Text

Annual Operating Rept 1978
	ML17244A797
Person / Time
Site:	Ginna
Issue date:	12/31/1978
From:	; ROCHESTER GAS & ELECTRIC CORP.
To:	;
Shared Package
ML17244A798	List: ML17244A797; ML17261A140;
References
	NUDOCS 7909050478
	Download: ML17244A797 (172)
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ANNUAL REPORT OF CHANGES K) STATION FACILITIES AND PRCCEIXJRES R.

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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 02 05 04 03 06 22 27 31 17 QC-1502, Nonconformance Reports QC-1701, Quality Assurance Records QC-401, Control of Procurement Documents for Purchased Material, Parts, Components and Services ET-19, Test of Accoustical Leak Monitoring System for Ginna Safety Injection Piping PZ-2.3, Safeguard Valve Operation A-30. 2, Plant Procedure Classification Review, Approval and Distribution Requirements M-55.5, Full Length Rod Control System Drive Mechanism Operating Coils Polarity Check M-51.4 Performance Check of Latch Mechanism for Relay LC-171CX EM-197, Repair of Weld on "B" Charging Pump Discharge Line to Relief Valve 284 A-52.4, Control of Limiting Conditions for Operating Equipment M-ll.4.4, Charging Pump Varidrive Belt Reneval and Installation 02 02 02 03 03 03 04 04 05 06 07 07 21 32

,23 29 14 18

~ EM-19 Inspection and Maintenance on 14" Pratt Butterfly Valve Operator Only Valve 4562 (Containment Recirculation System Cooling Water Return Line)

M-18.2, Waste Evaporator Feed Tank Float Valve Maintenance E-l.l, Safety Injection System Actuation A-50.11.3, Fire Watch/Escort Training A-50.11.4, General Employee Fire Training A-50.3, Preventive Maintenance Program 0-6-7-1, Plant Alarm Panels Test 0-6.4, Core Quadrant Power Tilt Calculation 07 07 07 07 07 07 07 07

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

PCN 0 78 Procedure

& Title Meetin 578 30 47 48 46 79 None None None RSSP-12, Testing of Primary and Secondary Relief Valves on Test Stand RD-9, Preparing Waste for Shipment or Storage RD-10, Shipping Radioactive Material 0-5.2, Load Increases 0-1.1C,'re-Critical Technical Specif ication Check Sheet SM 78 1458 g Auxiliary Building Holding Frame Filter SM 78-1845, Guide Stud Storage Rack SM 78-1865, "A" Steam Generator Air Mover Restraint 08 08 08 08 09 10 10 10 None None None 81 62

& 65 63 64 51 42 45 77 SM 78-1480, Auxiliary Reactor Coolant Pump Handrails SM 78-1464, Volume Control Tank Level (Accumulator Level)

SM 78-2160, GSM 7 Pipe Supports S-25.4, Processing Water from Either S/G S-4.5, Sluicing Water Condensate Polishing

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

Issuance, Proper Use and Return of Respira-tors 10 10 10 10 10 10 10 10 10 10 10

PCN 5 78 Procedure 6 Title Meetin 5 78 60 52 A-52.4, Control of Limiting Conditions for Operating Equipment A-53.1, Equipment Inspection Period and Lubricant List 10 10 54 A-53.0, Preventive Maintenance Program 69 A-49, Station Security 10 10 53 55 74 75 82 84 A-53.2, three &anth Lubrication and Maintenance Inspection PT-2.8, Component Cooling Water Pump System PT-13.1.13, Deluge Valve System Testing System Numbers 1, 2, 11 ~

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

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

PCN I 78 Procedure a Title Meetin I 78 91 103'Z-2. 5, Air Operated Valves, Quarterly Surveillance SN 77-13.2, Inspection of Containment Antenna Coaxial Cable 12 88 109 108 85 123 87 100 Q=-603, Control of Drawings A-55.1, Field Change Requests to Engineering Documents (g-105, Indoctrination and Training of Modifica-tion Project Personnel QC-402, Control of Procurement Documents for Materials and Services Purchased by the Ginna Modification Project QC-606, Control of Engineering Documents QC-304, Control of Modification Activities by the Ginna Modification Project 9 -202, Modification Project Organization 0-1.1, Plant Heatup From Cold Shutdown to Hot Shutdown 12 12 12 12 12 12 12 101 102 PZ-7, Hydro Test of Reactor Coolant, System 0-2.2, Plant Shutdown From Hot Shutdown to Cold

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

PCN ¹ 78 Procedure 6 Title Meetin

¹ 78 107 24 121 95 83 110 90 S-2.4A, Draining the Pressurizer (RCS Degassed)

S-3.3A, Coolant Chemistry Addition Tank W-101, Ginna QA Program Implementation GS-l. 2, Security Event Report A-30.3, Plant Procedure Content and Format Requirements 0-6.11, Routine Operations Check Sheet E-1.2, Zass of Coolant Accident PT-2. 6, Cold/Refueling Shutdown Air Operated Valve Surveillance 12 12 12 12 12 12 12 89 PZ-2.5, Air Operated Valves, Quarterly Sur-veillance 12 105 98 99 49 PT-6. 2, NIS Intermediate Range Channels PT-23.14, CV Air Sample Inlet PT-23.20, BC'as Header M-29, Decontamination of R-18 Liquid Sampler 12 12 12 12

126, 129 0.2, Main Control Board System Status 141 Verification 12 114 120 119 S-27.2776, Isolation of Valve 2276 S-3.1M, Isolation of Batching System S-27.2, Isolation of CVCS Letdawn Demineralizers and Associated Valves S-27.164SA, Isolation of Waste Evaporator Return Valve 1654A 13 13 13 13 115 118 S-3.2J, Isolation of Reactor Coolant Filter and Associated Grinnell Diaphragm Valves (249, 250, 251, 248A 248B)

S-27.245, Isolation of Mixed Bed Demineralizer Bypass Valve 245 13 13

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

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

Ii 1

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

PCN 5 78 Procedure 6 Title Meetin 5 78 181 180 166 189 78 167 176 CP-31.3, Calibration of Source Range N-31 CP-32.3, Calibration of Source Range N-32 PC-l.l, Analysis Schedule and Limits Primary Coolant A-54.3, Open Flame, Welding and Grinding Permit SM 77-1057.1, Relaocation of the Charging Pump Filter Vent M-48.3, Isolation and Restoration of Bus e15 T-35F, Steam to Auxiliary Building, Screen House or Diesel Generators and Oil Room 14 14 14 15 15 15 184 T-31.8, Turbine Generator Bearing Drain Vapor Extractor 15 Vent-Hydrogen Loss Calculation 93 113 HP-12.2, Medical Check, Fitting and Training of Personnel Using Respirators M-11.4.6, Charging Pump Stuffing Box Maintenance 15 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 192 190 191 188 195 194 193 154

. M-37.16B, Isolation of Batching System Grinnel Diaphragm Valves M-37.16N, Repair of Demineralizer Drain Valve 1610B M-37.16P, Repair of Valve 2276 GS-5.0, Security Guard General Instructions GS-28, Inspection of Personnel, Vehicle and Packages

