aux'.iary Feedwater Hanger AEW-51 Repair 1083 SM 75-58.8, Modification oof thee Walkway and Railings 1084 . SM 75-50.30, Rework of Jet Shield'n ze mg on Main Steam 46 1085 SM 75-48.30, Rework of the Auxilia 'y Feedwater Crossover 46 1086 SM 75-47.30 , Re Rework of CVCS Hangers Inside Containment 1050 M-38.3 , 1B Inveiter Maintenance or o Re pair 1049 M 38 ' , L~ia Inverter Maintenance or o Re paar 46 1041 M-38.4, 1A Constant Voltage Transformer Maintenance 46 or Repair 1040 M-38.5, 1B Constant Voltage Transformer Maintenance 46 or Repair 1028 0-1.1C, Pre-Critical Technical x ~~cification Check Sheet 1048 9 -2701, Quality Assurance Records 46 1054 Al '

0-7 Alignment and Operation of thee Reactor Vessel 46 Overpressure Prot t ion System

'c 990 , GS-26.1, Unocc ccountability up'ital ied Area Key Control and 46 1058 T-26,I 125 Volt DC and Station Battery System 46 1057 7.3, PT-17.3 RMS Channel Response to Po rtab le Radiation 46 Source 1119 M-11.8K, Reactor Coolant Pump Moto tor Minor Inspection 48

'8 1123 S-17B, Addition of 50% NaOH aOH to the Spray additive Tank 1108 TICP-.l , Test Instrument Calibration Procedure 48 1107 TICP-2, Test Instrument Calibration Procedure 48 1097 PT-13.1.9, Halon System Testing and'or 48 (Resetting) Comput mpu er Room and Relay Room 1099 PT-13.l. 3 De luge Valve System Testing Numbe rs 1, 2, ll 48

PCN I 78 Procedure 6 Title Meetin I 78 1098 PZ-13.1.7, Alarm Valve System Testing System Numbers 12, 13 Warehouse 1100 PZ-13.l.l, Protomatic Deluge Valve System Testing System 48 Numbers 7, 8, 9, 10 1122 M-43.21, Steam Generator Final Cleanup and Inspection 48 1121 M-47.1, Inspection of Pressurizer Internals 48 1156 CP-32.3, Calibration of Source Range N-32 48 1155 CP-31.3, Calibration of Source Range N-31 48 1117 CP-44.2, General Reinstate Procedure for N-44 48 1116 CP-44.1, General Defeat Procedure for N-44 48 1115 CP-43.2, General Reinstate Procedure for N-43 48 1114 CP-43.1, General Defeat Procedure for N-43 48 CP-41.2, General Reinstate Procedure for N-41 48 1110 CP-41.1, .General Defeat Procedure for N-41 48 1113 CP-42.2, Reinstate Power Range Channel 42 48 1112 CP-42.1, General Defeat Procedure for N-42, 48 1101 0-5.1, Zoad Reductions 48 1102 0-5. 2, Zoad Increases 48 1109 0-6.7, Weekly Alarm Status Check 48 1118 0-2.4, Plant Shutdown from Hot Shutdown to Cold 48 Shutdown During Blackout 1126 HP-5.1, Area Radiation Surveys 48 1120 SM 78-2160.1, GSM 7 Pipe Supports 48 955 A-50.12, Emergency Plan Training Program 49 1011 ISI-6.0, Inservice Leakage Inspection of Quality 49 Group C Systems 963 ISI-5, Eddy Current Testing of Series 44 Steam Generator Tubes

PCN 5 78 Procedure & Title Meetin 4 78 1210 ISI-1.2.1, Quality Group A Inservice Inspection 49 1211 ISI-l.2. 4, Quality Group A Inservice Inspection 49 1212 ISI-1.2.7, Quality Group A Inservice Inspection 49 1213 ISI-1.3.1, Quality Group A Inseryice Inspection 49 1214 ISI-1.3.4, Quality Group A Inservice Inspection 49 1215 ISI-1.3.7, Quality Group A Inservice Inspection 49 1216 ISI-1.4.1, Quality Group A Inservice Inspection 49 1217 ISI-1.4.4, Quality Group A Inservice Inspection 49 1218 ISI-1.4.7, Quality Group A Inservice Inspection 49 1046 PZ-23.14, Containment Isolation Valve Leak Rate 49 Testing Containment Air Sample Inlet 1047 PT-23.15, Containment Isolation Valve Leak Rate 49 Testing Containment Air Sample Outlet 1160 A-53. 0, Preventative Maintenance Program 49 1164 A-53.2, three bhnth Lubrication and Maintenance Inspection 1230 SM 76-21.7, Battery Room Air Conditioning Misc. 49 1223 SM 76-21.4, Battery Rocm Air Conditioning Air 49 Conditioner Discharge Duct South End of Battery Room 1224 PT-13.1.1, Protomatic Deluge Valve System Testing 49 System Numbers 7, 8, 9, 10 1222 SM 76-21.6, Battery Rocm Air Conditioning Air Supply 49 Duct to the Air Conditioner 1221 SM 76-21. 5, Battery Bcxm Air Conditioning Service 49 Water Piping Installation 1162 SC-3, Fire Emergency Plan 49 1163 A-50.2, R. E. Ginna Health Physics Orientation Program 49

PCN 5 78 Procedure a Title Meetin I 78 1161 SM 75.24, MSZ Jet, Shielding Installation Rework 49 1121 M-47.1, Inspection of Pressurizer Internals 49 1165 ET-l, Rod Control System 49 964 M-43.8 Eddy Current Testing of Series 44 Steam 49 Generator Tubes 1153 M-64.1, Periodic Surveillance and Minor Maintenance 49 of Limitorque Rotor Operated Safeguard Valves 1151 M-37.53, RHR Core Deluge Valve 852A, and 852B Isolation 49 and Packing 1152 M-37.55, Spray Additive Tank Discharge Valves HCV-836A/B 49 Inspection and Maintenance 1150 M-37.51, Component Cooling Water Surge Tank Local Vent 49 Valve RCV-017 Repair and Inspection 1149 M-37.50, MOV-721 RHR to "B" Zoop Maintenance and 49 Inspection 1148 M-37.49, Level Control Valve from "B" RCS Loop LCV-427 49 Maintenance and Inspection 1147 M-37.48, Component Cooling From RC Pumps MOV-759 and/or 49 MVT-759B Isolation and Maintenance 1146 M-37.47, RHR Pump Suction MOV-851A or MOV-851B 49 Maintenance and Inspection 1145 M-37.42, MOV-813 and/or MOV-814 Isolation and Maintenance 49 1144 M-37.40, Maintneance cn Wtor Driven Auxiliary Feedwater 49 Pumps Discharge Valves MCV-.4007 or MOV-4008 1154 M-64.2, Limitorque Valve Operator Maintenance and 49 Inspection 1143 M-37.36.4, Nuclear Sample System Air Operated 49 Valve Maintenance 1142 M-37.35, Valves 3504 and 3505; Main Steam 49 to Turbine Driven Auxiliary Feed Pump Maintenance 1141 M-37.19, Removal of Limitorque Motors 49 and/or Repacking of Gate Valves 860, A,B.C,GD

PCN 4 78 Procedure & Title 1140 M-37.16J, Inspection and Maintenance 49 of the Rotor Drive Auxiliary Feed Pump Recirculation Control Valve 1139 N-37.15.1, Inspection and Maintenance of 49 48" Butterfly Valve, Model R-lA8 Valve Operator 1138 M-37.15, Replacing or adjusting Rubber Seat 49 Seat in Purge Supply and Exhaust Valves 1137 N-37.10, Grinnell Diaphragm Valves, Air- 49 Operated, Maintenance 1136 M-37.3, Maintenance on Copes-Vulcan 49 Diaphragm Operated Control Valves for AOV 1131 M-ll.10, Major Inspection of Service Water 49 Pump 1129 M-ll.14, Inspection and Maintenance of 49 Ingersol Rand Pumps 1128 N-37.0, Repacking of Air Mtor Operated 49 Valves 1127 M-11.15, RHR Pumps Inspection/Maintenance 49 1134 M-11.5B, Major Mechanical Inspection of the 49 Auxiliary Feed Pumps for Pump 1132 N-ll.5K, Turbine Driven Auxiliary Feedwater Pump Major or Mechanical Inspection 1135 M-11.5C, Minor Mechanical Inspection of the 49 Auxiliary Feed imps for Pump 1133 N-11.5E, Pipefitters Inspectxon of Nctor 49 Driven Auxiliary Feed Pump for Pump 1130 M-ll.12.1, Safety Injection Pump, Mechanical Inaction, None A-54.6, Health Physics 'Ibur week of 6/12/78 49 1242 ET-16, Auxilairy Feedwater System 50

, 1288 S-4.4, Spent Resin Removal to Shipping 50 Casks

PCN 0 78 Procedure a Title Meetin 5 78 1272 M-43.6.1, Installation of "A" Steam Generator 50 Ring Nozzle Cover In Preparation for Explosive Tube Plugging 1273 M-43.13.1, Steam Generator Ring Nozzle Cover 50 Removal After Explosive Tube Plugging 1266 EM-156, Removal RT-3 of Reactor Trip Itic Relay, 50 1265 M-70.1, Steam Generator Level Deviation Bistable 50 Setpoint Change 1231 PZ-15, Containment Purge Supply and Exhaust 50 Damper Closure Time 1232 ET-18.1, lA Instrument Air Compressor Capacity 50 Check 1233 ET-18.2, 1B Instrument Air Compressor Air 50 Capacity Check 1234 PT-18.3, 1C Instrument Air Compressor Air 50 Capacity Check 1235 ET-22, Containment Penetration Leak Rate Testing 50 1236 PZ 22.22, Fuel Transfer Flange Leak Rate Test 50 1237 RSSP-2.6, Emergency Diesel Start and Breaker 50

.Closure Time 1239 RSSP-7.0, Control Rod Drop Test 50 1240 RSSP-8.0, RTD Cross Calibration Check 50 1241 PR-5, Relay Calibration and Trip Test 4160 50 Volt Auxiliaries 1271 M-43.31, Hand Hold Gasket Seating Surface 50 Repair 1274 M3.29, Steam Generator Inner Sleeve 50 Removal and/or Split Ring Assembly Removal 1275 M-3.2, Reactor Cavity Cleanup and Decontami- 50 nation 1276 M-54.2, Condenser Water Box Leak Testing with 50 Freon

PCN I 78 Procedure & Title Meeting I 78 1277 M-43.27, Steam Generator Secondary Side 50 Handhole Cover Removal 1278 M-43.28, Steam Generator SEcondary Side 50 Manway Cover Removal 1270 M-18.1, Drum Preparation for Waste Evaporator 50 Bottoms 1281 M-43. 26, Installation of Steam Generator 50 Secondary Manway Cover 1207 S-3.3D, CVCS Cation Demineralizer Bed Opera- 50 tions Using "A" Dekorating D. I. Unit 1206 S-3.3F, Reactor Coolant System pH Control 50 1205 S-3.4I, Recirculation of Monitor Tank for 50 nArs or nBss Moni 1204 S-3.4K, Releasing Monitor Tank to Discharge 50 Canal 1203 S-3.4M, b$ onitor Tank Recirculation through 50 Evaporator D. I.

1202 S-3.4N, Calculations for Boron Recycle 50 Process Using 2 HVZ's 1201 S-3.4P, Transferring Concentrates from 50 Boric Acid Evaporator Feed Tank to Waste Evaporator Feed Tank for Drumming 1200 S-3.4R, Transfer of any CVCS HUZ to Another 50 CVCS HVZ 1198 S-3.4T, Regeneration of the Boric Acid 50 Evaporator "B" Condensate D. I.

1197 S-3.5, Deborating Demineralizer "B" Regen- 50 eration 1196 S-4.1F, Waste Condensate Polisher Recircu- 50 lation 1195 S-4.1L, Reverse Osmosis Unit Startup and 50 Shutdown 1194 S-4.1N, Transfer Waste Holdup Tank to "A" 50 Monitor Tank

PCN I 78 Procedure a Title Meetin I 78 1193 S-4.1R, Transfer of Chemical Drain Tank to 50 Reverse Csmosis Feed Tank 1192 S-4.1S, Alternating Waste Evaporator Cart- 50 ridge Demineralizers 1191 S-.4.1T, Alternating Waste Evaporator Conden- 50 sate Polishing Demineralizers 1190 S-4.1U, Velocity Flush of R-18 50 1189 S-4.1Y, Laundry Tank Release Using Chemical 50 Drain Pump 1188 S-4.5. 2, Waste Condensate Polishing Deminer- 50 alizer Resin Replacement 1187 S-4.5.4, Boron Recycle Base Reneval D. I. 50 Resin Replacement 1186 S-4.5.5, Boron Recycle Cation D. I., Resin 50 Replacement 1185 S-4.5.6, Spent Fuel Pit, D. I. Resin Replace- 50 ment 1184 S-4.5.7, Letdown Mixed Bed D. I. Resin Replace- 50 ment 1183 S-4.5.8, Eetdown Cation D. I. Resin Re- 50 placement 1182 S-5, Nuclear Sample Room Sampling System 50 1181 S-8, Component Cooling system

,1199 S-3.4S, Regeneration of the Boric Acid 50 Evaporator "A" Condensate D. I.

1180 S-9J, Blending to EST '0 1179 S-9K, Transferring Water From Monitor Tank 50 to Spent Fuel Pit 1178 S-9L, Batching Boric Acid and Transferring 50

,to Spent Fuel Pit 1177 S-9M, Adding Reactor Makeup Water to Spent 50 Fuel Pit

PCN I 78 Procedure 6 Title Meetin 5 78 1176 S-10.1, Part Length Rod Control 50 1175 S-14.2, Determination of the Percent of 50 Tech. Spec. Limits for Radioactive Release 1209 S-3.2C,. Placing and Removing from Service 50 "B" Hot Leg Charing Valve 392A 1208 S-3.3C, H2 or 02 Removal from Primary System 50 by Bumping VCT with N2 1174 S-16.3, Vent N2 from the "A" Accumulator 50 1173 S-16.4, Vent N2 from the "B" Accumulator 50 1172 S-16.9, Charging of the "A" Accumulator with 50 Nitrogen 1171 S-16.10, Charging of the "B" Accumulator with 50 Nitrogen 1170 S-16.13, Water Makeup to the Accumulator 50 1169 S-23.5, Post Accident Charcoal Filter Opera- 50 tion 1168 S-25. 5, Steam Generator Radioactive Release 50 1167 S-26.4, Computor Rod Postion Alarm Program 50 1267 M-57.1, Power Range NIS Detector Replacement 50

,1260 E-29.1, Zass of Normal Feedwater (Not Recover- 50 erable) 1259 E-26.4, Mrbine Trip Without Reactor Trip 50 1258 E-16.2, High Iodine 1313 in the Plant Vent . 50 1257 E-13.1, Power Range NIS Malfunction (PR 41, 50 42, 43, 44) 1018 A-l, Radiation Control Manual 50

'1229 HP-6.2, Posting of Contaminated and Airkarne 50 Areas 1247 0-2.1, Normal Shutdown to Hot Shutdown 50 1226 PT-2.3.1, Post Accident Charcoal Filter 50 Dmtpers

PCN N 78 Procedure 6 Title Meeting N 78 1269 HP-1.1, Issuing Personnel Dosimeters 50 1227 HP-1.3, External Exposure Records 50 1264 M-18, Acid Cleaning of Waste Evaporator 50 1262 HP-4.3, Work Permit Use 50 1268 T-7E, Water Treatment-Carbon Filter Backwash 50 1263 S-4.1D, Drumming Waste Evaporator Bottoms 1286 A.C.-1701, Quality Assurance Records 50 1246 0-1.2, Plant From Hot Shutdown to Steady Load 50 1245 0-1.3, Reactor Startup for Training 50 1244 PZ-34.0, Startup Physics Test Program 50 1248 PZ-23.16A, Containment Isolation Valve Leak 52 Rate Testing "A" Steam Generator Blowdown 1249 PZ-23.16B, Containment Isolation Valve Leak 52 Rate Testing "B" Steam Generator Blowdown 1250 PZ 23.17A, Containment Isolation Valve Leak 52 Rate Testing Containment Pressure Sensing Transmitter PT-945 and PT-946 1251 PZ-23.17B, Containment Isolation Valve Leak 52 Rate Testing Containment Pressure Sensing Transmitter PT-947 and PT-948 1252 ET-23.17C, Containment Isolation Valve Leak 52 Rate Testing Containment Pressure Sensing Transmitter PT-949 and PT-950 1255 PZ-23.18B, Containment Isolation Valve Leak 52 Rate Testing "B" Containment Spray Header 1256 ET-23.19, Containment Isolation Valve Leak 52 Rate Testing Safety Injection System 1253 ET-23.20, Containment Isolation Valve Leak 52 Rate Testing R., C. D. T. Gas Header 1254 PZ-23.21, Containment Isolation Valve Leak 52 Rate Testing R. C. D. T. Gas Analyzer