, GS-21.0, Site Access Control (Security) and Personnel Identification GS-41. 0, Employee Screening Program QC-304, Control of Modification Activities by the Ginna Modification Project 15 15 15 15 15 15 15 15 PCN I 78 Procedure

& Title Meetin 5 78 194 a

230 GS-21..0, Site Access Control (Security) and Personnel Identification 16 231 GS-5.0, Security Guard General Instructions 16 177 A-60.3, Calibration Survey Program for Instrumentation/

16 Equipment of Safety Related Components 186 205 206 204 RSSP-15.7, Inservice Inspection Hydro Test of Class B

Safety Related Piping

.M-37.16Q, Isolation of CVCS Letdmm Demineralizers and Associated Grinnell Diaphragm Valves M-37.16K, V-245 (Mixed Bed Demineralizer Bypass Valve)

Isolation Draining and Restoration to Service M-37.16G, Isolation of Waste Evaporator Return Valve 1654A 16 17 17 17 203 257 250 249 238 M-37.16F, Isolation of Reactor Coolant Filter and Associated Grinnell Diaphragm.Valves T-27.2, lB Emergency Deisel Generator Pre-Start Alignment SM 76-21.5, Battery Room Air Conditioning Service Water Piping Installation QCIP-15, Visual Inspection During Hydro-Static and System Pressure Testing GS-21.0, Site Access Control (Security) and Personnel Identification 17 17 17 17 17 220 228 223 221 235 210 211 PT-2.7, Service Water System GS-26.0, Security Key and Lock Controls HP-9.1, Steam Generator Blowdawn Activity RD-3, Plant Vent Iodine and Particulate Releas'e

-Sampling and Analysis A-l, Radiation Control Manual AR/C-3, Accumulator IA Level

~C-4, Accumulator 1B Level 17 17 17 17 17 17 17

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PCN O 78 Procedure

& Title Meetin 0 78 207 AR/E-27, NIS Power Range Single Channel Lo Range Alert 17 213 208 214 209 215 AR/D-20, Pressurizer Lo Pressure

~~15, Reactor Coolant Lo Flow Undervoltage Underfrequency Zaop A

~M23, Reactor Coolant Lo Flow Undervoltage Underfrequency Loop B AR/D-10, NIS Power Range Lo Range Reactor Trip

~~19, Pressurizer Lo Pressure and Level 17 17 17 17 17 200 201 M-73.3, Welding on Carbon Steel Piping or Components 17 M-73.2, Welding on Stainless Steel Piping or Components 17 243 242 237 QCIP-3, Receiving Inspection of New Fuel QCIP-2, Pre-closure Core Verification

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

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289 A-30.2, Plant Procedure Classification, Review Approval 19 and Distribution Requirements 264 GS-20.0, Classification oj Ginna Station Photo ID Cards and Non-Photo Bactges 19 PCN N 78 Procedure a Title Meetin N 78 251 240 A-17, Plant Operations Review Committee Operating 2rocedure 4

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

19 19 19 19 19 19 296 256 CPO. 2, Rotameter Calibration RF-8.4, Fuel and Core Component Mvement in the Spent Fuel Pit 19 19 305 RSSP-6.0, Containment Integrated Leakage Rate Test 19 283 PT-16, Auxiliary Feedwater System 20 343 344 A-30.2, Plant Procedure Classification, Review, Approval 20 and Distribution Requirements A-.30.3, Plant Procedure Content and Format Requirements 20 310 329 SC-3.15.6, Fire Hose Reel Inspection A-60.1, Ginna Station Technical Specif ication Surveillance Program 20 20 PCN I 78 Procedure a Title Meetin I 78 334 307 308 312 314 313 298 395 30Ci 306 182 322 218 336 337 143 245 335 237 S-3.4J, Transferring Monitor Tank to RMÃ Tank E-1.2, Loss of Coolant Accident A-25.1,, Ginna Station Event Report E-23.5, Reactor Coolant Pump No.

1 Seal Leak-off Lmr Flow or Off

('-8,-Loss of Reactor Coolant Flow E-23.1, Malfunction of Il Reactor Coolant Pump Seal CP-218.2, Calibration of R-18 Detector M-15, Diesel Generator Maintenance RF-9.8.1, Part Length Control Rod Drive Shaft Unlatching RF-l, Refueling Organization GS-26.1, Unoccupied Vital Area Key Control and Accountability A-l.l, Locked Radiation Areas A-5.1, Protective Clothing Locker Locat'P-215.2, Calibration of R-15 Detector RSSP-6.1, Integrated Leakage Rate Test Valving Align-ment RSSP-6.2, Presurization Monitoring of Penetration Free Volumes During CV ILRT QC-1402, System and Equipnent Operating Status Control QCIP-5, Cleanliness Inspection of Components S-3.3G, CVCS Deborating Demineralizer Bed Operation Using "B" Deborating Unit GS-31.1, Door Alarm Assessment and Response Controlled 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 346 347 ISI-1.8, Quality Control A Inservice Inspection ISI-2.6, Quality Control B Inservice Inspection 20 20

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' PCN N 78 Procedure 6 Title Meetin N 78 348 241 244 246 247 234 239 229 395 362 363 ISI-3. 5, High Energy Inservice Inspection QCIP-1, Quality Control Inspection Procedure Steam Generator (Primary Side) Preclosure Inspection QCIP-4, Quality Control Inspection Procedure Receiving Inspection of NG-6 Type Relays QCIP-9, Quality Control Inspection Procedure Pressurizer Preclosure Cleanliness Inspection QCIP-13, Quality Control Inspection Procedure Material Receiving Inspection of Chemicals and Radio-Chemical Laboratory Supplies RSSP-13.6, Inservice Inspection Hydro Test of Class "C"

Safety Related Piping (Auxiliary Feedwater Pumps Discharge Piping)

RSSP-15.8, Inservice Inspection Hydro Test of Class "B"

Safety Related Piping (Charging Pump Suction excluding VCT)

SM 76-16.1, Eddy Current Wiring Conduits Rl-200, Replacement or Rework of Solenoid Valves for CV Purge Exhaust Valve 5879 S-2.5A, Burping the Reactor Goolant Drain Tank (To Be Opened to Atmosphere)

. S-2.5B, Restoring Reactor Coolant Drain Tank to Service After Maintenance 20 20 20 20 20 20 20 20 21 21 21 364 S-4.2.10, Burping the Pressurizer Relief Tank and Reactor Goolant Drain Tank and Isolating from the Vent Header 21 361 353 SM 76-17.2, Screen House Intake Heater Cable Tray SM 76-21.5, Battery Room Air Conditioning Service Water Piping Installation 21 21

PCN 5 78 Procedure

& Title Meetin

" 78 383 384 385 386 387 388 389 381 382 399 412 SN 77-1660.23, RCS Overpressure Protection Loop 452 Rack R2 Instrumentation Installation and Wiring SN 77-1660.24, RCS Overpressure Protection Loop 455 Rack=W2 Instrumentation Installation and Wiring B4 77-1660.25, RCS Overpressure Protection Loop 456 Rack R2 Instrumentation Installation and Wiring

&1 77-1660.26, RCS Overpressure Protection Loop 409 Rack RCS2 Instrumentation Installation and Wiring SM 77-1660.27, RCS Overpressure Protection Loop 410 Rack RCS2 Instrumentation Installation.and Wiring SM 77-1660. 28, Overpressure Protection Rxlification of the Relay Racks SN 77-1660.29, Overpressure Protection Rx3ification Annunciator Termination SN 77 1660 21 g Overpressure Protection Loop 450 Rack B2 Instrumentation Installation and Wiring SM 77-1660.22, RCS Overpressure Protection Loop 451 Rack W2 Instrumentation Installation and Wiring

'lCIP-10, Test Instrument Calibration Procedure CP-625.1, Residual Heat Reaaval Heat Exchanger Outlet Valve HCV-625 Isolation 21 21 21 21 21 21 21 22 22 410 411 396 355 263 222 PR-6, Protective Relay Calibration and Trip Test 19KV and 115KV Relaying CP-624.1, Residual Heat Removal Heat Exchanger Outlet Valve HCV-624 Isolation RSSP-10.2, Main Steam Safety Valve Test S1 75-58.8, Modification of the Walkway and Railings

, Around the Spent Fuel Pool A-60.2, Control of Inservice Inspection Status PR-2, Protective Relay Calibration and Trip Test 1A Emergency Diesel PR-3, Protective Relay Calibration and Trip Test 1B Emergency Diesel 22 22 22 22 22 22 PCN N 78 Procedure a Title Meetin N 78 372 374 373 293 294 403 406 413 400 332 345 380 356 354 353 342 349 341 338 340 CP-2019.0, Turbine Driven Au-iliary Feeawater Pung Discharge Pressure Loop 2019 CP-2030.0, 1B Wtor Driven Auxiliary Feedwater Pump Discharge Pressure Loop 2030 CP-2029.0, 3A Motor Driven Auxiliary Feedwater Pump Discharge Pressure Loop 2029 M-15.3, Diesel Fuel Oil Transfer Pump Maintenance M-15.4, Diesel Startup Air Compressor Maintenance M-40.7, Steam Generator Snubber Maintenance A-53.2, three anth Lubrication and Maintenance Inspection A-35, Prime Mover Holding and Markup Requirements RF-8.1, Step ky Step Fuel Loading and Maps GS-12.0, Security Guard Actions During a Fire GS-31.0, Door Alarm System

'I GS-21.0, Site Access Control (Security) and Personnel Identification GS-28.0, Search of Personnel, Vehicles and Packages

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

RSSP-15.7, Inservice Inspection Hydro Test of Class "B"

Safety Related Piping (Charging Pumps Discharge Piping)

RSSP-12, Testing of Primary and Secondary Relief Valves on Test Stand Fire Pump Ceration and System Alignment SC-1.12A, Inmdiate Call List HP-4.1, Controlled Area Entry SC-1.12B, Station Call List CP-209, Calibration of Area 8onitors, TA-62 Detectors (Rl-R9) 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 PCN 5 78 Procedure

& Title Meetin 5 78 303 302 RF-2, Reactor Refueling Outage Operations and Activities RF-10, Fuel Transfer System Checkout and Demonstration Procedure 22 22 351 376 277 A-50.11.4, General Employee Fire Training SM 76-26.4, Installation of 7.5KV Floor Mounted Constant Voltage Transformer lB SN 76-21.7, Battery Room Air Conditioning Misc.

22 22 22 317 260 RSSP-13.8, Inservice Inspection Hydro Test of Safety Related Piping (Service Water Piping-RSSP-13.7, Inservice Inspection Hydro Test of Safety Related Piping (CVCS Holdup Tank Inlet Gas Stripper Pumps Discharge Piping Including Removal and Cation Ion Exchangers Piping)

Class IICI1 Loop A)

Class "C"

Piping, Base 22 22 248 252 290 377 375 378 321 325 318 320 319 QCIP-14, Quality Control Inspection Procedure Material Receiving Inspection of Mechanical Measuring Tools HP-12.1, Usage of Respirators A-54.6, Health Phsyics Tour SN 76-26.2, Installation of 1B Inverter and Alternate Power Supplies SN 76-26.3, Installation of 7.5KVS Floor Wunted Constant Voltage Transformer 1A SN 76-26.1, Installation of 1A Inverter and Alternate Power Supplies SM 77-1682.1, Penetration Testing Modification Penetration 304 SN 76-27.1, Penetration 332 Modification SN 77-1682.4, Penetration Testing Modification Penetration 107 SN 77-1682.2, Penetration Testing Reification Penetration 202 SM 77-1682.3, Penetration Testing Modification Penetration 210 22 22 22 22 22 22 22 22 22 22 22 PCN I 78 Procedure a Title Meetin I 78 394 291 425 426 409 SM 77-1660.2, Overpressurization Mechanical Package B4 76-01.1, Safeguard Buses DC Control Voltage bhnitor SN 77-1660. 10, RCS, Overpressurization Protection Electrical Conduit and Wiring RI 77-2.10, DI Water Containment Isolation Electrical Conduit and Wiring SM 78-2273.1, Armor Plate on the East Wall of the Control Room 22 22 22 22 22 408 398 Rl 77-1836.1, Turbine Building Pressurization and Security Wall B4 77-02.1, DI Water to Containment Modification Mechanical 22 22 359 327 438 447 RSSP-15.9, Inservice Inspection Hydro Test of Class "B"

Safety Realted Piping (Service Water Loop B)

SM 78-1048.1, Accumulator Relief Modification M-52.3, Incore Thimbles Cleaning A-17, Plant Operations Review Committee Operating Procedure 24 24 24 420 ISI-3.5, High Energy Inservice Inspection 24 434 6 446 SM 77-1057.1, Relocation of the Chargine Pump Filter Vent 24 421 a 431 BI 77-1660.28, Overpressure Protection Modification of the Relay Backs 24 433 440 441 417 414 443 M-73.3, Welding on Carbon Steel Piping or Components S-2.5A, Burping RCVZ (To Be Opened to Atmosphere)

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

TCIP-9, Test Instrument Calibration Procedure S-2.4A, Draining the Pressurizer (RCS Degassed) 24 24 24 24 24 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 24 432 405 407 404 397 402 459 458 463 462 464 350 M-65.0,. Main Steam Line Weld Repairs (Outside of Containrent)

SN 78-1875.1, "A" Feedwater Venturi Monorail SN 78-1480.1,

".A" RCP Ladder and Handrail Installation SM 77-1474.1, RCP Seal Bypass Modification SN 75-14, Boric Acid Batch Tank Recirculation Piping and Supports SN 78-1485.1, Dillon Cell Storage Frame SN 77-1660.2, Overpressurization Mechanical Package SN 77-02.1, Demineralized Water to Containment Modification Mechanical RD-6, Gas Decay Tank Releases M-ll.8B, Reactor Coolant Pump Seal Injection and Service Mechanical SN 77-1623.1, Charging Pump Mnorails SC-3.15.16, Fire Protection System Inspections and Tests 24 25 25 25 25 25 25 25 358 366 367 i