1 PCN I 78 Procedure a Title Meetin I 78 719 M-37.57, Containment D. I. Check Valve 8419 52 Mainteannce 1293 &~~9.1, Manipulator Crane 52 1287 RF-2A, Requirements for Reactor Head Removal 52 1283 RF-8.1, Step-by-Step Fuel Loading and Maps 52 1279 M-15.1, "A" or "B" Diesel Generator Removal 52 From Service 1285 M-15.3.1, 1A Diesel Generator Solenoid Valves 52 5907 and/or 5907A Maintenance 1317 HP.3, Air Ejector Gas Sampling 52 1318 HP-9.2, Primary to Secondary Leakage Detection 52 and Measurement 1328 PZ-3, Containment Spray Pumps NaOH 52 Additive System 1315 M-18, Acid Cleaning of Waste Evaporator 1329 0-6.9, Operating Limits for Ginna Station 52 Transmission 1295 . S-9M, Adding Reactor Makeup Water to Spent 52 Fuel Pit 1348 . W-1701, Quality Assurance Records 53 1347 0-6.11, Routine Operations Check Sheet 53 1343 = A 37 1 I System Modification Requirements 53 1032 A-50.9.2, Non-Licensed Staff Retraining 53 Program 1323 GS-31.0, Ecor Alarm System 53 1322 GS-28.0, Inspection of Personnel Vehicles and 53 Packages 1342 A-37.0, Conduct of Operations for Safety- 53 Related Evaluations as related to Facility or Rxiifications, Special Tests, Experiments 1341 A-50.2, R. E. Ginna Health Physics Orientation 53 Program,

PCN 5 78 Procedure a Title Meetin 5 78 1340 PC-18.3, Determination of Chloride kp Speci- 53 fic Ion Electrode 1330 '-40.1, Hydraulic Snubber stallation Procedure Reaaval and Rein-. 53 1324 XT-34.1, Initial Criticality and ARO Boron 53 Concentration 1326 M-40.8, Functional Testing of Hydraulic 53 Snubbers 1325 RSSP-12, Testing of Primary and Secondary 53 Relief Valves in Test Stand 1354 AR-AA-'2, AVT Water Treatment Panel Trouble 55 1355 AR-AA-4, Standby Auxiliary Feedwater HVAC 55 Trouble 1356 AR-AA-5, Standby Auxiliary Feedwater Pump CAR C or D Trip 1357 AR-AA-6, KS Overpressurization Army'Inhibit 55 Loop "A" Select 1358 AR-AA-7, RCS Overpressurization Arrq/Inhibit 55 Loop "B" Select 1359 AR-AA-9, Condensate Booster Pump Pressuriza- 55 tion Trip 1360 AR-AA-10, Condensate Booster Pump Trip 55 1361 AR-AA-14, N2 Accumulator, V-801A Tow Pressure 55 1362 AR-AA-15, N Accumulator, V-801B Imr Pressure 55 1363 AR-AA-22, KS Overpressurization Protection High Pressure Train "A" 1364 AR-AA-23, RCS Overpressurization Protection 55 High Pressure Train "B" 1366 AR-AA-25, Condensate System Low Pressure 55 1368 AR-AA-29, Condensate +stem Low Pressure Drop 55 1367 AR-AA-30, Condensate Booster Pump Low 55 Suction Pressure

PCN I 78 Procedure a Title Meetin I 78 1365 AR-AA-31, RCS Overpressurization Protection 55 High Pressure Train "C" 1332 NC-1, A List of Sample Chemical Parameters 55 and Sampling Schedule 1333 HP-7.3, Calibration of Alpha Survey Instruments 55 1331 GS-41, Photography at Ginna Station 55 1385 SC-3.17.3, Fire Brigade Drill Records 55 1386 SC-3.17.1, Planning, Conduct and Evaluation 55 of a Fire Emergency Drill

. 1387 SC-1.10, Planning Conduct and Evaluation of a Radiation Emergency Drill 1388 A-50.11.4, General Employee Fire Txaining 55 1389 A-S0.11.2, Fire Department Familiarization 55 1390 A-50.11.1, Fire Brigade Training 1391 A-50.11.0, Fire Fighting Organization and 55 Training Program 1392 A-50.7, Emergency Coordinator Training Program 55 1336 PZ-6.3.1, Power Range Nuclear Instrumentation 55 System, Channel 41 1337 PZ-6.3.2, "

System, Channel 42 1338 PT-6.3.3, Power Range Nuclear Instrumentation System, Channel 43 1339 PT-6.3.4, Power Range Nuclear Instrumentation 55 System, Channel 44 1370 M-ll.8C, Reactor Coolant Pump Major Inspec- 55 tion in Service Electrical 1371 M-ll.8B, Reactor Coolant Pump Seal Inspec- 55 tion and Service Mechanical 1383 A-30.2, Plant Procedure Classification, Review, 55 Approval and Distribution Requirements

PCN I 78 Procedure & Title Meetin I 78 1372 A-30.3, Plant Procedure Content and Format 55 Requirements 1377 AR-F-2, Alarm Response Procedure 55 1345 PL'-2.1, Safety Injection System Pumps 55 1335 SC-1.12B, Station Call List 55 1369 A-60.3, Calibration Surveillance Program for 55 Instrumentation ~ignent or Safety-Related Components 1373 M-15.1, "A" or "B" Diesel Generator Removal From Service 1374 M-15.3.2, Diesel Generator, FLSI, Fuel Oil 55 Level Switch High Maintenance 1376 M-18, Acid Cleaning of Waste Evaporator 55 k

1378 S-4.1C, Liquid Waste Process Operation and 55 Shutdown 1384 S-7B, Reactor Coolant Low Pressure Purif ication 55 1393 0-6.11, Routine Operations Check Sheet 55 1382 PT-2.10, Check Valve Exercising Test Requirements- 55 Cold/Refueling Shutdown 1381. RSSP-l. 5, Valve Interlock Verification Feedwater 55 Isolation 1349 WC-7, Chloride Determination 56 13SO WC-6, Potentiometric Determination of Boron 56 1351 WC-S, Ammonia and Organic Nitrogen Determination 56 1352 WC-3, Anal inity Determination 1353 WC-4, Amelia Determination ky Direct Nessleriza- 56 tion 1402 EM-205, Turbine Runback Relay in RPI System 56 Replacement 1442 EM-186, CR-9 Relay in RPI System Replacement 56

PCN 5 78 Procedure a Title Meetin 5 78 1417 M-44.10, Isolation of MCC 1K and Restoring to Service 1418 M-31, Stator Replacement for Part-Length Control 56 Rod Drive System 1419 M-37.18E, ~ction and Repair of Auxiliary 56 Building Sump Pump Discharge Check Valves 1420 M-37.18F, Inspection and Repair of 1A 56 Auxiliary Building Sump Tank Pump Discharge Check Valve 1421 M-37. 43, Accumulator Drain Valves 844A and 844B Inspection and Repair 1422 M-37.27.1, Testing and Replacement of 1B 56 Steam Generator Blowdawn Sample Isolation Valves CV-77 *5736) or Manual Valve 5734 1423 M-ll.26.1, Heater Drain Pump Mechanical Seal 56 Inspection and Maintenance 1424 M-11.26, Heater Drain Pump Inspection and 56 Maintenance 1425 M-1125, Main Feedwater Pump ~ed Increase 56 Inspection and Maintenance 1426 M-11. 23, worthington Double-Helical Rotary 56 Pump Inspection and Maintenance 1427 M-ll.24, Main Feed Pump Inspection and 56 Maintenance 1428 M-ll.28, Rotary Air Samples Inspection and 56 Maintenance 1429 M-S3.1, Containment Air Loc3cs Door Gasket 56 Replacement 1430 M-53.2, Containment Air Lock equalizing Valve 56 Cleaning and Inspection 1431 M-37.16M, Isolation of V-356 for Maintenance 56 1432 M-37.18D, Check Valve 1713 Isolation N2 to R.C.D.T.

1433 M-37.20, Inspection and Repair of Main Steam 56 Isolation Valves

PCN 5 78 Procedure a Title Meetin 5 78 1434 M-37.18C, Inspection of Rockewell Check Valves 56 in the Waste Gas and Nitrcxjen System 1435 M-37.2.1, Repacking Pressurizer Power Relief 56 Guard Valves 515 and 516 1436 M-37.44, Immediate Boration Valve MDV-350 56 Maintenance 1397 A-50.9.1, Ginna Station Engineers (Cadet, 56 Assistant Station and Station) Training Program 1143 A-52.2, Control of Locked Valve Operation 56 1444 KT-5.10, Process Instrumentation Reactor 56 Protection Channel Trip Test (Channel 1) 1445 FZ-5. 20, Process Instrumentation Reactor '56 Protection Channel Trip Test (Channel 2) 1446 PZ-5. 30, Process Instrumentation Reactor 56 Protection Channel Trip Test (Channel 3) 1447 PT-5.40, Process Instrumentation Reactor 56 Protection Channel Trip Test (Channel 4) 1443 KT-16, Auxiliary Feedwater System 1403 KT-6.3. 2, Power Range Nuclear Instrumentation 56 System, Channel 42 1405 PZ-23.18A, Containment Isolation Valve Leak 58 Rate Testing "A" Containment Spray Header 1406 PZ-23.24, Containment Isolation Valve 58 Leak Rate Testing Reactor Support Goolers (Inlet and Outlet) 1407 PZ-23.26, Containment Isolation Valve Leak 58 Rate Testing Auxiliary Coolant System to "A" Reactor Coolant Pump 1408 . PT-23.27, Containment Isolation Va1ve Leak 58

.Rate Testing Auxiliary Coolant System to "B" Reactor Coolant Pump 1409 PZ-23.28, Containment Isolation Valve Leak 58 Rate Testing Auxiliary Coolant System Frcm "A" Reactor Coolant Pump

PCN 5 78 Procedure 6 Title Meetin 5 78 1410 PZ-23.29, Containment Isolation Valve Leak 58 Rate Testing Auxiliary Coolant System From "B" Reactor Coolant Pump 1411 PT-23.30, Containment Isolation Valve Leak 58 Rate Testing Auxiliary Coolant System Excess Letdown (Supply and Return) 1455 A-30.3, Plant Procedure Content and Foremat 58 Requirements 1450 AR-K31, Fire System Alarm Panel 58 1449 M-71. 2, Module Rework/Test Procedure 58 1451 0-6.2, Main Control Board System Status 58 Verification 1456 ET-2. 2, Residual Heat Removal System 58 1438 RSSP-6. 0, Containment Integrated Leakage 58 Rate Test 1334 M-40, Surveillance and Maintenance of Hydraulic 58 Snubbers 1475 S-7C, Transferring and Purification of ERST 58 Water Frcm RWST to SFP 1489 HP-12.3, Selection of Respirators 59 1496 HP-7.5, Pocket Dosimeter Accuracy and Leak 59

'est 1501 P-3, Precautions, Limitations, and Setpoints 59 P-3 Chemical and Volume Control System 1500 HP-1. 2, External Exposure Limits 59 1494 M-40, Surveillance and Maintenance of Hydraulic 59 Snubbers 1495 S-15.1, Flux Mapping Normal Procedure 59 1491 AR-F-10, Pressurizer Low Pressure Alarm 59 1483 0-6.6, Correcting Measured Boron Concen- 59 tration to Reference Full Power Expected Boron Concentration

PCN 4 78 Procedure a Title Meetin I 78 1704 CP-80.2, Calibration Procedure for Inside MicnxLeters 1705 CP-80.3, Calibration Procedure for Venier Calipers 69 1613 PZ-13.4.7, Protomatic Deluge Valve System Testing 69 System 1614 XT-13.4.8, Protomatic Deluge Valve System Testing

'ystem I8 1615 KT-13.4.9, Protomatic Deluge Valve System Testing System h

1666 , PZ-13.4.10, Protomatic Deluge Valve System Testing System 510 I'708 S-4.1.22, Waste Evaporator Feed Tank Pump Isolation 69 Restoration 1747 ET-13.1.12, Containment Post-Accident (Recirc) and/or Auxiliary Filter RPD Testing 1728 PZ-23.36, Containment Isolation Valve Leak Rate Testing, Purge Exhibit 1729 RSSP-8. 0, RTD Cross Calibration Check 69 1785 GS-28.1, Electronic Seatch Ekpipment Testing 69 1787 E-1.2, Loos of Coolant Accident 69 1783 CP-37.2, law Voltage Power Supply NQ-402 69 Adjustments 1782 CP-35. 3, Intermediate Raneg N-35 Calibration 69 1781 CP-35.4, Intermediate Range N-35 Bistable Relay 69 Drivers Calibration 1780 CP-36.0, Intermediate Range Channel N-36 69 Calibration and/or Maintenance 1778 CP-36.2 N-36, General Reinstate Procedure 69 1777 CP-36.3, Intermediate Range N-36 Calibration 1776 CP-36.4, Intermediate Range N-36 Bistable Relay 69 Drivers Calibration

PCN I 78 Procedure 6 Title Meetin I 78 1775 CP-37.0, Calibration and/or Maintenance of 69

.Comparator Drawer N-37 1774 CP-37.1, Zaw Voltage Polar Supply NQ-401 69 Adjustments 1773 CP-37.3, Low Voltage Power Supply NQ-403 69 Adjustments 1772 CP-37.4, Calibration of Level Trip Bistable Relay Driver NC-401 1771 CP-38.0, Calibration and/or Maintenance of 69 Detector Current Gomparator Drawer 1770 CP-38.1, Calibration and/or Maintenanoe of Power 69 Supply NQ-601 1769 CP-38.2, Calibration and/or Maintenance of Power 69 Supply NQ-602 1768 CP-38. 3, Calibration and/or Maintenance of Averaging Circuit NM601 1767 CP-38. 4, Calibration and/or Mainenance of Averaging Circuit %1602 1766 CP-40.0, Calibration and/or Maintenance of 69 Delta Flux Controllers CHannel 4 1765 CP-ill.ll, Reactor Nakeup Water Flow Power Supply 69 FQ-ill 1764 CP-209.3, Nx3el HFM-3, Hand and Foot Monitor 69 Calibration 1763 CP-210.0, Calibration and/or Maintenance 5KS 69 Channel R-10A or R-10B 1754 CP-212. 0, Calibration and/or Maintenance of MS 69 Channel R-12 1750 CP-213.0, Calibration and/or Maintenance of %IS 69 Channel R-13 1730 CP-35. 2, General Reinstate Procedure 69 1732 CP-40.0, Calibration and/or Maintenance of Delta 69 Flux Controllers Channel 4

PCN I 78 Procedure 6 Title Meetin I 78 1733 CP-30.0, Calibration and/or Maintenance of Delta Flux Controllers, Channel 3 1734 CP-20.0, Calibration and/or Maintenance of Dleta 69 Flux Controllers, Channel 2 1735 CP-10.0, Calibration and/or Maitnenance of Delta Flux Controllers, Channel 1 1736 CP-8.0, Calibration Alignment of T Avg. and Delta T at Zero Power Channel 4 1737 CP-7.0, Calibration Alignment of T Avg. and 69 Delta T at Zero Power Channel 3, Zaop B, Unit 1 1738 CP-6.0, Calibration Alignment of T Avg. and Delta T at Zero Power, Channel 2, Zaop A, Unit 2 1739 CP-5.0, Calibration Alignment pf T Avg. and 69 Delta T at Zero Power, Channel 1, Zaop A, Unit 1 1740 CP-2.20.5, Calibration Alignment of Pulse to 69 Analog Converter Bank 1741 CP-2.20.4, Calibration Alignment of Pulse to Analog Converter Bank "C" 1742 CP-2.20.3, Calibration Alignment of Pulse to 69 Ana1og Converter Bank "B" 1743 CP-2.20.2, Calibration Alignment of Pulse to 69 Analog Converter Bnak "A" 1744 CP-2.20.1, Calibration of Pusle to Analog Converter Power Supply 1745 CP-2.20.0, Calibration and/or Maintenance of RPI 69 Pulse to Analog Converter 1751 CP-212.3, Replacement of Detector for BNS 69 Channel R-12 1752 CP-212.2, Calibration of R-12 Detector 69 1760 CP-210.3, Replacement of Detector for RMS Channel 69 R-10A or R-10B 1759 CP-211.0, Calibration and/or Maintenance of RES Channel R-ll 1758 CP-211.1, Calibration of Ratemeter Drawer R-ll 69

PCN I 78 Procedure a Title Neetin I 78 1757 CP-211.2, Calibration of R-11 Detector 69 1756 CP-211.3, Replacement of Detector for 69 R-ll R'%hannel.