368 369 370 371 255 CP-70.5, Test Gauge Calibration Procedure

. CP-617.0, Component Cooling Water Pumps Discharge Pressure PIC-617 CP-628.0, RHR Loop Reactor Coolant Test Bypass Flow CP-2033.0, Service Water Flow From "3A" Vent Cooler Flowmeter FIA-2033 CP-2034.0, Service Water Flow From "lB" Vent Cooler Flowmeter FIA-2034 CP-2035.00 Service Water Flow From "lC" Vent Cooler Flowmeter FIA-2035 CP-2036.0, Service Water Flow Frcm "1D" Vent Cooler Flowmeter FIA-2036 HP-10.7, Flow Calibration of Low Volume Air Samplers 26 26 26 26 26 26 26 PCN 4 78 Procedure 6 Title Meetin 5 78 323 448 449 435 454 450 457 456 424 428 429 430 445 427 444 439 202 PR-7.2, Protective Relay Calibration and Trip Test 512B Transformer 34KV Relaying A-19, Change in Written Procedures RSSP-6.1, Integrated Leakage Rate Test Valving Alignment RSSP-6. 0, Containment Integrated Leakage Rate Test M-37.24A, Main Steam Safety Valve Maintenance Valve No.

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

SM 77-1660.28, Overpressure Protection Modification of the Relay Racks S-4.1U, Velocity Flush of R-18 A-35, Prime Hover Holding and Markup Requirements ISI-1.8, Quality Group A Inservice Inspection ISI-2.6, Quality Group B Inservice Inspection ISI-3.5, High Energy Inservice Inspection O-l. 1C, Pre-Critical Technical Specif ications Check Sheet HP-12.4, Fitting and Testing of Respirators A-52.4, Control of Limiting Conditions for Operating Equipment GS-41. 0, Employee Screening Program

, A-58, Installation of Power, Control or Instrunentation Cables at Ginna Station 26 26 26 26 26 26 26 26 26 26 26 26 26 442 360 451 469 505 A-54. 4, Empty Engineer Responsibilities M-43.15, Installation of Steam Generator Manway Insert SM 76-28.1, Flange Installation on Main Feedwater Flow Venturis Ginna Station Feedwater Line

&1 78-1845.1, Guide Stud Storage Racks SM 78-2160.1, GSM-7 Pipe Supports 26 26 27 27 PCN I 78 Procedure

& Title Meetin 5 78 470 510 460 455 513 512 508 465 517 474 473 511 476 516 466 518 509 452 SM 77-1682.5, Penetration Testing Modification Penetration 143 SM 76-28.2, Flange Installation on Feedwater Flow Venturis A Feedwater Line SM 75-5.50, Auxiliary Feedwater Hanger APW-51 Repair RF-51, Reactivity Insertion Computation ISI-2.1.6, Quality Group B Inservice Inspection ISI-1.1.8, Quality Group A Inservice Inspection SM 76-26.1, Installation of 1A Inverter and.Alternate Power Supplies 0-2.3.1, Draining the Reactor Coolant System S-3.2J, Isolation of Reactor Coolant Filter and Associated Grinnel Diaphragm Valves (249, 250, 253,

251, 248A, and 248B)

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

S-3.2J, Isolation of Reactor Coolant Filter and Associated Grinnell Diaphragm Valves (249, 250,

253, 251, 248A, and 248B)

M-43.1, Steam Generator Manway Cover Rermval Steam Generator EN-201, B Steam Generator Secondary Side Peripheral Tube Removal RSSP-15.9, Inservice Inspection Hydro Test of Class "B"

Safety Related Piping (Service Water Loop B)

SM 75-14, Boric Acid Batch Tank Recirculation Piping and Supports SM 77-2.10, DI Water Containment Isolation Electrical Conduit and Wiring RF-2E, Draining of Refueling Canal SM 77-1682.4, Penetration Testing Modification Penetration 107 E-1.2, Zoss of Coolant Accident GS-1.2, Ginna Station Security Event Report 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27

)g 4 t

'\\

?

PCN 5 78 Procedure

& Title Meetin 5 78 548 542 558 559 a 546 521 520 520 552 551 561 554 SM 76-26.2, Installation of 1B Inverter and Alternate Pawer Supplies A-54.3, Open Flame, Welding and Grinding Permit S-27.209, Isolation of CVCS Relief Valve 209 RSSP-13.8, Inservice Inspection Hydro Test of Class "C"

Safety Related Piping (Service Water Piping Loop A)

P RSSP-15.8, Inservice Inspection Hydro Test of Class "B"

'afety Related Piping (Charging Pump Suction Excluding VCT)

RF-10, Fuel Transfer System Checkout and Demonstration Procedures M-11.8.3, Reactor Coolant Pump Seal Inspection and Service Mechanical B4 77-1057.1, Relocation of the Charging Pump Filter Vent RSSP-14.8, ISI Hydro Test of Class "C" Safety Related Piping (Service Water Piping Loop A)

M-38.5; 1B Constant Voltage Transformer Maintenance RSSP-12, Tiesting of Primary and Secondary Relief Valves on Test Stand GS-21.0, Site Access Control (Security) and Personnel Identification 28 28 28 28 28 28 28 28 28 28 28 28 553 562 S-27.209, CVCS Relief Valve 209 Isolation S-27.1, Volume Control Tank Grinnell Diaphragm Valves Isolation 28 28 545 550 A-50.6, R.'. Ginna Operator Requalification Program M-ll.8A, Reactor Coolant Pump 5

Removal from Service for Pump Maintenance 28 28 471 S-2.1B, Reactor Coolant Pumps Isolation for Naintenance 28 522 515

, PZ-2.5, Air Operated Valves, Quarterly Surveillance A-36, Station Holding Rules 28 28

'k A

P)

/

PCN 4 78 Procedure 6 Title Meetin 5 78 543 519 316 507 472 330 540 538 541 539 532 533 CP-429.7, Pressurizer Pressure Bistable PC-429A M-15.5, lA Deisel Startup Air Compressor Maintenance QC-1403, Inspection and Test Status Control 0-2.3.1, Draining the Reactor Coolant System M-15.6, 1B Deisel Fuel Oil Transfer Pump Maintenance 0-6.4, Core Quadrant Power Tilt Calculation CP-410.0, Reactor Coolant Temperature Gold Leg "410B" Calibration and/or. Maintenance CP-409, Reactor Coolant Termperature Cold Leg "409B" Calibration and/or Maintenance CP-410.3, Reactor Coolant Temperature Cold Leg Bistable TC-410A/B CP09.3, Reactor Coolant Temperature Cold Leg Bistable TC-409A/B CP-455.0, N2 Accumulator Pressure Low Loop 455 CP-455.'1, N2 Accumulator Pressure Lear Zoop 455 Transmitter 28 28 28 28 28 28 28 28 28 28 28 28 534 535 536 CP-455.2, N2 Accumulator Pressure Low Loop 455

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

V I

PCN N 78 Procedure

& Title Meetin N 78 529 530 524 525 514 477 478 479 480 481 482 483 484 485 486 487 488 489 490 CP-452.0, Overpressure Protection Loop 452 CP-452.1, Overpressure Protection Loop 452 Transmitter CP-.450.1, Overpressure Protection Loop 450 Transmitter CP-450.2, Overpressure Protection Loop 450 Ewer Supply and Bistable CP-450.0, Overpressure Protection Loop 450 QCIP-20, Verification of Accuracy for Mechanical Measuring Tools ISI-1.1.9, Quality Group A Inservice Inspection ISX-1.2.1, Quality Group A Inservice Inspection ISI-1.2. 2, Quality Group A Inservice Inspection ISI-1.2.3, Quality Group A Inservice Inspection ISX-1.2.4, Quality Group A Inservice Inspection ISI-1.2.5, Quality Group A Inservice Inspection ISI-l.2.6, Quality Group A Inservice Inspection ISI-1.2.7, Qaulity Group A Inservice Inspection

~ ISI-1.2.8, Quality Group A Inservice Inspection ISI-1.2.9, Quality Group A Inservice Inspection ISI-1.3.1, Quality Group A Inservice Inspection ISI-1.3. 2, Quality Group A Inservice Inspection ISI-1.3.3, Quality Group A Inservice, Inspection ISI-1.3.4, Quality Group A Inservice Inspection 28 28 28.

28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 491 ISI-'1.3.5, Quality Group A Inservice Inspection 492

~

ISI-1.3.6, Quality Group A Inservice Xnspection 28 28 493 494 ISI-l.3.7, Quality Group A Inservice Inspection ISX-1.3. 8, Quality Group A Inservice Inspection 28 28 PCN 5 78 Procedure 6 Title Meetin 5 78 495 496 497 498 499 500 501 502 503 504 597 557 565 ISI-1.3.9, Quality Group A Inservice Inspection ISI-1.4.1, Quality Group A Inservice Inspection ISI-1.4.2, Quality Group A Inservice Inspection ISI-1.4.3, Quality Group A Inservice Inspection ISI-1.4.4, Quality Group A Inservice Inspection ISI-1.4.5, Quality Group A Inservice Inspection ISI-1.4.6, Quality Group A Inservice Inspection ISI-1.4.7, Quality Group A Inservice Inspection ISX-1.4.8, Quality Group A Inservice Inspection ISI-1.4.9, Quality Group A Inservice Inspection A-54.6, Health Physics Tour EM-202, Safety Injection Sequence Timing Relay Replacement SM 76-01.2, Cable Installation for the DC Control Fuses SN 77-1660.15, Instrumentation Tie-Ins for RCS Overpressurization 28 28 28 28 28 28 28 28 28 28 28 29 29 29 544 SN 78-1865.1, Steam Generator "A" Air Mver Installation 29 603 604 S-27.348B, Valve 348B Isolation EN-201, "B" Steam Generator Secondary Side Peripheral Tube Removal 30 30 608 S-3. 1K, 1A Boric Acid Transfer Pump Isolation/RestOration 30 574 SM 77-1682. 2, Penetration Testing lkx3ification-Penetration 202 30 579 598 566 SM 77-1682.3, Penetration Testing Modification

.Penetration 210 RF-51, Reactivity Insertion Computation PT-2.10.2, RHR System Core Deluge Check Valves 853A and 853B 30 30 30 PCN 5 78 Procedure

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

~ S-27.2, Isolation of CVCS Letdown Demineralizers and Associated Valves 31 642 617 621 613 582 581 605 M-37.46, Reactor Compartment Cooler Service Water Outlet Valve 4758 Maintenance and Inspection GS-10.1, Security Guard Action During a Local Radiation Emergency QC-1701, Quality Assurance Records RF-2D, Filling the Refueling Canal CP-950.3, Containment Pressure Transmitter PT-950 CP-949.3, Containment Pressure Transmitter PT-949 M-43. 24.1, Inspection of Steam Generator Secondary Side Upper Internals 31 31 31 31 31 31 31 PCN I 78 Procedure

& Title Meetin I 78 602 600 583 570 560 563 591 PZ-2.7, Service Water System S-27.887, Safety Injection Relief Valve 887 Isolation T-17J, Generator Bearing Drain Vapor Extractor Normal Lineup and Operation PZ-7, Hydro Test of Reactor Coolant System PT-22.10, Mechanlical Manifold "C" Leak Rate Test SC-1.12B, Station Call List PZ-23.45, Containment Isolation Va1ve Leak Rate Testing Leakage Test Instrumentation 31 31 31 31 31 31 31 593 PZ-23.51A, Containment Isolation Valve Leak Rate Testing 31 "A" Hydrogen Recombiner (Pilot and Hain) 594 595 589 587 622 624 620 590 592 596 567 PZ-23.S1B, Containment Isolation Valve Leak Rate Testing "B" Hydrogen Recombiner (Pilot and Main)

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

~23.23, Containment Isolation Valve Leak Rate Testing Sump "A" Discharge PT-23.22, Containment Isolation Valve Leak Rate Testing RCDZ Discharge l

A-20, Control Room Its A-25.1, Ginna Station Event Reports S-14.1, Radiation Honitoring and Related Systems Daily Plot Hequirements PT-23.29, Containment Isolation Valve Leak Rate Testing Demineralized Water PZ-23.46, Containment Isolation Valve Leak Rate Testing Nitrogen to Accumulators PZ-23A, Containment Isolation Valve Test Connection Boundary Control M-ll.27, Corrtponent Cooling Pump Inspection and Maintenance 31 31 31 31 31 31 31 31 31 31 31 PCN I 78 Procedure a Title Meetin I 78 637 636 658 SN 77-02.2, Hydrostatic Testing and Initial Service L'eat Test of the Deraineralized Water to Containment Modification SN 77-1682.10, Hydrostatic Testing of Penetration 143 Piping Modification SN 78-1048.1, Accumulator Relief Rx3ification for Accumulator Relief Line 32 32 32 657 SM 77-1682.4, Penetration Testing Modification Penetration 107 32 659 666 665 668

& 670 650 664 650 663 674 644 653 654 645 SN 77-1832.1, Flame Retardant Cable Coating in the East Cable Vault SN 75-47.50, Rework of CVCS Hangers Inside Containment SM 77-1660.15, Instrumentation Tie-ins for RCS Overpressurization SN 77-1660. 2, Overpressurization Mechanical Package EM-194, Repair of CVCS Hanger CH54 N-37.38.1, Crosby Safety and Relief Valve Maintenance N-48.5, Isolation of Bus 17 RSSP-15.7, Inservice Inspection Hydro Test of Class "B"

Safety Related Piping (Charging Pumps Discharge Piping)

SN 77-1057.1, Relocation of the Charging Pump Filter Vent QC-105, Indoctrination and Training Modification Program QC-301, Work Start Authorization QC-304, Control of Modification Activities by the Modification Project SN 77-1660.100, Pneumatic Testing of the Containment DI Water Automatic Isolation Valve 8418 S-27.861, Relief Valve 861 Isolation S-27.1817, Relief Valve 1817 Isolation SN 77-02.15, Air Tie-in for the DI Water to Containment 32 32 32 32 32 32 32 32 32 32 32 32 33 33 33 33 PCN I 78 Procedure