1755 CP-211.4, Check of Flew Control Systen for R-ll 69 and R-12 1762 CP-210.1, Calibration of Bate Meter Drawer R-10A 69 or R-10B 1761 CP-210.2, Calibration of R-10A or R-10B Detectors 69 1779 CP-36.1, N-36, General Defeat 1731 CP-35.1, N-35, General Defeat 69 1753 CP-212.1, Calibration of Batemeter Drawer R-12 69 1701 Rl 76-17.3, Screen House Intake Heater Cable Tray 71 Rework 1905 EM-207, Replacing Splices and Splice Sleeves 71 for Pressurizer Level and Pressure Channels 1906 B4-208, Containment Recirculation Fan Splices 71 1907 220209, YDV-852A and 852B Splices 71 2022 9 IP-30, Visual Examination of Supports 72 1788 CP-220.3, Replacement of Detector for R1S 72 Channel R-20 1789 CP-220.2, Calibration of R-20 Detector 72 1790 CP-220.1, Calibration of Batemeter Drawer R-20 72 1791 CP-220. 0, Calibration and/or Maintenance of EBS 72 Channel R-20 1792 CP-219.3, Replacement of Detector for RMS Channel 72

-R-19 1793 CP-219.2, Calibration of R-19 Detector 72 1794 CP-219.1, Calibration of Batemeter Drawer R-19 72 1795 CP.-219.0, CAlibration and/or Maintenance of MS 72 Channel R-19

PCN 5 78 Procedure a Title Meetin N 78 1796 CP-218.3, Replacement of Detector for EHS Channel 72 R-18 1797 CP-218.1, Calibration of Batemeter Drawer R-18 72 1798 CP-218.0, Calibration and/or Miantenance of Et1S 72 Channel R-18 1799 CP-217.3, Replacement of Detector for EBS Channel 72 R-17 1800 CP-217.2, Calibration of R-17 Detector 72 1801 CP-217.11 Calibration of Ratemeter Drawer R-17 72 1802 CP-217.0, Calibration and/or Maintenance of NS 72 Channel R-17 1803 CP-216.3, Replacement of Detector for RNS Channel 72 R-16 1804 CP-216.2, Calibration of R-16 Dtector 72 1805 CP16.1, Calibration of Batemeter Drawer R-16 72 1806 CP-216.0, Calibration and/or Maintenance of 72 RMS Channel R-16 1807 CP-215.3, Replacement of RIS Channel R-15 Detector 72 1808 CP-215.1, Calibration of Batemeter Drawer R-15 72 1809 CP-215.0, Calibration and/or Maintenance of MS 72 Channel R-15 1810 CP-214.3, Replacement of Detector for R4S Channel 72 R-14 1811 CP-214.2, Calibration of R-14 Detector 72 1812 CP-214.1, Calibration of Ratemeter Drawer R-14 72 1813 CP14.0, Calibration and/or Maintenance of %IS 72

" Channel R-14 1814 CP-213.4, Check of R-13 and R-14 Flow Control 72 System 1815 CP-213.3, Replacement of Detector for RMS Channel 72 R-13

P PCN 4 78 Procedure a Title Meetin I 78 1482 0-1.2, Plant From Hot Shutdown to Steady 59 Load 1476 0-2.1, Normal Shutdown to Hot Shutdown 59.-

1479 PT-6.1, Source Range Nuclear Instrumenta- 59 tion System, Channels 1478 PZ-16, Auxiliary Feedwater System 59 1457 M-40.1, Hydraulic Snubber Removal and Re- 59 installation Procedure 1459 M-73.2, Welding on Stainless Steel Piping or 59 Components 1458 M-73.3, Welding on Carbon Steel Piping and 59 Components 1505 RD-9, Preparing Waste for Shipment or Storage 59 1506 RD-10, Shipping Radioactive Material 59 1507 S-9R, Containment Sump "A" Water to Spent 59 Fuel Pit and the Return to Normal 1488 SC-1.12B, Station Call List 59 1511 SC-1.3A, Site Radiation Emergency (Shift 59 Foreman and Control Rocm 1460 M-ll.8F, Reactor Coolant Pump Internal 59 Inspection 1461 M-ll.8H, Reactor Coolant Pump Impeller 59 Assembly Decontamination 1462 M-ll.5C, Minor Mechanical Inspection of the 59 Auxiliary Feed Pumps for Pump 1463 M-ll.5B, Major Wchanical Inspection of the 59 Auxiliary Feed Pumps for Pump 1465 M-66.1, Boric Acid Evaporator Feed Tank 59 Heater Replacement 1466 M-32, Use of Circuit Reaker Multi-Amp Test 59 Unit 1467 M-56.2, Multi-Cable Electrical Penetration 59 Epoxy Seal Repair

PCN I 78 Procedure a Title Meetin I 78 1468 M-51.2, D. C. Voltage Monitor Relays for 59 Safeguard rains 1469 M-71.1, Bistable 431B for Pressure Controller 59 PRV-431C Replacement 1470 M-72.1, Replacement Primary Zoop RPD 59 1471 EM-154, Steam Generator, Handhole Cover 59 Gasket Leak Repair Using "Furmanite" Process 1474 M-43.1.1, Steam Generator Insert Removal Steam Generator 1472 M-16.1, Service Water Discharge Header For 59 Turbine Building Isolation 1473 M-43. 20A IIAI'team Generator Secondary Side 59 Pressure Test 1065 A-2. 1 f

~ Re ce iving, Inventory and Sh ipnen t of 59 Fuel 1497 PL'-31, Safeguard Pump Bearing Temperature 59 Check 1490 HP-7.4 , Calibration of Neutron Surveey Ins tru- 59 ments 1352 WC-3, Alkalinity Determination 59 1508 SC-l. 7F , Emergency Radiation bhnitoring 60 Off-Site Survey Team N9F 1509 SC-1.7H , Emergency Radiation bbnitorin 60 Off-Site Survey Team N9H 1549 A-50.12, Emergency Plan Training Program 60 1562 A-60.3, Calibration Surveillance Program ram for 60 Insttrumentation/equipment of Safet y Rel at ed Components PZ-13.1.0, Testing and/or Maintenan ceo f th e 1558

'd Fix Fire Detection and Extinguishi1ng 60 System

PCN I 78 Procedure 6 Title Meetin I 78 1563 ET-13.1.9, Halon System Testing (Resetting) 60 Computer Room and Relay Room 1517 M-40. 6, Steam Generator Hydraulic Shock 60 Suppressors Leakage Test and Inspection 1570 EC-.18. 2, Fluoride Determination 60 1566 PC-18.1, Chloride Determination 60 1610 6 RI-199, Sludge Removal from Waste Holdup 61 1659 Tank 1576 NC-7.2, Determination of Chloride ky Specific 62 Ion Electrode 1519 WC-8, Amperometric Determination of Chlorine 62 in Water 1520 WC-8.1, Chlorimetric Determination of 62 Chlorine Water 1590 WC-10.0, Solution pH Determination ky Glass 62 Electrode Method 1602 ET-5.10, Process Instrumentation Reactor Protection Channel Trip Test (Channel 1) 1605 ET-5. 20, Process Instrumentation Reactor Protection Channel'rip Test (Channel 2) 1604 ET-5.30, Process Instrumentation Reactor 62 Protection Channel Trip Test (Channel 3) 1603 ET-5.40, Process Instrumentation Reactor 62 Protection Channel Trip Test (Channel*4) 1609 ET-5.10, Process Instrumentation Reactor 62 Protection Channel Trip Xhst (Channel 1) 1610 EM-199, Sludge Removal from Waste Holdup 62 Tank 1643 EM-158, Seal Welding MOV-721 RHR to "B" 62 Loop 1654 M-12. 2, Inmdiate-Boration ET 113 Gaskets 62 Replacement 1648 M-18.3, Waste Evaporator Inlet Check Valve 62 1769 Replacement

PCN 5 78 Procedure 6 Title Meetin 0 78 1649 M-37.1A, Repacking of Pressurizer Spray 62 Valves 431A and 431B 1647 M-37.18G, Inspection and Repair of 1B 62 Auxiliary Building Sump Tank Pump Discharge Check Valve 1645 M-37.18H, Containment Spray Pump Discharge Check Valve 862A and/or 2B Inspection and Maintenance 1644 M-37.26.1, Testing and Repair of 1A Steam 62 Generator Blowdown Sample Isolation Valves CV6 (5735) 1651 M-37.27, Inspection and Repair of 3B Steam 62 Generator Blowdown Isolation Valve CV-71 (5737) 1650 M-37.47, RHR Pump Suction MOV-851A or 62 MOV-851B Maintenance and Inspection 1646 M-37.48, Component Cooling from RC Pumps 62 MOV-759A and/or MOV-759B Isolation and Maintenance 1652 M-37.49, Level Control Valve From "B" RCS 62 Loop ZCV-427 Maintenance and Inspection 1653 M-37.50, MOV-721 RHR to "B" Loop Maintenance 62 and Inspection 1594 PC-2, Gross Degassed Beta-Gamma Activity in 62 Primary Coolant 1066 A-2.8, Special Nuclear Materia1 Inventoey and 62 Record Requirements 1591 RD-8, Liquid Radwaste Compositing and Analysis 62 1574 PC-21, Hydrogen Peroxide Analysis 62 1575 PC-88 Reactor Coolant System Chemical Additions 62 1573 XC-10, Radioiodine Determination in Primary 62 Coolant Unit T-10A Extraction 1598 RSSP.3, Air Supply for Integrated Leak Rate 62 Test

PCN N 78 Procedure 6 Title Meetin N 78 1597 RSSP-7.3, Reactor Trip logic Relays Drop Out 62 T>i&s 1592 PC-5, Gamma Isotopic Analysis of Degassed Primary Coolant 1642 RI-157, Repair of Piping Leak on the B. A. 62 Concentrates Holding Tank Pump Discharge 1513 KT-23.25, Containment Isolation Valve Leak 62 Rate Testing Purge Supply 1512 Pl'-23.36, Containment Isolation Valve Leak 62 Rate Testing Purge Exhaust 1608 HP-4.3, Work Permit Use 62 1595 HP-12.2, Medical Check, Fitting and Training 62 of Personnel Using Respirators 1607 HP-12.5, Maintenance of Respirators 62 1606 M-53.1, Containment Air Lodges Gasket Re- 62 placement 1572 0.4.1, equilibrium Indicated Axial Flux 62 Difference Determination 1611 0-6.11, Routeine Operations Check List 62 1577 PC-18.3, Determination of Chloride by Specific 62 Ion Electrode 1578 PI'-2.2, Residual Heat removal System 1596 A-l.l, Locked Radiation Areas 62 1612 A30.3, Plant Procedure Content and Format Requirements Hone GS-1.2, Ginna Station Security Event Report 62 (2) 8/12/78 and 8/18/78 None A-54. 4, Duty Engineer Responsibilities 8/14/78 None A-54.6, Health Physics Tour 8/148 62 None 0-6.7, Weekly Alarm Status Check 8/7/78 62 1695 S-27.348A, Valve 348A, Isolation 65

PCN I 78 Procedure a Title Meet'in 5 78 1499 PZ-13.1.10, Smoke Detector System Testing 1699 A-30.3, Plant Procedure Content and Format 66 Retirements 1660 E-l.l, Safety injection System Actuation 1661 E-l.2, Loss of Coolant Accident 1665 E-16.1, High Activity Radiation Ronitoring 66 System 1698 PZ 6.3.1, Power Range Nuclear Instrumentation System, Channel 41 1697 PT-6. 2, N.I.S. Intermediate Range Channels 1696 PZ-6.3. 2, Power Range Nuclear Instrumentation

.System Channel 42 1666 M-ll.SB, Major bhchanical Inspection of the Auxiliary Feed Pumps 1690 RF-52, Inspection Procedure for Exxon Nuclear Fuel 66 Assemblies at R. E. Ginna 1686 SC-1.12B, Station Call List 1691 HP-12.6, Issuance, Prayer Use and Return of Respirators 1579 , ET-23.44, Containment Isolation Valve Leakrate 66 Testing Leakage/Test Depressurization 1580 PT-23.45, Containment Isolation Valve Leakrate 66 Testing Leakage Test/Instrumentation 1581 PT-23.48, ll 66 Testing Deadweight Tester 1978 PT-23. 49, Containment 66 Testing Construction Fire Service Water 1583 PT-23 50A ll ll ll ll 66 Testing Containment Post Accident Air Sample (Clean Int. Building) 1584 PZ-23.50B, Containment Isolation Valve Leak rate 66 Testing Containment Post Accident Air Sample (Controlled Int. Building)

PCN I 78 Procedure 6 Title Meetin I 78 II If II 1585 PT-23. 50C, 66 Testing Containnent Post Accident Air Salrple (Auxiliary Building)

PT-23 o 51A, If II I'I 1586 66 Testing "A" Hydrogen Recombiner (Pilot and Main) 1587 PT-23. 51B, If tl If II Testing "B" Hydrogen Recombiner (Pilot and Main)

If If II 1588 PZ 23 51CI 66 Testing "A" and "B" Hydrogen Recombiner Oxygen Makeup tf If It 1514 PT 23 34 66 Testing Depressurization at Power 1515 PZ-23.33, 66 Testing Service Air 1516 ET-23. 32, Testing Instrument Air 1551 PZ-23.43, II n If 66 Testing Leakage Test Supply Header ET-23. 42, I'I II II 1552 Testing Leakage Test Depressurization 1553 PZ-23.40, Containment Isolation Valve Leakrate 66 Testing Auxiliary Steam Supply and Condensate Return 1554 PZ-23.39, Containment Isolation Valve Leakrate Testing Demineralized Water 1555 PT-23.46, Containment Isolation Valve Leakrate 66 Testing Nitrogen to Accumulators 1556 PT-23.22, "

Testing R. C. D. T. Discharge If II II II 1557 pg 23 23 66 Testing Sump "A" 1617 PT-22, Containment Penetration Leakrate Testing 1618 PT-22. 1, Hquipnent Hatch Door Seal Leakrate Test 66

PCN O 78 Procedure a Title Meetin I 78 1619 PZ-22.2, Personnel Hatch Door Seal Leakrate Test 66 1620 PZ-22.3, Persnel Hatch Between Door Volume Leakrate Test 1621 ~22.4, shipment Hatch Between Door Volume 66 Leakrate Test 1622 PZ-'22.5, Personnel Hatch Canopy Leakrate Test 66 1623 PZ-22. 6, equipment Hatch 66 1624 PZ 22.7, Hcpipment Hatch 0-Ring 66 1625 PZ-22. 8t Mechanical Manifold "A" 1626 ET-22. 9, II IIBtt II 66 1627 ET-22.10, IICII II 1628 PZ-22.11, ItEII ft

,1629 PZ-22.12, IIFII ll 66 1630 PT-22.13, IIQII II 66 1631 PT-22.14, IIHI'I II 1632 PT-22.15, II tl If 1 66 1633 PT-22.16, Mechanical Manifold "J" Leakrate Test 66 1634 'Z-22.17, II tfKfl It II 66 1635 PZ-22.18 Electrical Manifold IX, Leakrate Test II II Ngl It If 1636 PT-22.19, 66 1637 PZ-22.20, Illl tl 'I 66 1638 PT-22. 21, Mechanical Manifold "L" Leakrate Test 66 1639 PZ22..22, Fuel Transfer Flange Leakrate Test 1640 PZ-23, Containment Isolation Valve Leakrate Testing 66 1673 M-73.3, Welding on Carbon Steel Piping or Components 66 1672 M-73.2, Welding on Stainless Steel Piping or 66 Components

PCN 0 78 Procedure a Title Meetin I 78 1589 PC-15. 1 , Solution pH Determination ion ~ Glass Electrode Method 1593 PC-7, Iine 131, equivalent Calculat'C9.