& Title Meeting I 78 673 679 678 677 676 683 682 686 685 687 699 634 684 612 700 RF-2, Reactor Refueling Outage Operations and Activities SM 76-27.1, Penetration 332 Modification SM 77-1682.4, Penetration Testing Modification Penetration 107 SM 76-27.1, Penetration 332 Modification Rl 77-1682.1, Penetration Testing Modification Penetartion 304 RSSP-13.6, Inservice Inspection Hydro Test of Class "C"

Safety Related Piping SM 77-1660.15, Instrumentation Tie-ins for RCS Overpressurization SM 78-1485.1, Dillon Cell Storage Frame SN 78-1480.1, A RCP Ladder and Handrail Installation SN 78-1865.1, Steam Generator "A" Air Mover Installation M-37.11, Repair and Inspection of Pressurizer Power Operated Relief Valves 430 and 431C SN 78-1888.1, Spray Additive Tank Recirculation Line Shutoff Valve Installation SN 76-26.5, Installation of 7.5 KVA Floor Munted

. Constant Voltage Transformer Backup Supply for Instrument Busses A, B, C, and D

PT 32.2, Initial Checkout of the KS Overpressure Protection System SN 77-1660.24, KS Overpressure Protection Loop 455 Rack W2 Instrumentation and Wiring 33 33 33 33 33 34 34 34 34 34 34 34 35 35 35 635 655 S-12.4, RCS Leakage Surveillance Record Instructions 35 RF-2, Reactor Refueling Outage Operations and Activities 35 649 691 690 RF-2E, Draining of Refueling Canal RF-14.4.1, Relaxing and Removing Reactor Vessel Head

Studs, Stud Hole Plugs and Guide Stud Installation RF-14.412, Removing Reactor Vessel Guide Studs and Stud Hole Plugs, Installating and Tensioning Head Studs 35 35 35 PCN 4 78 Procedure

& Title Meetin N 78 688 706 697 627 647 648 662 675 672 HP-4.1, Controlled Area Entry S-SA, Component Cooling Water System Startup and Normal Opeation Valve Alignment M-47.1, Inspection of Pressurizer Internals M-44.2, Isolation and Restoration of Motor Control Center 1A CP-924.0, Calibration and/or Maintenance of Safety Injection Flow Loop "B" CP-925.0, Calibration and/or Maintenance of Safety Injection Flaw laop "A" BSSP-15.7, Inservice Inspection Hydro Test of Class "B"

Safety Related Piping (Charging Piping)

S-4.5.9, Letdown Deborating DI (A or B) Resin Replacement GS-17.0, Accountability of Personnel During Emergency Conditions 35 35 35 35 35 35 35 35 35 660 669 GS-31.0, Door Alarm System 35 RF-2; Reactor Refueling Outage Operations and Activities 35 707 705 704 671 RF-8. 2, Fuel Handling Instruction Pre-Loading and Periodic Valve Test 0-1.1B, Establishing Containment Integrity RF-2B, Recpired Valve Line-.Up for Reactor Head Removal HP-4.3, Work Permit Use 35 35 35 35 628

629, 623 0-2.5, Plant Shutdown from Hot Shutdawn to Cold Shutdown 35 When Condenser Steam Dump is Unavailable 0-2.4, Plant Shutdown from Hot Shutdown to Cold Shutdown 35 During Blackout 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 78 694 695 693 692 703 PT-2.7, Service Water System PT-3, Containment Spray Pumps and NaOH Additive System PZ-2.2, Residual Heat Removal System PT-2.1, Safety Injection System Pumps PT-2. 4, Cold/Refueling Motor Operated Valve Surveillance 35 35 35 35 651 702 701 698 315 640 RSSP-1.1, Valve Interlock Verification Residual Heat Removal System RSSP-3.0, Verification of Emergency Start Logic Auxiliary Feedwater Pumps PT-2. 5, Air Operated Valves Quarterly Surveillance SC-3, Fire Emergency Plan QC-1003, Control of Inservice Inspection Activities QC-103, Periodic Review of Quality Control Procedure 35 35 35 35 35 35 638 a 639 QC-201, Ginna Quality Control Organization

.QC-303, Control of System Modification Activities 35 35 652'20 S-3.1N, Isolation of Miscellaneous Valves in the Boric Acid Storage Tank Room SM 77-1682. 2, Penetration Testing Modification Penetration 202 36 36 714 710 SM 75-14, Boric Acid Batch Tank Recirculation Piping and Supports

&I 76-28.2, Flange Installation on Feedwater Flow Venturis A Feedwater Line 36 36 721 711 713 CP-455.0, N2 Accumulator Pressure Low Loop 45S S-3.2A, Charging and Volume Control Systen Pre-Startup Alignment P-8, Precautions, Limitations and Setpoints Waste Disposal System 36 36 36 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 36 723 722 767 EM-155, Safeguard Rack Relays VI and/or CI Replacement M-81, Safeguard Rack Ventillation and Containment Isolation Relays Replacement A-54.6, Health Physic's Tour S-2.3B, Burping the Pressurizer Relief Tank with N2 (Not to ke Opened the Atmosphere) 36 36 37A 774 M-40.1, Hydraulic Snubber Unit Removal and Reinstallatio 37A Procedure 766'24 725 726 727 728 RF-2, Reactor Refueling Outage Operations and Activities ISI-2.1.7, Quality Group B Inservice Inspection ISI-2.1.8, Quality Group B Inservice Inspection ISI-2.1.9, Quality Group B Inservice Inspection ISI-2.2.1, Quality Group B Inservice Inspection ISI-2.2. 2, Quality Group B Inservice Inspection 37A 37 37 37 37 37 729 730 ISI-2.2. 3, Quality Group ISI-2. 2. 4, Quality Group B Inservice Inspection B Inservice Inspection 37 37 731 732 733 734 735 736 737 738 739 ISI-2.2.55 Quality Group B Inservice Inspection ISI-2.2.6, Quality Group B Inservice Inspection ISI-2.2.7, Quality Group B Inservice Inspection ISI-2.2.8, Quality Group B Inservice Inspection ISI-2.2. 9, Quality Group B Inservice Inspection ISI-2.3.1, Quality Group B Inservice Inspection ISI.3.22 Quality Group B Inservice Inspection ISI-2.3.3, Quality Group B Inservice Inspection ISI-2.3.4, Quality Group B Inservice Inspection 37 37 37 37 37 37 37 37 37 PCN I 78 Procedure 6 Title Meetin I 78 740 741 742 743 744 745 746 747 748 749 750 751 680 681 789 771 784 768 712 752 716 791 780 ISI-2.3.5, Quality Group B Inservice Inspection ISI-2.3.6, Quality Group B Inservice Inspection ISI-2.3.7, Quality Group B Inservice Inspection ISI-2.3.8, Quality Group B Inservice Inspection ISI-2.3. 9 Quality Group B Inservice Inspection ISI-2.4.1, Quality Group B Inservice Inspection ISI-2.4.2, Quality Group B Inservice Inspection ISI-2.4.3, Quality Group B Inservice Inspection ISI-2.4.4, Quality Group B Inservice Inspection ISI-2.4.5, Quality Group B Inservice Inspection ISI-2.4. 6, Quality Group B Inservice Inspection ISI-2.4.7, Quality Group B Inservice Inspection S.5.11, "B" Letdown Deborating DI Replacement S-4.5.10, "A" Letdown Deborating DI Resin Replacement PT-23A, Containment Isolation Valve Test Connection Boundary Control RF-2, Operations and Activities T-16A, Turbine Pre-Statup O-l. 1B, Establishing Containment Integrity T-41A, Alignment of Auxiliary Feedwater System Prior to Power Operation O-l. 1B, Establishing Containment Integrity S-2.5B, Restoring Reactor Coolant Drain Tank to Service After Maintenance PZ-7, Hydro Test of Reactor Coolant System ISI-1.1.8, Quality Group A Inservice Inspection 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 PCN -5 78 Procedure

& Title Meetin I 78 782 781 ISI-3.1.5, High Energy Inservice Inspection ISI.1.6, Quality Group B Inservice Inspection 37 37 785 PT-13.1.1, Protomatic Deluge Valve System Testing Systen 37 Number 7, 8, 9, 10 787 777 795 794 793 718 778 769 788 770 753 708 779 717

790, 783 PZ-7, Hydro Test of Reactor Coolant System ET-23.3, Containment Isolation Valves Leak Bate Testing Makeup Water to Pressurizer Relief Tank Line FT-32.2, Initial Checkout of the RCS Overpressure Protection System ISI-1.1.9, Quality Group A Inservice Inspection 0-6.2, Main Control Board System Status Verification M-7.3, Boric Acid Concentrates and Ion Exchanger Filter Replacement M-48.3, Isolation and Restoration of Bus 115 PC-1.3, Daily Chemistry Analysis Results HP-11.2, Iodine in Air-Charcoal Cartridge Method ISI-3.1.5, High Energy Inservice Inspection A-52.2, Control of Locked Valve Operation A-36, Station Holding Rules 0-2.3.1, Draining the Reactor Coolant System T-34A, Generator Seal Oil System Startup M-40.8, Functional Testing of Hydraulic Snubbers R1-201, "B" Steam Generator Secondary Side Peripheral Tube Removal 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 786 796 799 RSSP-13.8.1, Hydro Test of Loop A Underground Service Water Piping EM 204 I Seal Welding MOV-700 RHR from Loop A

&1 76-01.1, Safeguard Buses DC Control Voltage Mnitor 38 38 38 PCN 5 78 Procedure a Title Meetin 5 78 800 830 831 840 841 842 899 RSSP-1.4, Valve Interlock Verification - Reactor Coolant System PT-32.2, Initial Checkout of the RCS Overpressure Protection System 0-1.2, Plant from Hot Shutdcam to Steady Load S-29.1, Prealignment of the Reactor Vessel Overpressure Protection System N2 Supply System S-29.2, Charging the Reactor Vessel Overpressure Protection System Accumulators With N2 0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System EN-204, Seal Welding MOV-700 RHR "A" Loop 38 38 38 39 39 39 39 883 0-2.5, Plant Shutdown from Hot Shutdown to Cold Shutdown 39 When Condenser Steam Dump is Unavailable 792 839 O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 39 39 838 0-2.2, Plant Shutdown from Hot Shutdown to Gold Condition 39 837 834 836 0-2.3, Plant at Gold Shutdown Filling and Venting the Reactor Coolant System Plant Blackout from Hot Shutdown to Cold Shutdown During Blackout 39 39 39 835 0-2.5, Plant Shutdown from Hot Shutdown to Cold Shutdown 39 When Condenser Steam Dump is Unavailable 888 896 897 898 887 844 A-l.1, Locked Radiation Areas QC-1404, Test Status Control O-l.2.2, Critical Rod Position Calculation 0-3.1, Boron Concentration for the Hot Xenon Free Shutdown Margin ISI-4.1. 5, High Energy Inservice Inspection

&1 75-14, Boric Acid Batch Tank Recirculation Piping and Supports 39 39 39 39 40 40 PCN 4 78 Procedure

& Title Meetin I 78 845 846 847 SN 76-11.10, No.

12B Auxiliary Transformer Deluge System Tie-in SM 76-26.1, Installation of 1A Inverter and Alternate Power Supplies I

SN76-26.2, Installation of 18 Inverter and Alternate Power Supplies 40 40 40 848 849 850 SN 76-26.3, Installation of 7.5KV Floor Mounted Constant 40 Voltage Transformer 1A SN 76-26.4, Installation of 7.5KV Floor Mounted Constant 40 Voltage Transformer 1B SN 76-26.5, Installation of 7.5KV Floor Haunted Constant 40 Voltage Transformer Backup Supply for Instrument Buses A, B, C and D

851 852 853 854 855 856 857 858 RI 76-27.1, Penetration 332 Modification SN 76-28.2, Flange Installation on Feedwater Flow Venturis A Feedwater Line RI 77-02.1, Demineralized Water to Containment Modification Mechanical SN 77-02.2, Hydrostatic Testing and Initial Service Leak Test of the Demineralized Water to Containment Modification SM 77-2.10, DI Water Containment Isolation Electrical Conduit and Wiring SN 77-02. 12, Demineralized Water Containment Isolation SN 77-02.15, Air Tie-in for the DI Water to Containment SM 77-1057.1, Relocation of the CHarging Pump Filter Vent 40 40 40 40 40 40 40 40 860 861 862 SN 77-1660.10, RCS Overpressurization Protection Electrical Conduit and Wiring SN 77-1660.11, RCS Overpressurization Protection Electrical Terminations in the Control Room and in the Field SN 77-1660.15, Instrumentation Tie-Ins for RCS Overpressurization 40 40 40 PCN 5 78 Procedure

& Title Meetin I 78 863 864 865 866 867 868 869 870 871 872 873 874 875

'I 876 877 878 879 887 SN 77-1660.21, BCS Overpressure Protection Loop 450 Rack B2 Instrumentation Installation and Wiring SM 77-1660.22, RCS Overpressure Protection Loop 451 Rack W2 Instrumentation Installation and Wiring SN 77-1660.23, KS Overpressure Protection Lcop 452 Rack R2 Instrumentation Installation and Wiring SN 77-1660.24, BCS Overpressure Protection Loop 455 Rack W2 Instrumentation Installation and Wiring SN 77-1660.25, RCS Overpressure Protection Loop 456 Rack R2 Instrumentation Installation and Wiring SN 77-1660.26, BCS Overpressure Protection Loop 409 Rack RCS2 Instrumentation Installation and Wiring SM 77-1660.27, KS Ovezpressure Protection Loop 410 Rack RCS2 Instrumentation Installation and Wiring SN 77-1660. 28, Overpressure Protection Rx3ification of.the Belay Backs SN 77-1660.29, Overpressure Protection Rx3ification Annunciator Wiring SN 77-1682.1, Penetration Testing Modification Penetration 304 SN 77-1682.2, Penetration Testing Modification Penetration 202 B4 77-1682.3, Penetration Testing Rx3ification Penetration 210 SM 77-1832.1, Flame Retardant Cable Coating in the East Cable Vault SN 77-1480.1, "A" RCP Ladder and Handrail Installation SM 78-1485.1, Dillon Cell Storage Frame SM 78-1865.1, Steam Generator "A" Air Mover Installation Rf 78-1890.1, Feedwater Line Drain Valves Before the Containment Check Valves ISI-4.1.5, High Energy Inservice Inspection 40 40 40 40 40 40 40 40 40