1565 .0, Determination of Chromate 66 1569 NC-7.1, Fluoride Determination 1571 WC-9.1, Determination of Total Ch romium in Water 1550 HP-l..5, 5 Dosimeter Discrepancy Evaluation 66 1568 RI 78-1458 , Spe nt Fuel Pat Roughing 0

Filter Frame 1712 A-30.2, Plant Procedure Clas f 67 and Distribution pproval 1713 S-3.4F , Boron Bo Recycle Process Shutdown 1671 SC-1.15, In ct'pe ion of Emergency Ekpipment 1693 PT-ll.l, Heat Trace ace Circuitry Functional Check 67 1694 PZ-ll. 60, Cell Battery Banks "A" and "B" 67 1715 P-l, Precautions imitations and Setpoints r Control and Protection System L'ac 1670 HP-12.4, Fitti'ng and Testing of Respirators 67 1714 Heat Exchanger Valve, HCV 625 1711 GS-34.0, Vital Areas 67 1709 RF-S.O, Fuel Assembly and Core Co nent 67 ment Prerequisites an and Precautions Pre 1688 GS-42.0, Site Designated Vehicles 67 1786 EM-2 Sp 1 ice Covering Removal on thee lD Con-tainment Recirculation Fan 1702 CP-80.0 Cal'eters ibratxon Procedure forr Outs'd e Micro- i 1703 CP-80.1, Calibration 'on Procedure for Micrometer 69

PCN 5 78 Procedure a Title Meetin 4 78 1816 CP-213.2, Calibration of R-13 Detector 72 1817 CP-213.1, Calibration of . Ratemeter Drawer R-13 72 1818 CP-403.5, T Avg (3 Sec) Lag Unit IN-403BB 72 1819 CP-403.4, T Avg Dana Amplifier PN03A 1820 CP-403.3, T Avg Dual Current Source TT-403 72 1821 CP-403.2, Reinstate of T Avg Signal for Channel 3 72 1822 CP-403.1, Defeat of T Avg Signal Channel 3 1823 CP-402.9, T Avg Indicator TI-402 72 1824 CP-402.8, T Avg Repeater 'IN-402W 72 1825 CP-402.7, T Avg Repeater 'IN-402C 72 1826 CP-402.5, T Avg (3 Sec) Lag Unit 'IN-402BB 72 1827 CP-402.4, T Avg Dana Amplifier IN-402A- 72 1828 CP-402.3, T Avg Dual Current Source TT-402 72 1829 CP-402.2, Reinstate T Avg Signal for Channel 2 72 1830 CP-402.1, Defeat of T Avg Signal Channel 2 72 1831 CP-401.8, T Avg Repeater IN-401W 72 1832 CP-401.7, T Avg Repeater 'IN-401C 72 1833 CP-401.6, T Avg Bistable TC-401A 1834 CP-401. 5, T Avg (3 Sec) Lag Unit 'IN-401BB 72 1835 CP-401.4, T Avg Dana Amplifier 'IN-401A 72 1836 CP-401.3, T Avg Dual Current Source TZ-401 1837 CP-401.1, Defeat of T Avg Signal Channel 1 72 1838 CP-401.2, Reinstate T Avg Signal Channel 1 72 1839 CP-221.2, Calibration of R-21 Detector 1844 CP-426.8, Pressurizer Level Indicator LI-426 72 1845 CP-426.7, Pressurizer Level Repeater LN-426B 72

PCN I 78 Procedure 6 Title Meetin 4 78 1846 CP-426.6, Pressurizer Level Repeater LM-426A 72 1847 CP-426.5,'ressurizer Level Bistable LC-426A/B 72 1848 CP-426.4, Pressurizer Level Power Supply LQ-426 72 1849 CP-426.2, General Reinstate 426 Pressurizer Level 72 1850 CP-426.1, General Defeat Procedure 426 Pressurizer 72 Level 1851 CP-426.0, Calibration and/or Maintenance of 426 72 Pressurizer Level Channel 1852 CP-416.7, Reactor Coolant Flow Indicator FI416 72 1853 CP-416.6, Reactor Coolant Flow Repeater FM-416 72 1854 CP-416.5, Reactor Coolant Flow Bistable FC-416 72 1855 CP-416.4, Reactor Coolant Flow Power Supply 72 FQ-416 1856 CP-416.2, General Reinstate Procedure of Reactor 72 Coolant Flow Channel 416 1857 CP-416.1, General Defeat Procedure of Reactor 72 Coolant Flow Channel 416 1858 CP-416.0, Calibration and/or Maintenance of 72 Reactor Coolant Flow Channel 416 1859 CP-415.7, Reactor Coolant FLow Indicator FI-415 72 1860 CP-415.6, Reactor Coolant Flow Repeater B4-415 72 1861 CP-415.5, Reactor Coolant Flow Bistable EC-415 72 1862 CP-415.4, Reactor Coolant FLow Power Supply 72 FQ15 1863 CP-415. 2, General Reinstate Procedure for Reactor 72 Coolant Flow Channel 415 1864 CP-415.1, General Defeat Procedure of Reactor 72 Coolant Flow Channel 415 1865 CP-415.0, Calibration and/or Maintenance of 72 Reactor Coolant Flow Channel 415

PCN N 78 Procedure a Title Meetin 5 78 1866 CP-414.6, Reactor Coolant Flow Repeater Fill-414 72 1867 CP-414.5 Reactor Coolant Bistable Flow FC-414 72 1868 CP-414.4, Reactor Coolant Flow Power. Supply 72 FQ14 1869 CP-414.2, General Reinstate Procedure of Reactor 72 Coolant Flow Channel 414 1870 CP-414.1, General Defeat Procedure of Reactor 72 Coolant Flow Channel 414 1871 CP-414.0, Calibration and/or Maintenance of 72 Reactor Coolant Flow Channel 414 1872 CP-413.7, Reactor Coolant Flow Indicator FI-413 72 1873 CP-413. 6, Reactor Coolant Flow Repeater Fill-413 72 1874 CP-413.5, Reactor Coolant Flow Bistable PC-413 72 1875 CP-413.4, Reactor Coolant Flow Polar Supply 72 FQ13 1876 CP-413.2, General Reinstate Procedure Reactor 72 Coolant FLow Channel 413 1877 CP-413. 1, General Defeat Procedure Reactor 72 Coolant Flow Channel 413 1878 CP-413.0, Calibration and/or Maintenance of 72 Reactor Coolant Flow Channel 413 1879 CP-412.7, Reactor Coolant FLow Indicator FI-412 72 1880 CP-412.6, Reactor Coolant Flow Repeater EH-412 72 1881 CP-412.5, Reactor Coolant Flow Bistable EC-412 72 1882 CP-412.4, Reactor Coolant Flow Power Supply 72 FQ-412 1883 CP-412.2, General Reinstate Procedure Reactor 72 Coolant Flow Channel 412 1884 CP-412.1, General Defeat Procedure Reactor Coolant 72 Flow Channel 412 1885 CP-412.0, Calibration and/or Maintenance of Reactor 72 Coolant Flow Channel 412

PCN 5 78 Procedure a Title Meetin N 78 1886 CP-411.7, Reactor Coolant Flow Indicator FI-411 72 1887 CP-411. 6, Reactor Coolant Flow Repeater ETC-411 72 1888 CP-411.5, Reactor Coolant Bistable EC-411 72 1889 CP-411.4, Reactor Coolant Flow Power Supply 72 FQ-411 1890 CP-411. 2, General Reinstate Procedure of Reactor 72 Coolant Flow Channel 411 1891 CP-411.1, General Defeat Procedure of Reactor 72 Coolant Flow Channel 411 1892 CP-411. 0, Calibration and/or Maintenance of 72 Reactor Coolant Flow Channel 411 1893 CP-406.10.1, Defeat of Dleta T Setpoint 1 Channel 2 72 1894 CP-404.9, T Avg Indicator TI-404 72 1895 CP-404.8, T Avg Repeater 1H-404W 72 1896 CP-404.7, T Avg Repeater TM 404C 72 1897 CP-404.5, T Avg (3 Sec) Lag Unit KM-404BB 72 1898 CP-404.4, T Avg Dana Amplifier 'IR-404A 72 1899 CP-404.3, T Avg Dual Current Source TZ-404 72 1900 CP-404.2, Reinstate of T Avg Signal for 72 Channel 4 1901 CP-404.1, Defeat of T Avg Signal Channel 4 72 1902 CP-403.8, T Avg Repeater 'BI-403W 72 1903 CP-403.7, T Avg Repeater XK-403C 72 1904 CP-403.6, T Avg Bistable XC-403A 72 1909 CP-463.7, Steam Generator Level Repeater LM-463B 72 1910 CP-463.6, Steam Generator Level Bistable LC-463E 72 1911 CP-463.5, Steam Generator Level Bistable 72 LC-463C/D

PCN N 78 Procedure & Title Meetin N 78 1912 CP-463.4, Steam Generator Level Pomr Supply 72 LQ63 1913 CP-463.2, Reinstate of A Steam Generator Level 72 Channel 463 1914 CP-463.1, Defeat of A Steam Generator Level 72

..Channel 463 1915 CP-463.0, Calibration and/or Maintenance of 72 Steam Generator Level Channel 463 1916 CP-462.8, Steam Generator Level Indicator LI-462 72 1917 CP-462.7, Steam Generator Level Repeater EM-462 72 1918 CP-462.5, Steam Generator Level Bistable LC-462A/B 72 1919 CP-462.4, Steam Generator Level Power Supply 72

~462 1920 CP-462.0, Calibration and/or Maintenance of Steam 72 Generator Level Channel 462 1921 CP-461.8, Steam Generator Level Indicator LI-461 72

.1922 Steam Generator Level Repeater ZZ-461B 'P-461.7, 72 1923 CP-461.6, Steam Generator Level Repeater LM-461 72 1924 CP-461.5, Steam Generator Level Bistable 72 LC-461A/B 1925 CP-461.4, Steam Generator Level Power Supply 72

,LQ-461 1926 CP-461.0, Calibration and/or Maintenance of 72 Steam Generator Level Channel 461 1927 CP-449.11, Pressurizer Pressure Indicator PI-449B 72 1928 CP-449. 9, Pressurizer Pressure Repeater PM-449C 1929 CP-449.10, Pressurizer Pressure Indicator PI-449 72 1930 CP-449.8, Prewsurizer Pressure Repeater EM-449A 72 1931 CP-449.6, Pressurizer Pressure Bistable PC-449A 72 1932 CP-449.5, Pressurizer Pressure Lead/Lag Unit 72 PM49B

i PCN N 78 Procedure a Title Meetin N 78 1933 CP-449.4, Pressurizer Pressure Power Supply 72 P~449 1934 CP-449. 2, General Reinstate Procedure for 72 Pressurizer Pressure Channel 449 1935 CP-449.1, General Defeat Procedure for 72 Pressurizer Pressure Channel 449 1936 CP-449.0, Calibration and/or Maintenance of 72 Pressurizer Pressure Channel 449 1937 CP-431.11, Pressurizer Pressure Indicator PI-431 72 1938 CP-431.10, Pressurizer Pressure Repeater P4-431C 72 1939 CP-431.9, Pressurizer Pressure Rpeater PM-431A 72 1940 CP-431.8, Pressurizer Pressure Bistable PC-431J 72 1941 CP-431. 5, Pressurizer Pressure Lead/Lag Unit 72 PM31B 1942 CP-431. 4, Pressurizer Pressure Power Supply 72 rg-431 1943 CP-431. 2, General Reinstate Procedure Pressurizer 72 Pressure Channel 431 1944 CP-431.1, General Defeat Procedure 431 Pressurizer 72 Pressure Channel 431 1945 CP-431.0, Calibration and/or Maintenance of 72 Pressurizer Pressure Channel 431 1946 CP-430.10, Pressurizer Pressure Indicator PI-430 72 1947 CP-430.9, Pressurizer Pressure Repeater PM-430A 72 1948 CP-430.6, Pressurizer Pressure Bistable PC-430A 72 1949 CP-430.5, Pressurizer Pressure Leak/Zag Unit 72 PM-430

.1950 CP-430. 4, Pressurizer Pressure Power Supply PQ-430 72 1951 CP-430.2, General Reinstate Procedure 430 72 Pressurizer Pressure Channel 1952 CP-430.1, General Defeat Procedure 430 Pressurizer 72 Pressure Channel

PCN N 78 Procedure & Title Meetin 5 78 1953 CP-430.0, Calibration and/or Maintenance of 430 72 Pressurizer Pressure cannel 1954 CP-429.9, Pressurizer Pressure Bistable PC-429E 72 1955 CP-429.6, Pressurizer Pressure Bistable PC-429A 72 1956 CP-429.5, Pressurizer Pressure Lead/Lag PM-429B 72 1957 CP-429.4, Pressurizer Pressure Power Supply 72 1958 CP-429. 0 Caiibration and/or Maintenance of 72 Pressurizer Pressure Channel 429 1959 CP-428.0, Calibration and/or Maintenance of Pressurizer 72 Pressure Channel 428 1960 CP-427. 7, Pressurizer Level Indicator LI-427 72 1961 CP-427. 6, Pressurizer Level Bistable LC-427A/C 72 1962 CP-427.5, Pressurizer Level Bistable LC-427A/C 72 1963 CP-427.4, Pressurizer Level Power Supply ZQ-427 72 1964 CP-427.0, Calibration and/or Maitnenance of 72 Pressurizer Level Channel 427 1965 CP-427.1, Defeat of 427 Pressurizer Level 72 1966 CP-427.2, Reinstate 427 Pressurizer Level 72 1967 CP-428.1, Defeat of 428 Pressurizer Level 72 1968 CP-428.2, Reinstate 428 Pressurizer Level 72 1969 CP-429. 2, General Reinstate Procedure of 72 Pressurizer Pressure Channel 429 1970 CP-429.1, General Defeat Procedure of 72 Pressurizer Pressure Channel 429 1987 CP-466.4, Feedwater Flow Power Supply FQ-466 72 1988 CP-466.2, Reinstate of A Feedwater Flow Channel 466 72 1989 CP-466.1, Defeat of A Feedwater Flow Channel 466 72 1990 CP-466.0, Calibration and/or Maintenance of Feedwater 72 Flow Channel 466

PCN 5 78 Procedure a Title Meetin N 78 1991 CP-465.11, Steam Flow Recorder FR-465 1992 CP-465.10, Steam Flow Indicator FI-465 72 1993 CP-465.9, Steam Flow Repeater PR-465D 72 1995 CP-465.8, Steam Flow Repeater ER-465C 72 1996 CP-465.7, Steam Flow Square Root Extractor PR-465B 72 1997 CP-465.6, Steam Flow Multiplier/Divider FM-465A 72 1998 CP-465.5, Steam Flow Bistable FC-465A 72 1999 CP-465.4, Steam Flow Power Supply FQ-465 72 2000 CP-465.2, Reinstate of A Steam Flow Channel 465 72 2001 CP-465.1, Defeat of A Steam Flow Channe; 465 72 2002 CP-464. 9, Steam Flow Repeater FN-464D 72 2003 CP-464.8, Steam Flow Repeater EN-464C 72 2004 CP-464.7, Steam Flow Square Root Extractpr 72 FM-464B 2005 CP-464. 5, Steam Flow Bistable FC-464A 72 2006 CP-464.4, Steam Flow Power Supply FQ-464 72 2007 ~

CP-464.2, Reinstate 'of A Steam Flow Channel 464 72 2008 CP-464.1, Defeat of A Steam Flow Channel 464 72 2009 CP-463.8, Steam Generator Level Indicator LI0463 72 2010 CP-466.5, Feedwater Flow Square Root Extractor 72 FM-466A 1982 PZ-28, Control Room Air Handling Unit Efficiency 72 Test of HEPA and Charcoal Filter Banks in the Accident Axle 1984 PT-29.1, Auxiliary Building HEPA and Charcoal 72 Filter Efficiency 'I@st 1985 ET-29.2, Controlled Access HEPA and Charcoal Filter 72 Efficiency 'Ihst 1840 PC-7, Iodine 131 Calculation 72

PCN N 78 Procedure 6 Title Meetin N 78 1841 PC-6, E Total Activity and Maximum Acitivity 72 in the Primary Coolant 2011 RD-5, Ventilation System Releases 72 1980 P 9g Precautions, Limitations and Setpoints, P-9g 72 Radiation Honitoring System 1843 A-54.5, Bulk Storage of Ccanbustible Materials and 72 Their Use 1976 FT-16, Auxiliary Feedwater System 72 1842 A-60.1, Ginna Station Technical Specification 72 Surveillance Program 1977 M-67.1, Protomatic Deluge Valve System Maintenance 72 System Numbers 7, 8, 9, 10 1981 M-37.13, Inspection and Maintenance of A loop 72 Accumulator Discahrge Check Valve V-842B 1986 A-54, Ginna Station Administrative and Enginering Staff 72 Responsibilities 1974 PT-18.3, 1C Instrument Air Gompressor Air Capacity 72 Check 1975 ~18.2, 1B Instrument Air Gompressor Air Capacity 72 Check 1973 PT-20.1, Control Air System Integrity for Steam 72 Line Power Relief Valves 1972 PZ6, Containment Fan Recirculation Unit HEPA 72 Filter Bank 'lbsting 1971 ISI-1.2.9, Quality Group A Inservice Inspection 72 1994 RSSP-2. 4, Containment Recirculation Fan Service 72 Mater Flow Test 1983 XT-29, Containment Purge and Exhaust A and B 72 Efficiency Xhst of HEPA and Charcoal Filter Banks 1908 A-50.12, Emergency Plan Training Program 72 1784 SM 75-34.24, Rework of Hanger SGB-19 72 S-12.2, Operator Action in the Event of Indication 72 of Significant Increases in Leakage Items a-i

PC@ 4 78 Procedure & Title Meetin N 78 2039 A-20, Control Room Logs 73 2040 A-3, Containment Access 73 2019 SC-1.12C, Specialized Call List 73 2014 SC-l, Radiation Emergency Plan 73 2015 SC-l. 7E, Emergency Radiation monitoring On-Site 73 Survey Team 59E 2016 SC-1.7G, Emergency Radiation monitoring On-Site 73 Survey Team 59G 2017 SC-1.3B, Site Radiation Emergency (Emergency 73 Coordinator and Survey Center Assignees) 2018 SC-1.15, Inspection of Bnergency equipment 73 2020 SC-l. 11A, Immediate Re-entry 73 2038 CP-429. 2, General Reinstate Procedures of 73 Pressurizer Pressure Channel 429 2024 CP-430.1, General Defeat Procedure 430 73 Pressurizer Pressure Channel 2026 CP-429.1, General Defeat Procedure of 73 Pressurizer Pressure Channel 429 2027 CP-429.2, General Reinstate Procedure of 73 Pressurizer Pressure Channel 429 2028 CP-449.1, General Defeat Procedure for 73 Pressurizer Pressure Channel 449 2029 CP-449.2, General Reinstate Procedure for 73 Pressurizer Pressure Channel 449 2030 CP-431.1, General Defeat Procedure 431 73 Pressurizer Pressure Channel 2031 CP-431. 2, General Reinstate Procedure Pressurizer 73 Channel 431 2043 HP-12.1, Usage of Respirators 73 2042 HP-12.4, Fitting and Testing of Respirators 73 2044 . HP-12.2, Medical Check Fitting and Training of 73 Personnel Using Respirators

PCN I 78 Procedure 6 Title Meetin 5 78 2041 HP-12.3, Selection of Respirators 73 2035 RD-7, Liquid Waste Release 73 2037 HP.1, Controlled Area Entry 73 2033 QC-1502, Non-Conformance Report 73 2013 E-6.1, Loss of Component Coolaing During Power 73 Operation 2034 S-3.4P, Transferring Concentrates frcm Boric 73 Acid Evaporator Tank to Waste Evaporator Feed Tank for Dnzraning 2032 PT-2. 3, Safeguard Valve Operation 73 2045 SN 75-10.28, Service Water Piping to Air Handling 73 Units for Auxiliary Building Addition Remrk 2073 CP-467.0, Calibration and/or Maintenance of 74 Feedwater Flow Channel 467 2072 CP-467.1, Defeat of A Feedwater Flow Channel 74 2063 CP-468.11 Defeat of A Steam Generator Pressure 74 Channel 468 2064 CP-468.0, Calibration and/or Maintenance of 74 Steam Generator 468 2046 CP-471. 0, Calibration and/or Maintenance of 74 Steam Generator Level Channel 471 2159 CP-471.1, Defeat of Steam Generator Level 74 Channel 471 2152 CP-472.0, Calibration and/or Maintenance of 74 Steam Generator Level Channel 472 2151 CP-472.1, Defeat of Steam Generator Level 74 Channel 472 2138 CP-473.0, Calibration and/or Maintenance of 74 Steam Generator Level Channel 473 2139 CP-473.1, Defeat of B Steam Generator Level 74 Channel 473

PCN I 78 Procedure a Title Meetin I 78 2133 CP-474.1, Defeat of B Steam Flow Channel 474 74 2124 CP-475.0, Calibration and/or Maintenance of Steam 74 Flow Channel 475 2113 CP-476.0, Calibration and/or Maintenance of B 74 Feedwater Flow Channel 476 2112 CP-477.0, Calibration and/or Maintenance of Feedwater Flow Channel 477 2103 CP-477.1, D feat of B Feedwater Flow Channel 4 74 2123 CP-475.1, General Defeat Procedure Steam Flow 74 Channel 475 2055 CP-469.1, Defeat of A Steam Generator Pressure 74 Channel 469 2091 S-1BB Shutdown of Rx3 Drive Motor Generator Sets 74 2162 HP-12.6, Issuance, Proper Use and Return of 74 Respirators 2161 HP.3, Work Permit Use 74 2084 ISI-4.1.6, High Energy Inservice Inspection 74 2168 QC-1701, Quality Assurance Records 74 2163 E-1.2, Zass of Coolant Accident 74 2164 E-1.3, Steam Line Break Accident 74 2165 E-1. 4, Steam Generator Tube Rupture Accident 74 2077 SC-1.12B, Station Call List 74 2166 ET-6.1, Source Range Nuclear Instrumentation System 2086 PT-2.3, Safeguard Valve Operation 74 2087 PZ-2.4, Gold/Refueling MOV's Surveillance 74 2088 PZ-2.5, AOV's Quarterly Surveillance 74 2089 PZ-2.6, Gold/Refueling AOV's Surveillance 74 2167 ET-30, Containment Spray Nozzle Check of A & B 74 Rings

PCN 5 78 Procedure & Title Meetin N 78 2090 PZ-16.1, Auxiliary Feedwater System Flow Balance 74 2048 EM-. 210, Auxiliary Building Main Crane Replacement 74 of Driver Axle 2180 RI-211, Replacing Splices and Splice Sleeves for 74 Pressurizer Level and Pressure Channels 2160 S-3A, Startup of Rxl Drive Wtor Generator Sets 74 EN-190, Repair of Auxiliary Feedwater Hanger, 74 FNH-39 2083 M-40.4, Visual Leakage Inspection of High Energy 74 Piping 2190 E-4.1, Safeguard Buses Low Voltage Condition 76 2191 E-9, ?leakage Into the Component Cooling Loop 2192 E-23.2, Malfunction of N2 Reactor Coolant Pump Seal 2193 E-23.3, Malfunction of N3 Reactor Coolant Pump Seal 2194 E-23.4, Zass of Reactor Coolant Pump Seal 76 Injection Supply 2195 E-26.1, Erergency Shutdown Resulting from a 76 Reactor Trip from 8.5% Power or Less 2196 E-26.2, Emergency Shutdown Resulting from a 76 Reactor Trip When Between 50% and 8.5% Power 2197 E-31, Automatic Turbine Load Runback 76 2198 E-36, orator Actions to be Taken in the Event 76 of Alarm Conditions on the Turbine Vibration Instruments 2188 M-40.6, Steam Generator Hydraulic Shock Suppressors 76 Leakage Test and Inspection 2021 SC-1.12A, Immediate Call List 76 2187 S-15.3, Incore Wvable Detector Alignment 76 2185 A-54.3, Cpen Flame, Welding and Grinding Permit

PCN 4 78 Procedure a Title Meetin 5 78 2183 A-52.1, Shift Organization Relief and Turnover 76 2189 M-25, Adjustment Procedure for thermally 76 Compensating Supports cn Main Steam Header Safety Valves and Power Operated Relief Valves 2199 O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 2203 HP-10.3, Flow Rate Calibration of High Volume Air 76 Samples 2170 GS-l.l, Security Cgerations Plan 2171 GS-7.0, Security Officer's Report 2172 GS-14.0, Security Guard Response to Trespassers 2173 GS-15.0, Security Guard Action if There is a Portal 76 Monitor Alarm 2174 GS-16.0, Property Removal 76 2175 GS-21.1, Site Access Control (Security) for 76 Emergency Situations 2176 GS-21.1, Unoccupied Vital Area Access Control 76 2177 GS-24. 0, Security Surveillance Requirements and 76 Procedures 2178 GS-28.0, Search of Personnel, Vechiles, and 76 Packages 2179 GS-21. 0, Door Alarm System 76 2023 A-50.9.3, Health Physics Technician Training 76 and Responsibility Limits 2217 SC-1.12D, Management Call List 77 1560 XT-13. 5, Fire Spray System External Header/Nozzle 78 Inspection 1498 PT-13.1.14, Fire Barrier Penetration Seals ,78 2212 A-3, Containment Access 78 2216 RSSP-l. 1, Interlock Verification Residual Heat 78 Removal System

PCN I 78 Procedure & Title Meetin I 78 2215 ET-2.10.2, RHR System Core Deluge Check Valves 78 2220 A-17, Plant Operations Review Committee Operating 78 Procedure 2219 S-4.1S, Lictuid Waste Process Operation and Shutdown 78 2221 S-4. 1E, Waste Condensate Releases 78 2182 PT-2.5.1, Air Operated Valve Quarterly Surveillance 78 (Containment) 2225 S-4.2.9, Nitrogen Backup Supply to Auxiliary 79 Building 2233 S-2. 1A, Pre-Startup Lineup of Reactor Coolant 79 Pump 2232 S-3. 3B, Hydrogen Concentration Control 79 2231 S-4.2.2, 1A Waste Gas Compressor Startup 79 2230 S-4.2.4, Gas Decay. Tank Opeations 79 2229 S-4.2.6, Isolating Reactor Coolant Drain Tank 79 from Vent Header 2228 S-6, Nuclear Instrumentation System 79 S-14, Area and Process Radiation Monitoring System

'224 79 2251 - ~

KT-23.37, Containment Isolation Valve Leakrate 79 Testing Reactor Compartment Cooling Unit A 2252 PT-23.28, Containment Isolation Valve Leakrate 79 Testing Reactor Compartment Cooling Unit B 2247 P-4, Precautions, Limitations and Setpoints 79 Auxiliary Coolant System 2235 PZ-29.3, Auxiliary Building Ventilation Main 79 HEPA Filter Bank 'lhsting 2237 RSSP-2. 2, Diesel Generator Load and Safeguard 79 Sequence Test 2241 RSSP-2.1A, Safety Injection Functional Test 79 Alignment 2242 RSSP-1. 3, Valve Interlock Verification Chemical 79 Volume and Control System

PCN 5 78 Procedure s Title Meetin 5 78 2261 EM-190, Repair of Auxiliary Feedwater Hanger, 79 FNH-39 2262 EM-206, Spl-ice Covering Removal on the 1D 79 Containment Recirculation Fan 2263 EM-207, Replacing Splices and Splice Sleeves for 79 Pressure Level and Pressure Channels 2264 EM-208, Containment Recirculation Fan Splices 79 2265 EM-209, MOV-852A and 952B Splices 79 2269 HP-8.4, RAdioactive Source Inventory 79 2254 S-15. 2, Flux Mapping Emergency and Calibration 79 Procedure 2250 PZ-31, Safeguard Pump Bearing Temperature Check 79 2255 PZ-2.1, Safety Injection System Pumps 79 2256 ~2. 2, Residual Heat Reaaval System 79 2257 PT-2.7, Service Water System 79 2259 PT-3, Containment Spray Pumps and NaOH Additive 79

.System 2260 PT-16, Auxiliary Feedwater System 79 2249 . A-60.3, Calibration Surveillance Program for 79 Instrumentatio@+uipnent of Safety Related Components 2248 M-45. 4, Safeguard Motors Inspection 79 2270 HP-12.6, Issuance Proper Use and Return of 79 Respirators 2271 SM 75-7.25, HVAC Backfits Rework 79 2244 RF-2, Reactor Refueling .Outage Cgerations and Activities 2245 SC-1.12B, Station Call List 79 2234 A-54.6, Health Physics Tour 79 2236 ET 9, Undervoltage and Underfrequency Protection 79 11A and 11B 4160 Volt Buses

PCN I 78 Procedure & Title Meetin I 78 2238 RSSP-13.1, Hydro cn CVCS Class C Safety 79 Related Piping, Part 1 2239 RSSP-13.2, Hydro on CVCS Class C Sagety Belated 79 Piping, Part 2 2240 BSSP-14.1, Condenser Steam Dump Interlock Zoic 79 Test 2243 RSSP-1. 2, Valve Interlock Verification Safety 79 Injection System 2252 PT-13.1.1, Protomatic Deluge Valve System Testing 79 System Numbers 7, 8, 9, 10 2267 CP-70.6, West Pyrometer Calibration or Maintenance 79 Serial No.

2213 HP-1.6, Neutron Exposure 79 1655 M-73.4, Welding of Carbon Steel Piping or Components 79 to Stainless Steel Piping or Components 2200 WC.1, Bed+en DU-2 Calibration Procedure 79 2202 SC-3.16.15, Charging of Air Pak Cylinders 79 Compressor or Cascade Method 1477 SM 75-50.31, Jet Shielding Rework, Main Steam 79 and Feedwater 2246 M-40.8, Functional Testing of Hydraulic Snubbers 79 2268 9 -1601, Corrective Action 79 2137 EM-212, Repair of Boric Acid Cation DI Bad>wash 80 Drain Valve V-1163 2306 0-6.11, Routine ~rations Check 81 2303 A-52.8, Ginna Station Curve Book Directions 81 2302 HP.5, Pocket Dosimeters Accuracy/Leak Rate Test 81 2312 PZ-6.3.1, Polar Range Nuclear Instrumentation 81 System, Channel 41 2315 PZ-6.3.2, Power Range Nuclear Instrumentation 81 System, Channel 42

PCN I 78 Procedure & Title Neetin I 78 2314 PT.3. 3, Power Range Nuclear Instrumentation 81 System, Channel 43 2313 PT.3.4, Power Range Nuceear Instrumentation 81 System, Channel 44 2310 N-38.4, lA Constant Voltage Transformer Maintenance 81 2309 Calibration and/or Maintenance of 'P-250.6, 81 Wind Speed Voltage Signal Conditioner 2323 PT-13.4.10, Protomatic Deluge Valve System Testing 81 System 510A (412A Transformer) 2266 PZ-2.5.2, Air Operated Valves, Quarterly 81 Surveillances (Valves 112B and 112C) 2036 KT-35, Welding Rod Oven 'Ihermmeters 2324 PZ-13.4.10A, Protomatic Deluge Valve System 81 Testing System 10A (512A Transformer) 2327 S-4.5.4, Boron Recycle Base Removal DI Resin 81 Replacement 2328 S-4.5.5, Boron Recycle Cation DI Resin Replacement 81 2304 O-l.2. 2, Critical Rod Position Calculation 81 2331 SC-13.15.15, Emergency Fire shipment Locker 81 Inventory and Inspection 2369 M-38. 9, Battery Charger Maintenance and/or 82 Repair 2333 A-20, Control Room Zags 83 2326 N-56.1, Placement of Ceramic Fiber Penetration 83 Seals 2359 RD-2, Containment Purge Releases 83 2316 T-32C, Velocity Flush of the Fire Water System 83 2373 T-32C, Velocity Flush of the Fire Water System 83 2329 HP. 2, Self-Reading Dosimeter Use , 83 2353 PC-22, Hydrazine Determination 83 2354 PC-15. 2, Specif ic Conductance 83

PCN 5 78 Procedure 6 Title Meetin 5 78 2357 PC-13, Dissolved Oxygen Determination 83 2367 CP-250. 7, Calibration and/or Maintenance of 83 Synchro to DC Converter 2360 A-l.1, Locked Radiation Areas 83 2358 K',-l.l, Primary Coolant Anaylsis Schedule and 83 Limits 2347 M-37.38.1, Crosby Safety and Relief Valve 83 Maintenance for Valve No.

2273 A-30. 2, Plant Procedure Classif ication, Review, 83 Approval and Distribution Requirements 2273 A-30.3, Plant Procedure Content and Format 83 Requirements 2339 RD-6, Gas Decay Tank Releases 83 2342 CP-424.1, Calibration and/or Maintenance of 83 Pressurizer Liquid Temperature +I Converter 2343 CP-425. 3, Calibration and/or Maintenance of 83 Pressurizer Vapor Temperature Indicator TI-425 2344 CP-425.1, Calibration and/or Maintenance of 83 Pressurizer Vapor Temperature +I Concerter 2361 PC-16, Solids Determination 83 2345 ZN-211, Replacing Splices and Splice Sleeves for 83 Pressurizer Level and Pressure Channels 2346 ZM-212, Review of B. A. Recycle Cation DI 83 Backwash Drain Valve 1163 2335 QCIP-21, Shipping Package LL-50-100 Inspection 83 2236 QCIP-22, Shipping Package HN-100 Series 1 83 Inspection 2330 WC-2. 0, Metrohm E-415 Titractor Calibration 83 2372 &I 75-5.43, Final Reowrk for Standby Auxiliary 83 Feedwater 2305 A-30.3, Plant Procedure Content and Format 84 Requirements

PCN I 78 Procedure a Title Meetin I 78 2463 SM 75-5.38, Standby Auxiliary Feedwater System 84 Operational Testing 2456 CP-103. 0, Calibration and/or Maintenance of 84 Boric Acid Temperature Controller TIC-103 2457 CP-104.0, Calibration and/or Maitenance of 84 Boric Acid Tank ~rature Indicator TI-104 2458 CP-105.0, Calibration and/or Maintenance of 84 Boric Acid Tank lhmgerature Indicator TI-105 2459 CP-107.0, Calibration and/or Maintenance of Boric 84 Acid Tank ~rature Controller TCI-107 2451 S-4.4.1, Spent Resin Package Site Receipt and 84 Shigrent 2452 RD-10, Shipping Radioactive Material 2453 A-50.10, Operator Incident Review 84 2454 0-2.1, Normal Shutdown to Hot Shutdown 84 2375 RD-S, Waste Water Composite Calculations 84 2383 HP-4.1, Controlled Area Entry 84 2382 A-3, Containment Access 84 2381 Pl.3.1, Power Range Instrumentation System 84 Channel 41 2378 ET.3. 2, Power Range Instrumentation System 84 Channel 42 2379 PT-6.3.3, Power Range Instrumentation System Channel 43 2380 PX 6.3. 4 Power Range Instrumentation System 84 Channel 44 2377 RF-8.1, Step by Step Fuel Loading and Maps 84 2376 SC-1.12B, Station Call List 84 2386 CP-934. 1, Accumulator Level Transmitter LT-934 84 2394 CP-920.1, Placing of Refueling Water Storage 84 Tank Level Channel 920 Out of Service

PCN N 78 Procedure 6 Title Meetin N 78 2413 CP-485.1, Defeat of Turbine First Stage Pressure 84 Channel 485 2434 CP-482.1, Defeat of A Steam Generator Pressure 84 Channel 482 2441 CP-479.1, Defeat of B Steam Gnerator Pressure 84 Channel 479 2448 CP-478.1, Defeat of B Steam Generator Pressure 84 Channel 478 2348 HP-7.7, Calibration of Beta Survey Instruments 84 2322 M-43.16.1, Steam Generator Tube Sheet Photo-Mapping 84 2341 PC-1.4, Operation of Gamma Analyser 84 2364 WC-3. 1, Sodium Sulfate Determination 84 2362 WC-3. 2, Solids Determination 84 2351 WC-3. 3, Hardness Determination 84 2355 WC-10.1, Specif ic Conductance 84 2356 WC-12.0, Dissolved Oxygen Determination 84 2363 WC 12 1 g Dissolved Oxygen Determination AZ IDE 84 Method 2352 W-13.0, Hydrazine Determination 84 2350 NC-13.1, Free Hydroxide Determination 84 2365 WC-13. 2, Silica Determination 84 2366 WC-13. 3, Phosphate Determination 84 2349 WC-14.0, Oil and Grease Determination 84 QC-801, PDR Control of Accepted Materials, 2384 2385 Parts 85 and Components CP-934.3, Accumulator Level ~ Indicator LI-934 CP-934.2, Accumulator Level Bistable LC-934 86 2387 CP-920.7, Hefueling Water Storage Tank Level 86 Indicator LI-920

,I a.

J

PCN I 78 Procedure & Title Meetin " 78 2389 CP-920.6, Refueling Water Storage Tank Level 86 3istable LC-920C 2390 CP-920.5, Refueling Water Storage Tank Level 86 Bistable LC-9203/B 2391 CP-920.4, Refueling Water Stroage Tank Level 86 Power Supply LQ-920 2392 CP-921.0, Calibration and/or Maintenance P~ure for Refueling Water Storage Tank Level Indicating Alarm 2393 CP-920.2, Placing of Refueling Water Storage Tank 86 Level Channel 920 In Service 2395 CP-626.9, Residual Heat Removal Flow Channel 86 Controller FC-626A 2396 CP-626. 8, Residual Heat Removal Flaw Channel 86 2398 CP26.7, Residual Heat Removal Flow Indicator 86 FI-626 2399 CP-626. 6, Residual Heat Removla Flow Square 86 Root Extractor 2K-626 2400 CP-701Turbine Driven Auxiliary Feedwater Pump 86 Oil Pressure Regulator Adjustment 2401 CP-626.5, Residual Heat Removal Flow Channel 86 Bistable PC-626B 2402 CP-626. 4, Residual Heat Removal Power Supply 86 FQ-626 2403 CP-486.2, Reinstate carbine First Stage Pressure 86 Channel 486 2404 CP-486.9, Turbnie First Stage Pressure Indicator 86 PI-4 2405 CP-486.1, General Defeat Procedure Channel 486 86 First Stage Pressure 2406 CP-486.8, Turbine First Stage Pressure Transmitter 86 Repeater M-486A 2407 CP-486.7, Turbine First Stage Pressure Bistable 86 PC-486B

OTHER CHANGES, TESTS AND EXPERIMENTS PCN 0 78 Procedure & Title Meetin N 78 2408 .6, Turbine CP-486.6 First Sl'age Pressure I

.,~se PM-486B 'nit 2409 .5, TUrbine CP-486.5 First Stage Pressure B'abl is e PC-486~C 2411 .4, Turbine CP-486.4 First Stage Pressure Power 86 Supply PQ-486 2412 CP-485.9, Turbine First Stage Pressure Indicator PI-485 2414 CP-485.8, Turbine First Stage Pressure Repeater PM-485B 2415 CP-485.7, Turbine PM-485A First Stage Pressure Re pea ter 86 2416 CP-485.6, Turbine First Stage Pressure B'abl is e 86 PC-485C 2417 CP-485.5 , Turbine First Stage Pressure B'abl is e 86 PC-48~

2418 CP-485.4 , Turbine First Stage Pressure Power 86 Supply PQ-485 2419 CP-483.9, Steam Generator Pressure Indicator 86 PI-483 and PI-483B 2420 CP-4 83.8, Steam Generator Pressure PM-483C Re pea ter 2421 ~

CP-483..7, Steam Generator Pressure PM-483B pea Repe ter 86 2422 CP-483. 6 , Steam S Generator Pressure Bistabl e PC8 3A 86

.PC-483A 2423 CP-483.5, Steam Generator Pressure Lead~~" a g~g 86 Unit PM-483A 2424 CP-483.4, Steam Generator Pressure Power Supply PQ-483 2425 CP-483.2, Reinstate of B Steam Generatoror Pr essure 86 Channel 483 2426 CP-482. 9, Steam Generator Pressure Indicator 86 PI-482A and Remote PI-4828

PCN 5 78 Procedure 6 Title Meetin I 78 2427 CP-478.8, Steam Generator Pressure Repeater 86 PM-478C 2428 CP-483.1, Defeat of B Steam Generator Pressure 86 Channel 483 2429 CP-482.7, Steam Cinerator Pressure Repeater 86 PM-482B 2430 CP-482. 6, Steam Generator Pressure Bistable 86 PC-482A 2431 CP-482.5, Steam Generator Pressure Lead/Lag Unit PM-482A 2432 CP-482.4, Steam Generator Pressure Power 86 Supply PQ-482 2433 CP-482.3, Steam Generator Pressure Transmitter 86 PT-482 2435 CP-479. 8, Steam Generator Pressure Indicator PI-479 2436 CP-479.7, Steam Generator Pressure Repeater PM-479B 2437 CP-479.6, Steam Generator Pressure Bistable 86 PC-479A 2438 CP-479. 5, Steam Generator Pressure Lead/Lag 86 Unit PM-479A 2439 CP-479.4, Steam Generator Pressure Power 86 Supply FQ-479 2440 CP-479.2, Reinstate of B Steam Generator Pressure Channel 479 2442 CP-478.10, Steam Generator Pressure Indicator 86 PI-478 2443 CP-478.8, Steam Generator Pressure Repeater 86 Pi<1-478C 2444 CP-478.7, Steam Generator Pressure Repeater 86 PM-478B 2446 CP-478.6, Steam Generator Pressure Bistable 86 PC-478A

-100-PCN I 78 Procedure & Title Meetin I 78 2447 CP-478.5, Steam Generator Pressure Lead/Lag 86 Unit Pi4-478A 2449 CP-478.4, Steam Generator Pressure Power Supply PQ-478 2448 CP-478.1, Def at of B Steam Generator Pressure Channel 478 2441 CP-479.1, Defeat of B Steam Generator Pressure Channel 479 2434 CP-482.1, D feat of A Steam Generator Pressure 86 Channel 482 2413 CP-485.1, Defeat of Turbine First Stage Pressure 86 Channel 485 2394 CP-920.1, Placing of Refueling Water Storage Tank 86 Level Channel 920 Out of Service 2386 CP-934.1, Accumulator Level Transmitter LT-934 86 2450 CP-478.0, Calibration and/or Maintenance of Steam 86 Generator Pressure Channel 478 2445 CP-479.0, Calibration and/or Maintenance of 86 Steam Generator Pressure Channel 479 2410 CP.-486. 0, Calibration and/or Maintenance of 86 Turbine First Stage Pressure Channel 486 2397 CP-920.0, Calibration and/or Maintenance of 86 920 Refueling Water Storage Tank Level Channel 2388 CP-934.0, Calibration and/or Maintenance P~ure of 86 Accumulator Level Channel 934 2485 Rl 75-5.39, Standby Auxiliary Feedwater +stem 86 Rework 2464 RI 75-14.1, Batch Tank Recirculation Heat Trace 86 Installation 2340 M-2.2, Calibration of Specific Ion Electrodes 86 2370 M-38.8, lA Battery Charger Maintenance or Repair 86 2374 WC-14.1, Oil Film Thickness Determination 86 2362 WC-3.2, Solids Determination 86

(~

-101-PCN 5 78 Procedure a Title Meetin N 78 2461 M-43.0, Steam Generator Maintenance Test and 86 Repair Procedures 2462 M-43.16, Steam Generator Explosive Tube Plugging 86 Steam Generator 2467 HP-7.5, Pocket Dosimeter/Accuracy and Leak T st 2483 XT-13. 5, Fire Spray System External Header/h7ozzle Inspection 2484 ET-2.9. 2, Accumulator Discharge Check Valves 86 Quarterly Exercising 2371 SC-3.3.3, Fire Brigade Recall List 86 2085 SC-3.15.6, Fire Hose Reel Assembly Inspection 86 2334 S-12.4, RCS Leakage Surveillance Record 86 Instructions 2471 S-12. 4, RCS Leakage Surveillance Record 87 Instructions 2307 ~13.1.9, Halon System Testing (Resetting) 87 Computer Room and Relay Bxxn 2492 SC-3.3.1, Immediate Fire Notification 87 2493 SC-3. 15. 2, Fire Protection shipment Impairment 87 2494 SC-3.16. 6, Operating Instructions Fusible Link 87 Sprinkler System 2496 SC-3.16.7, Operating Instructions, Automatic 87 Deluge System 2495 SC-3.16. 8, Operating Instructions, Manual 87 Deluge Systems 2497 SC-3.16. 9, Operating Instructions, Halon 1301 87 Systems 2486 PP-20.1, Control Air System Integrity for 87 Steam Line Pawer Relief Valve 2487 PZ-5.10, Process Instrumentation Reactor 87 Protection Channel Trip Test (Channel 1)

-102-PCN I 78 Procedure & Title Meetin I 78 2488 ET-5. 20, Process Instrumentation Reactor 87 Protection Channel Trip Test (Channel 2) 2489 FZ-5. 30, Process Instrumentation Reactor 87 Protection Channel Trip Test (Channel 3) 2490 ZT-5. 40, Process Instrumentation Reactor 87 Protection Channel Trip Vest (Channel 4) 2472 PT-13.7, Fire Hose Reel Assembly Inspection 87 2479 A-30.3, Plant Procedure Content and Format 88 Retirements 2538 HP-l. 1, Issuing Personnel Dosimeters 88 2537 HP-l. 3, External Exposure Records 88 2543 HP-2.2, Whole Body Counter Operation 88 2512 HP-11.4, High Volume Air Sampling 88 2525 AR/Fl, High Condenser Pressure or Loss 88 of Both Recirculating Water Pumps 2526 AR/H, High Condenser Pressure 88 2527 AR/K-17, Zaw Vacuum Trip 88 2517 PT-23.17A, Containment Isolation Valve Leak 88 Rate Testing Containment Pressure Sensing

~ Transmitterr PT45 and PZ 946 2518 PZ-23.17B, Containment Isolation Valve Leak 88 Rate Testing Containment Pressure Sensing Transmitter, PT 947 and PZ48 2519 FT-23.17C, Ctainment Isolation Valve Leak 88 Rate Testing Containment Pressure Sensing Transmitter, PT49 and PT50 2520 PZ 23.19, Containemtn Isolation Valve Leak 88

, Rate Testing Safety. Injection System 2521 PT3.21, Containment Isolation Leak Rate 88 Testing RCDZ to Gas Anaylser 2499 S-27. 365A, V-365A Isolation 88 2540 0-6, Cperation and Process Nonitoring 88

-103-PCN 5 78 Procedure a Title Meetin I 78 2513 RD-1.3, Tritium in Containment Air Sampling 88

. and Analysis 2500 RD-3, Plant Vent Iodine and Particulate 88 Releases Sampling and Anylysis 2501 RD-6, Gas Decay 'ink Releases 88 2514 RD-12, Tritium in Air Sampling and Analysis 88 2544 GS-8.0, Detex Tours ky Security Guards 88 2522 CP-134.0, Zetdown Line Flaw Iaop 134 88 Calibration and/or Maintenance 2531 CP-501.1, Voltmeter Calibration for 480V 88 Circuit Bus 513 2532 CP-S01.2, Voltmeter Calibration for 480V 88 Circuit Bus 315 2533 CP-501.3, Voltmeter Calibration for 480V 88 Circuit Bus 114 (Safeguard) 2524 CP-501.4, Voltmeter Calibration for 480V 88 Circuit Bus 117 2535 CP-501.5, Voltmeter Calibration for 480V 88 Circuit Bus 116 Safeguard Device NN 2536 CP-501.6, Voltmeter Calibration for 480V 88 Circuit Bus 118 (Safeguard) 2542 CP-2030.0, 1B Mtor Driven Auxiliary Feedwater 88 Pump Discharge Pressure Loop 2030 2523 PC-13, Dissolved Oxygen Determination 88 2535 PC-1.4, Cperation of Gamma Analyzer 88

'2515 PC-l.l, Analysis Schedule and Limits, Primary 88 Coolant 2473 6 2455 A-l, Radiation Control Manual 88 2528 T-6.1, Regeneration of the Condensate Polishing 88 Mixed Bed Demineralizer Unit 2529 T-6.2, Air Bump and Rinse Cleaning of the 88 Condensate Polishing Mixed Bed Demineralizer Units

-104-PCN 4 78 Procedure a Title Meetin O 78 2516 T-6.1, Regeneration of the Condensate 88 Polishing Mixed Bed Demineralizer Unit 2503 PV-6.3. 1, Power Range Nuclear Instrumentation 88 System, Channel 41 2504 PZ-6.3. 2, Power Range Nuclear Instrumentation 88 System, Channel 42 2505 PZ 6.3.3, Power Range Nuclear Instrumentation 88 System, Channel 43 2506 PZ-6.3. 4, Power Range Nuclear Instrumentation 88 System, Channel 44 2475 PT-13.4.12, Alarm Valve System Testing Fire 88 System 512, Turbine Island Sprinkler 2476 PZ-13.4.13, Alarm Valve System Testing Fire 88 System f13 Service Building Sprinkler 2477 PZ-13.4.15, Alarm Valve System Testing, Fire 88 System 515 Warehouse 2482 Rl 74-28.1, Installation of i~cup Lines 88 to Condensate Storage Tanks 2637 CP-2093.3, Atmospheric Relief Valve 1B 90 (CV-57) Control Pressure Switch 2093 2636 CP-2093. 2, General Reinstate Procedure 2093 90 Ahnospheric Relief Valve 1B (CV-57) Control 2633 CP-2092.3, Atmosheric Relief Valve 1A (CV-56) 90 Control Pressure Switch 2092 2632 CP-2092.2, General Reinstate 2092 90 Atmospheric Relief Valve 1A (CV-56) Control 2629 CP-950.7, Containment Pressure Indicator 90 PI-950 2628 CP-950.6, Containment Pressure Repeater 90 PM-950 2627 CP-950. 5, Containment Pressure Bistable 90 PC-950k/8 2626 CP-950.4, Containment Pressure Power Supply 90 PQ-950

-105-PCN N 78 Procedure a Title Meetin g 78 2625 "

CP-950. 3, Containment Pressure Transmitter 90 PT-950 2624 CP-950. 22 Reinstate of B-3 Containment 90 Pressure Channel 950 2621 CP-949. 7, Containment Pressure Indicator 90 PI-949 2620 CP-949. 6, Containment Pressure Repeater 90 PM-949 2619 CP-949. 5, Containment Pressure Bistable 90 PC-949A/8 2618 CP-949. 4, Containment Pressure Power Supply 90 PQ-949 2617 CP-949.3, Containment Pressure Transmitter 90 PT-949 2616 CP-949. 2, Reinstate of B-1 Containemnt 90 Pressure Channel 949 2613 CP-948.7, Containment Pressure Indicator 90 PI-948 2612 CP-948.6, Containment Pressure Repeater 90 PM-948 2611 CP-948. 5, Containment Pressure Bistable 90 PC-94~

2610 CP-948.4, Containment Pressure Power Supply 90 PQ-948 2609 CP-948. 3, Containment Pressure Transmitter 90 PT-948 2608 CP-948. 2, Reinstate of B-2 Containmeyt 90 Pressure Channel 948 2605 CP-947.7, Containment Pressure Indicator 90 PI-947 2604 CP-947. 6, Containment Pressure Repeater 90 PN-947

-106-PCN I 78 Procedure 6 Title Meetin I 78 2603 CP-947.5, Gontainment Pressure Bistable 90 PC-947~

2602 CP-947. 4, Containment Pressure Power Supply 90 PQ-947 2601 CP-947. 3, Containment Pressure Transmitter 90 PT-947 2600 CP-947.2, Reinstate A-3 Containemnt Pressure 90 Channel 947 2597 CP-946. 7, Containment Pressure Indicator 90 PI-946 2596 CP-946. 6, Containment Pressure Repeater 90 PM-946 2595 CP-946. 5, Gontainment Pressure Bistable 90 PC-946A/8 2594 CP-946.4, Containment Pressure Power Supply 90 PQ-946 2593 CP-946. 3, Containment Pressure Transmitter 90

~946 2592 CP-946.2, Reinstate of A-2 Containment Pressure 90 Channel 946 2589 CP-945. 7, Containment Pressure Indicator 90 PI-945 2588 CP-945. 6, Containment Pressure Repeater 90 PM-945 2587 CP-945. 5, Containment Pressure Bistable 90 PC-945A/B 2586 CP-945.4, Containment Pressure Power Supply 90 PQ-945 2585 CP-945. 3, Containment Pressure Transmitter 90 PT-945 2584 CP-945.2, Reinstate of A-1 Containment Pressure 90 Channel 945 2635 CP-2093.1, General Defeat Procedure 2093 90 Atmospheric Relief Valve 1B (CV-57) Control

-107-PCN N 78 Procedure & Title Meetin N 78 2631 CP-2092.1, General Defeat Procedure 2092 90

. Atriaspheric Relief Valve,lA (CV-56) Control 2623 CP-950.1, Defeat of B-3 Containment Pressure 90 Channel 950 2615 CP-949.1, Defeat of B-1 Containment Pressure 90 Channel 949 2607 CP-948.1, Defeat of B-2 Containment Pressure 90 Channel 948 2599 CP-947.1, Defeat of A-3 Containment Pressure 90 Channel 947 2591 CP-946.1, Defeat of A-2 Containment Pressure 90 Channel 946 2583 CP-945.1, Defeat of A-1 Containment Pressure 90 Channel 945 2582 CP-945. 0, Calibration and/or Maintenance of 90 Containment Pressure Channel 945 2581 CP-941.4, Accumulator Pressure Local Indicator 90 PI-941 2580 CP-941.3, Accumulator Pressure Bistable 90 PC-94~

'579 CP-941.2, Accumulator Pressure Power Supply 90 PQ-941 2578 CP-941. 1, Accumulator Pressure Transmitter 90 2576 PT-941 CP-940. 4, Accumulator Pressure Indicator PI-940

~ 90 2575 CP-940.3, Accumulator Pressure Bistable 90 PC-940~

2574 CP-940.2, Accumulator Pressure Power Supply 90 PQ-940 2573 CP-940.1, Accumulator Pressure Transmitter 90 PT-940

1

-108-PCN N 78 Procedure a Title Meetin N 78 2571 CP-939. 3, Accumulator Level Indicator 90 LI-939 2570 CP-939. 2, Accumulaotr Level Bistable 90 LC-939A/8 2569 CP-939.1, Accumulator Level Transmitter 90 LT-939 2567 CP-938. 3, Accumulator Level Indicator 90 LI-938 2566 CP-938. 2, Accumulator Level Bistable 90 LC-938A/B 2565 CP-938. 1, Accumulator Level Transmitter 90 LT-938 2563 CP-937. 4, Accumulator Pressure Indicator 90 PI-937 2562 CP-937.3, Accumulator Pressure Bistable 90 PC-937~

2561 CP-937. 2, Accumulator Pressure Power Supply 90 PQ-937 2560 CP-937.1, Accumulator Pressure Transmitter 90 PT-937 2558 CP-936.4, Zoop A Accumulator Pressure Local 90 Indicator 2557 CP-936. 3, Accumulator Pressure Channel 90 Bistable PC-936Ajh 2556 CP-936.2, Accumulator Pressure Power Supply 90 PQ-936 2555 CP-936.1, Accumulator Pressure Transmitter 90 PT-936 2553 CP-935.3, Accumulator Level Indicator LI35 90 2552 CP-935. 2, Accumulator Level Bistable 90 LC-935~

2551 CP-935. 1, Accumulator Level Transmitter 90 LT-935

-109-PCN I 78 Procedure a Title Meetin I 78 2630 CP-2092.0, Calibration and/or Maintenance of 90 2092 Atmospheric Belief Valve 1A (CV-56) Control 2634 CP-2093.0, Calibration and/or Maintenance of 90 2093 Atmospheric Relief Valve 1B (CV-57) Control 2622 CP-950.0, Calibration and/or Maintenance of 90 Containment Pressure Channel 950 2614 CP-949.0, Calibration and/or Maintenance of 90 Containment Pressure Channel 949 2590 CP-946.0, Calibration and/or Maintenance of 90 Containment Pressure Channel 946 2598 CP-947.0, Calibration and/or Maintenance of- 90 Containment Pressure Channel 947 2606 CP-948.0, Calibration and/or Maintenance of 90 Containment Pressure Chanenl 948 2550 CP-93S.0, Calibration and/or Maintenance of 90 Accumulator Level Channel 935 2554 CP-936.0, Calibration and/or Maintenance of 90 Accumulator Pressure Channel 936 2559 CP-937.0, Calibration and/or Maintenance of 90 Accumulator Pressure Channel 937 2564 CP-938.0, Calibration and/or Maintenance of 90 Accumulator Level Channel 938 2568 CP-939.0, Calibration and/or Maintenance of 90 Accumulator Level Channel 939 2572 CP-940.0, Calibration and/or Maintenance of 90 Accumulator Pressure Channel 940 2577 CP-941.0, Calibration and/or Maintenance of 90 Accumulator Pressure Channel 941 2546 CP-920. 0, Calibration and/or Maintenance 920 90 Refueling Water Storage Tank Level 2639 SC-1.12B, Station Call List 90 2646 S-12.4, BCS Leakage Surveillance Record 90 Instructions

-110-PCN 4 78 Procedure a Title Meetin 4 78 2545 S-26.1, Gomputer Program Check 90 2548 M-38.9, 1B1 Battery Charger Maintenance or 90 Repair 2641 PT-5. 40, Process Instrumentation Reactor 90 Protection Channel Trip Test (Channel 4) 2644 RD-2, Containment Purge Release 90 2645 HP-10.1, Quality Control of Counting Systems 90 2643 HP-10.6, Calibration of the Liquid 90 Scintillation Counter 2649 HP-7.4, Calibration of Neutron Survey 90 Instruments 2549 HP-1.2, External Exposure Limits 90 2647 A-19, Changes in Written Procedures 90 2640 M-51.3, Non-Controlling Relay Replacement 90 for K',39X 2654 T-14A, Feedwater Heaters Valve Alignment 90 2655 T-5A, Condensate System Lineup, Charging 90 and Venting 2530 T-6.9, Condensate Polishing Mixed Bed 90 Demineralizer Units: Bed Startup Operation and Bed Removal frcm Service Operation 2507 CP-209.5, Calibration and/or Maintenance of 90 RMS Ratemeter for Channels R-8, R, and R-23 through R-28 2511 CP-222.0, Calibration and/or Maintenance of 90 RMS Channel 2508 CP-222.1, Calibration of Ratemeter Drawer 90 R-22 2510 CP-222.2, Calibration of R-22 Detector 90 2509 CP-222.3, Replacement of Detector for R4S 90 Channel R-22 2638 SM 78-1657.1, Installation of 42" Duct for 90 Control Room Ventilation

f PCN 5 78 Procedure a Title Meetin N 78 2671 M-ll.4.10, Charging Pump Gear Reducer 91 Inspection 2704 PZ-2. 5, Air Operated Valves, Quarterly 93 Surveillance All of the above items were reviewed by the Committee with respect to the Technical Specifications and the Committee has determined that no Technical Specification changes or violations were involved in the changes and there are no unresolved safety questions.

-112-S stem Modification SM 77-1449 System Modification SM 77-1449, Diesel Fire Pump Heater. This rxx3ification involved installation of a water heater on the Diesel driven Fire Pump.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 75-9.24 System Modification SM 75-9.24, EST Jet Shielding Installation Rework. This procedure included the steps necessary to rework the jet shields near the Refueling Water Storage Tank for GSM-14.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1474 System Modification SM 77-1474, RC Pump Seal Bypass. This mxlification included the relocation of the RC Pump Seal Bypass lines as recommended ky Westinghouse.

A Safety Evaluation was performed .and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical-Specifications is not necessary.

S stem Modification SM 75-47.30 System Modification 75-47.30, Rework of CVCS Hangers Inside Containment. This procedure involved the reworking of the CVCS Hangers for GSM-3.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is mt recessary.

S stem Modification SM 75-5.40 System Modification SM 75-5.40, Standby Auxiliary Feedwater System. Rework Inside Containment. This procedure involved reworking of the pipe supports on the 3" Standby Auxiliary Feedwater Piping, in mnjunction with: procedure SM-75-5.24.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not racessazy.

-113-S stem Modification SM 77-1498.1 System Modification SM 77-1498.1, Low Power S/G Peedwater Bypass Control Modification. This procedure included modifying the feedwater bypass valve control circuitry for low power steam generator level control.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 78-1485 System Modification SM 78-1485, Dillon Load Cell Stand. This rmdification involved installation of the Dillon Load Cell Stand.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not rmcessary.

S stem Modification SM 78-1845 System i%ddification SM 78-1845, Guide Stud Storage Rack. This edification involved installation of a new Guide Stud Storage Rack in the reactor cavity.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant ~rating Technical Specifications is not recessary.

S stem Modification SM 78-1865 System Modification 78-'1865, "A" Steam Generator Air &ver Restraint. This modification involved installation of an "A" Steam Generator Air Mover Restraint.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant ~rating Technical Specifications is not necessary.

S stem Modification SM 78-1480 System Modification SM 78-1480, "A" Reactor Coolant Pump Handrails. This modification involved the installation of the "A" Reactor Coolnat Pump Handrails A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

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-114-S stem Modification SM 78-1464 System Nodification SN 78-1464, Volume Control Tank and Accumulator Level.

This nodification involved installation of h ~roved Volte Control Tank and Accumulator Level control instruments.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not incre'ased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 78-2160 System Modification SM 78-2160, GSM 7 Pipe Supports. This rxxlification involved the installation of the GSM 7 Pipe Supports on the Auxiliary Feedwater Piping.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1877 System Modification SM 77-1877, RCP Anti-Rotation Pins. This mxiification involved the installation of the RCP Anti-Rotation Pins.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-13.2 System Modification 77-13.2, Inspection of Containment Antenna Coaxial Cable.

This procedure involved inspection of the Containment antenna maxial cable which has already been installed.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 78-1873 System Modification SN 78-1873, Pressurizer Jib Crane Extension. This modification involved installation of the Pressurizer Jib Crane Extension.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Cperating Technical Specifications is not necessary.

-115-S stem Modification SM 77-10.3 System Modification SM 77-10.3, Containment Personnel Hatch Hinge Assembly Modification Inner Hatch Door. This procedure required adding bearing supports to the upper main hinge shaft of the Inner Personnel and Equipment Hatch dcors of the Containment Vessel.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessaxy.

S stem Modification SM 76-21.5 System Modification SM 76-21.5, Battexy Room Air Conditioning Service Water Piping Installation. This procedure involved installation of the service water piping and associated hangers for the battexy room air conditioner.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessaxy.

S stem Modification SM 76-21.4 System Modification 76-21.4, Battery Rxm Air Conditioning Air Conditioner Discharge Duct South End of Battery Room. This procedure involved installation of the hangers, ductwork and danpers required for the discharge of the air conditioning unit.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant ~rating Technical Specifications is not necessaxy.

S stem Modification SM 76-21.6 System Modification SM 76-21.6, Battexy Room Air Conditioning Air Supply Duct to the'Air Conditioner. This procedure involved installation of the hangers, ductwork and dampers required for the air supply to the air conditioner. This installation was for the ductwork in the air handling room up to and including the fire damper in the wall between this room and the turbine building.

A Safety Evaluation was performed and it was determined that the possibility of an accident is .not increased. A change in the Plant Cperating Technical Specifications is not necessary.

S stem Modification. SM 77-1623.1 System Modification SM 77-1623.1, Charging Pump Monorail Installation. This procedure involved installation of the mnorails above the three charging pumps to facilitate removal and installation of the pumps.

A Safety Evaluation was performed and it was determined that the possibility of an, accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

-116-S stem Modification SM 77-1832A.l I

System Modification SM 77-1832A.1, Circuit Separation Fuse Installation. This procedure involved installation of fuses to protect electrical circuits frcm adjacent fires.

A Safety Evaluation was performed and it was determined that the possibility of an accident is mt increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1057.1 System Modification SM 77-1057.1, Relocation of the Charging Pump Filter Vent.

This procedure involved the relocation of the charging pump filter vent from the inlet side of the 3" hypos valve to the discharge side.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Mcdification SM 78-1048 System Modification 78-1048, Accumulator Relief, WR 1048. This rmdification involved installation of a new hanger on relief lines from the accumulators.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Cperating Technical Specifications is not necessary.

S stem Modification SM 77-1660.23 System Modification SM 77-1660.23, RCS Overpressure Protection Loop 452 Hack R2 Instrumentation Installation and Wiring. This procedure included the installation and wiring of the 452 loop power supply, alarm, test points, lights and test switches in the R2 protection rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1660.24 System Modification SM 77-1660.24, RCS Overpressure Protection Loop 455 Hack W2 Instrumentation Installation and Wiring. 'Ihis procedure included the installation and wiring of the 455 loop power supply, alarm, test point, test switch and light in the W2 protection rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

-117-S stem Modification SM 77-1660.25 System Modification SM 77-1660.25, KS Overpressure Protection Loop 456 Rack R2 Instrumentation Installation and Wiring. This procedure included the installation and wiring of the 456 loop power supply, alarm, test point, test switch and light in the R2 protection rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 77-1660.26 System Modification SM 77-1660.26, BCS Overpressure Protection Loop 409 Rack RCS 2 Instrumentation Installation and Wiring. This procedure included the installation and wiring of the 409 loop alarm bistable in the RCS 2 rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1660.27 System Modification 77-1660.27, RCS Ovexpressure Protection Loop 410 Rack KS 2 Instrumentation Installation and Wiring. This procedure included the installation and wiring of the 410 loop alarm bistable in the KS 2 rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1660.28 System Modification SM 77-1660.28, KS Overpressure Protection Modification of the Relay Racks. This procedure included the installation and wiring of the realy racks to be used for the overpressure protection rrodification.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is mt necessary.

S stem Modification SM 77-1660.29 System Modification R4 77-1660.29, BCS Overpressure Protection bkx3ification Annunciator Termination. This procedure included the installation and wiring of the annunciators which will be used for the overpressure protection modif ication.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant ~rating Technical Specifications is mt necessary.

-118-S stem Modification SM 77-1660.21 System Modification SM 77-1660.21, RCS Overpressure Protection Loop 450 Rack B2 Instrumentation Installation and Wiring. This procedure included the installation and wiring of the 450 lcop power supply, alarm, test point, test switch and light in the B2 protection rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1660.22 System bkxlification SM 77-1660.22, KS Overpressure Protection Loop 451 Rack W2 Instrumentation Installation and Wiring. This procedure included the installation and wiring of the 451 loop power supply, alarm, test points, lights and test switches in the W2 proctection rack.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 76-26.4 System Modification 76-26.4, Installation of 7.5 KVA Floor Wunted Constant Voltage Transformer 1B. This procedure involved replacing the existing constant voltage transformer with new solid state controls unit using existing installed wiring.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Techriical Specifications is not necessary.

S stem Modification SM 76-21.7 System Modification SM 76-21.7, Battery Room Air Conditioning Miscellaneous.

This procedure involved pouring the concrete pad, installing dampers and making necessary wiring connections.

A of Safety Evaluation was performed and an accident is not increased.

it was determined that the possibility A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 76-26.2 System Modification SM 76.26.2, Installation of 1B Inverter and Alternate Power Supplies. This procedure involved replacing the existing inverter and manual transfer alternate power supply with a new solid state inverter/static switch, automatic transfer to C.V.T. alternate power supply (and maintenance supply to instrument Bus 1B, if applicable).

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant ~rating Technical Specifications is mt necessary.

-119-S stem Modification SM 76-26.3 System Modification SM 76-26.3, Installation of 7.5 KVS Flow Mounted Constant, Voltage Transformer 1A. This procedure involved replacing the existing constant voltage transformer with new solid state controls unit using existing installed wiring.

A Safety Evaluation was performed and it was determined that the possibility of an'accident is not increased. A change:in the Plant Operating Technical Specif ications is not. necessary.

S stem Modification SM 76-26.1 System Modification SN 76-26.1, Installation of 1A Inverter and Alternate Power Supplies. This procedure involved replacing the existing inverter and manual transformer alternate power supply with a new solid state inverter/static switch, automatic transfer to C.V.T. alternate power supply (and maintenance supply to Instrument Bus lA, if applicable).

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1682.1 System Modification 77-1682.1, Penetration Testing Rxlification Penetration 304. This procedure involved the installation of hanger PA 401 and necessary piping modifications on Penetration 304.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification-SM 76-27.1 System Modification SM 76-27.1, Penetration 332 Modification. 'his procedure involved installing hanger PA 401 and necessary piping mx3ifications on Penetration 332.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Cperating Technical Specifications is not necessary.

S stem Modification SM 76-11.10 f.

System Modification SM 76.11.10, No. 12B Auxiliary Transformer Deluge System Tie-In. This procedure involved installing the tie-in to the "B" Deluge Header for the No. 12 Auxiliary Transformer deluge system. 'Ibis tie-in includes the elbow, the "6" pipe, the blind flanged 6" x 4" x 6" tee and the 4" gate valve.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

-120-S stem Modification SM 77-1682.4 System edification R4 77-1682.4, Penetration Testing Modification Penetration 107. This procedure involved installing hangers PA 407 and PS 408, and necessary piping nadifications on Penetration 107.

A Safety Evaluation was performed and it was determined that the possibility of an accident is mt increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1682.2 System Modification SM 77-1682.2, Penetration Testing Modification Penetration 202. This procedure involved installing hangers PA 409 and PA 410 and necessary piping rmdifications on Penetration 202.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1682.3 System edification 77-1682.3, Penetration Testing Modification Penetration 210. This procedure involved the installation of hangers PA 402,PG 403 and PA 404 and necessary piping modifications on Penetration 210.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1660.2 System Modification SM 77-1660.2, Overpressurization Mechanical Package. This procedure involved installing piping, valve piping hangers and accumulator vessels for the RCS overpressurization modification.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased., A change in the Plant Operating Technical Specif ications is not accessary.

S stem Modification SM 76-01.1 System Modification SM 76-01.1, Safeguard Buses DC Gontrol Voltage Ronitor.

This procedure involved installation of necessary relays and terminations for the safeguard buses DC Control Voltage 8onitor.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

-121-S stem Modification SM 77-1660.10 System Modification SM 77-1660.10, RCS Overpressurization Protection Electrical Conduit and Wiring. This procedure involved installation and fabrication of mnduit, conduit supports and wire/cable .excluding terminations for RCS Overpressurization Protection. System.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is mt necessary.

S stem Modification SM 77-2.10 System Modification SM 77-2.10, D.I. Water Containment Isolation Electrical Conduit and Wiring. This procedured involved fabrication and installation of conduit, 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 possibility of an accident is mt increased. A change in the Plant Operating Technical Specifications is mt necessary.

S stem Modification SM 78-2273.1 System Modification 78-2273.1, Armor Plate on the East Wall of the Control Room. This procedure involved the installing anger plate and necessary structural steel on the east wall of the Control Rocm.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not rmcessary.

S stem Modification SM 77-02.1 System Modification SM 77-02.1, D.I. Water to Contaiment i%ddification Mechanical. This procedure involved installing valves, piping and piping hangers on the demineralized water line going to Containment.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Mcdification SM 78-1048.1 System Modification SM 78-1048.1, Accumulator Relief Modification. This procedure involved installation of a new hanger on the 1" relief line from both accumulators and cut off the relief valve discharge lines before the elbow.

A Safety Evaluation was performed and it was determined that the possibility of an accident is mt increased. A change in the Plant Cperating Technical Specifications is not recessary.

-122-S stem Modification SM 78-2273 System Modification SM 78-2273, Armor Plate East Wall of Control Room.

This reification involved installation of armor plate on the East Wall of the Control Room.

A Safety Evaluation was per'formed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 78-1875.1 System Modification SM 78-1875.1, "A" Feedwater Venturi Monorail. This procedure involved fabrication and erection of a nnnorail above the "A" Feedwater Venturi.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications 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 steel by the "A" Reactor Coolant Pump.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 78-1890.1 System Modification SM 78-1890.1, Feedwater Line Drain Valves Before the Containment Check Valves. This rxxlification involved the installation of a drain line and valve on each feedwater line before vlaves 3992 and 3993.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Cperating Technical Specifications is not necessary.

S stem Modification SM 77-1474.1 procedure involved relocating the 41 Seal on the Reactor Coolant Pumps.

~s System Modification SM 77-1474.1, RCP Seal Bypass Modification. This piping and necessary hangers A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

-123-S stem Modification SM 75-14 System Modification SM 75-14, Boric Acid Batch Tank Recirculation Piping and Supports. '1%is modification involved installing the necessary piping, valves and hangers to allow the transfer of boric acid from either storage tank to the batch tank.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 78-1485.1 System Modification SM 78-1485.1, Dillon Cell Storage Frame. 'Ibis procedure involved the fabrication and installation of platform aadifications for the Dillon Cell Storage frame.

A Safety Evaluation was performed and it was determined 'that the possibility of an accident is=not increased. A change in the Plant Cgerating Technical Specifications is not necessary.

S stem Modification SM 78-1845.1 System Modification 78-1845.1, Guide Stud Storage Racks. This procedure involved the fabrication and installation of the Guide Stud Storage Racks on the wall of the Refueling Cavity.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 78-2160.1 System Modification SM 78-2160.1, GSM-7 Pipe Supports. This rxdification involved the fabrication and installation of the GSM-7 Pipe Supports on the Auxiliary Feedwater Piping.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 76-28.2 System Modification SM 76-28.2, Flange Installation on Feedwater Flow Venturis "A" Feedwater,Line. This procedure involved installation of flanges upstream and downstream of the main feedwater flow venturis on the "A" Feedwater line.

A of Safety Evaluation was performed and an accident is not increased.

it was determined that the possibility A change in the Plant Operating Technical Specifications is not necessary.

-124-S stem Modification SM 75-5.50 System Modification SM 75-5.50, Auxiliary Feedwater Hanger AEN-51 Repair.

This procedure involved repairing Hanger AEW-51, including rermval of some existing structural rremkers and replacement with new materials.

A of Safety Evaluation was performed and an accident is not increased.

it was determined that the possibility A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 76-01.2 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 Fuses excluding terminations.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 77-1660.15 System edification 77-1660.15, Instrumentation Tie-Ins for RCS Overpressurization. This procedure involved miscellaneous instrumentation installation on the new RCS overpressurization N2 piping to describe the steps necessary to make the tie-.in to the instrument air in mntainment and to describe the steps necessary to make the tie-ins for the new loop pressure transmitters onto the exis'ting flow transmitter takeoffs.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

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 holding frame.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Cperating Technical Specifications is not necessary.

S stem Modification SM 78-1873.1 System Modification SM 78-1873.1, Pressurizer Jib Crane. This procedure involved fabrication and installation of the Pressurizer Jib Crane Extension.

A of Safety Evaluation was performed and an accident is not increased.

it was determined that the possibility A change in the Plant Operating Technical Specifications is not necessary.

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-125-S stem Modification SM 77-1660.11 System Modification SM 77-1660.11, RCS Overpressurization Protection Electrical Terminations in the Control Room and in the Field. This procedure involved instructions necessary to make, cable terminations on new eguipnent installed in the field and on new equip"ent installed in the Control Room.

This does not include terminations in the racks.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-02.2 System Modification SM 77-02.2, Hydrostatic Testing and Initial Service Leak Test of the Demineralized Water to Gontainment Modification. Wis prooedure involved testing the new piping installed using SM 77-02.1.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SN 77-1682.10 System Modification 77-1682.10, Hydrostatic Testing of Penetration 143 Piping Modification.. This procedure involved testing the piping mxiifications installed using SM 77-1682.5.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-02.12 System Nodification SM 77-02.12, Cemineraalized Water Containment Isolation.

This procedure involved rmunting relay C14X, install rack wiring in SIA2 and SIB2 racks, and terminate field wires at SIA2 and SIB2 racks.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1660.100 System Nodification SN 77-1660.100, Pneumatic Testing of the KS Overpressure Protection System. This procedure involved performing pneumatic tests on the RCS oyerpressure protection system.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

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-126-S stem Modification SM 77-02.20 System Modification SM 77-02.20, Checkout Testing of the Containment DI Water Automatic Isolation Valve 8418. This procedure involved verifying proper operation and installation of valve 8418.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Cgerating Technical Specifications is not necessary.

S stem Modification SM 77-02.15 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.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-02.11 System Modification 77-02.11, Electric Termination of Valve 8414 and in the Control Room for DI Water to Containment. This procedure involved making the electrical terminations at the Containment DI Automatic Isolation Valve 8418 and to describe the steps necessary to install necessary switch and lights in the control board and make necessary terminations. This does not include terminations covered kp B4 77-02.12.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is rmt necessary.

S stem Modification SM 78-1888.1 System Modification SM 78-1888.1, Spray Additive Tank Recirc. Line Shutoff Valve Installation. This procedure involved installation of a shutoff valve and nipple on an existing plug connection for the spray additive tank recirc.

line.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 76-26.5 System Modification SM 76-26.5, Installation of 7.5 KVA Floor Munted Constant Voltage Transformer Backup Supply for Instrument Buses A-B-C a D. This procedure involved replacing the existing transformer with new solid state controls unit using the existing installed wiring.

A of Safety Evaluation was performed and an accident is not increased.

it was determined that the possibility A change in the Plant Operating Technical Specifications is not necessary.

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-127-S stem Modification SM 75-50.30 System Modification SM 75-50.30, Rework of Jet Shielding for Main Steam Bypass Piping and Valves. This procedure involved rework of the jet shielding for the main steam ~s piping and valves.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1030.1 System Modification SM 77-1020.1, Neutralizing Tank Modification. This procedure involved allowing recirculation mde of the neutralizing tank pump and to prevent discharge from the neutralizing tank when there is a pH alarm from the retention tank.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1449.1 System Modification 77-1449.1, Diesel Fire Pump Heater. This procedure involved installing an engine coolant heater and an engine coolant filter to the Diesel Fire Pump.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating, Technical Specifications is not necessary.

S stem Modification SM 78-1458.1 System Modification SM 78-1458.1, Spent Fuel Pit Roughing Filter Frame.

This procedure involved the installation of spent fuel pit roughing filter frames.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1405.1 System Modification SM 77-1405.1, Installation of Conduit for Security System.

This procedure involved installation of conduit for the Security System and provided a procedure to control Q.A. aspects of the rredification.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

-128-S stem Modification SM 76-17.3 System Modification SM 76-17.3, Screenhouse Intake Heater Cable Tray Rework.

This procedure involved installation rework of Hilti Fastenings to Nuclear Safety-Related structural steel by a power actuated fastening tool per NCR~78-57 A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not. necessary.

S stem Modification SM 76-18.1 System Modification SM 76-18.1, Waste Condensate Pumps, Monitor Tank Pump and Laundry Pump Rotor Controller Nx3ification. This procedure involved modifications to ensure that a liquid release is terminated if R-18 Monitor detects high activity.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-2110.1 System Nxlification 77-2110.1, Chem Lab D.I. Storage Tank Cable Routing. This procedure involved providing tank level indication at the D.I. Plant Control Panel.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant ~rating Technical Specifications is not necessary.

S stem Modification SM 75-50.31 System Modification SM 75-50.31, Jet Shielding Rework, Main Steam and Feedwater. This procedure involved documenting the work required to correct open items from NCR~77-139. These were incomplete items from SM 75-50.21 for GSM-8.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 77-1836.3 System Modification RI 77-1836.3, Relocation of Hangers SWXH 38 and 39. This procedure involved relocating Service Water Hangers BFJH 38 and 39.

A of Safety Evaluation was performed and it was determined that the possibility an accident is- not increased. A change in the Plant Operating Technical Specif ications is not necessary.

-129-S stem Modification SM 76-11.21 System Modification SM 76-11.21, 12B Transformer Grinnel Valve Alteration.

This procedure involved altering the position of Grinnel Multi-matic Valve Model A-4 for. the 12B Auxiliary Transformer Deluge System so that locking water is on the inlet side of the O.S. a Y. Valve.

A of Safety Evaluation was performed and an accident is not increased.

it was determined that the possibility A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 75-5.43 System Modification SM 75-5.43, Final Rework for Standby Auxiliary Feedwater.

This procedure involved resolving all known remaining deficiencies associated with the installation of GSM-16, Standby Auxiliary Feedwater System. Also, this describes the rework necessary to completely resolve NCR~77-131.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SM 75-14.1 System Modification 75-14.1, Batch Tank Recirculation Heat Trace Installation.

This procedure involved installation of a permanent heat trace on the Boric Acid Batch Tank Recirculation Piping.

A Safety Evalu'ation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.

S stem Modification SN 74-28.1 System Modification SN 74-28.1, Installation of Makeup Lines to Condensate Storage Tanks. This procedure involved installation and return to service of the new makeup line for the Condensate Storage Tank.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

S stem Modification SM 78-1657.1

,System i~ification .SN 78-1657.1, Installation of 42" Duct for Control Room Ventilation. This procedure involved fabrication of hangers and installation of the 42" duct for Control Rocm Ventilation.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

-130-S stem Modification SM 77-1663.1 System Modification SN 77-1663.1, Spent Fuel Pit Wall Temperature hhnitor.

This procedure involved installation of a temperature nanitor for the Spent Fuel Pit/Refueling Canal Wall.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specif ications is not necessary.