'40 40 40 40 40 40 40 40 40

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

PCN 4 78 Procedure a Title Meetin 5 78 989 938 937 953 967 SM 75-50.30, Rework of Jet Shielding for Main Steam Bypass Piping and Valves ET-13.1.5, Flood Valve System Testing System Numbers 3, 4, 5, 6

RSSP-13.8.1, Hydro Test of Loop A Underground Service Water Piping S-29.1, Prealignment of the Reactor Vessel Overpressure Protection System N2 Supply System SM 75-34.23, Pipe Restraining and Jet Shields Rework for Steam Generator Blowdown Lines 42 43 43 43 43 906 M-ll.8D, Reactor Coolant Pump iWjor Inspection and Service Instrument and Control 43 941 801 802 803 804 805 806 807 808 809 810 811 812 813 814 815 816 RSSP-13.8.1, Hydro Test of Loop A Underground Service Water Piping ISI-4.1.6, Quality Group A Inservice Inspection ISI-4.1.7, Quality Group A Inservice Inspection ISI-4.1.8, Qaulity Group A Inservice Inspection ISI-4.1.9, Quality Group A Inservice Inspection ISI-4.2.1, Quality Group A Inservice Inspection ISI-4.2. 2, Quality Gruop A Inservice Inspection ISI-4.2.3, Quality Group A Inservice Inspection ISI.2.4, Quality Group A Inservice Inspection ISI.2.5, Quality Group A Inservice Xnspection ISI.2.6, Quality Group A Inservice Inspection ISI.2.7, Quality Group A Inserviee Inspection ISI-4.2. 8, Quality Group A Inservice Inspection ISX-.4.2. 9, Quality Group A Inservice Inspection ISI-4.3.1, Quality Group A Inservice Inspection ISX-4.3. 2, Quality Group A Inservice Inspection ISI-4.3.3, Quality Group A Inservice Inspection 43 43 43 43 43 43 43 43 43 43 43 43 43 43 PCN 4 78 Procedure 6 Title Meetin 5 78 817 818 819 820 821 822 823 824 825 826 827 828 829 947 956 ISI-4.3.4, Quality Group A Inservice Inspection ISX-4.3.5, Quality Group A Inservice Inspection ISI-4.3.6, Quality Griup A Inservice Inspection ISI-4.3.7, Quality Group A Inservice Inspection ISX-4.3.8, Quality Group A Inservice Inspection ISX-4.3.9, Quality Group A Inservice Inspection ISX-4.4.1, Quality Group A Inservice Inspection ISI-4.4.2, Quality Group A Inservice Inspection ISI-4.4.3, Quality Group A Inservice Inspection ISI-4.4.4, Quality Group A Inservice Inspection ISI-4.4. 5, Quality Group A Inservice Inspection ISX-4.4.6, Quality Group A Inservice Inspection ISX-4.4.7, Quality Group A Inservice Inspection PR-5, Relay Calibration and Trip Test 4160 Volt Auxiliaries Circuit 0-1.2.1, 1/M Curves 43 43 43 43 43 43 43 43 43 43 43 43 43 43 43 961 881 CP-70. 5, Test Gauge Calibration Procedure HP-1.1, Issuing Personnel Dosimeters 43 43 954 A-30.3, Plant Procedure Content and Format Requirements 43 960 959 958 957 948 A-l, Radiation Control Manual A-l.3, Smearing Procedure S-4.4.1, Spent Resin Package Site Receipt and Shipment RD, Gas Decay Tank Release PT-2.1, Safety Injection System Pumps 43 43 43 43 949 PZ-23.5A, Containment Isolation Valve Leak Rate Testing 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, 939 993 944 946 945 SC-3.12, Plan for Recovery from Fire M-67. 3, Flood Valve System Maintenance System Numbers 3, 4, 5, 6

O-l.2. 2, Critical Rod Position Calculation GS-26.1, Unoccupied Vital Area Key Control and Accountability GS-10.0, Security Personnel Actions During a Radiation Emergency GS-17.0, Accountability of Personnel During Emergency Condition 43 43 43 43 43 43 943 GS-30.0, threatening Phone Call or Bomb Threat Procedure 43 993 1024 1023 907 908 909 910 911 912 913 914 915 916 PT-34.6, At Power Physics Testing CP-502.1, Calibration of 1A Emergency Diesel Kilowatt Meters CP-502.2, Calibration of lB Emergency Diesel Kilowatt Meters ISI-3.1. 5A, Quality Group C Inservice Inspection ISI-3.1. 6, Quality Group C Inservice Inspection ISI-3.1.7, Quality Group C Inservice Inspection ISI-3.1.8, Quality Group C Inservice Inspection ISI-3.1. 9 Quality Group C Inservice Inspection ISI-3.2.1, Quality Group C Inservice Inspection ISI-3.2.2, Quality Group C Inservice Inspection ISI-3.2.3, Quality Group C. Inservice Inspection ISI-3.2.4, Quality Group C Inservice Inspection ISI-3.2.5, Quality Group C Inservice Inspection 44 44 44 45 45 45 45 45 45 45 44

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

45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 45 PCN I 78 Procedure

& Title Meetin I 78 1013 1004 951 952 M-37.38.1, Crosby Safety and Relief Valve Maintenance M-73.3, Welding on Carbon Steel Piping and Components S-27.5.3, RCS Loop Sample Valves Isolation S-27.5.2, Pressurizer Lie@id Space Sample Isolation Valves 45 45 45 968 943 974 969 970 971 972 859 1034 1033 1026 E-39.0, Fire at Facility E-39.1, Containment Vessel Fire E-39. 2, Relay/Computer Room Fire E-39.3, Grinnell Deluge System Fire E-39.4, Smoke Detector Area Fire E-39. 5, Sprinkler System Fire E-39.6, Auxiliary Building/Controlled Area Fire SM 77-1660.2, Overpressurization Mechanical Package SM 78-1873.1, Pressurizer Jib Crane SM 78-1888.1, Spray Additive Recirculation Line Shutoff Valve Installation SM 77-02.11, Electric Terminations at Valve 8418 and in Control Room for DI Water to Containment 45 45 45 45 45 45 45 45 45 45 45 1000 999 0-2.4, Plant Shutdown from Hot Shutdwon to Cold Shutdown 45 During Blackout 0-2.2, Plant Shutdown from Hot Shutdown to Gold Condition 4S 1015 ET-6.3.3, Power Range Nuclear Instrumentation System Channel 43 45 1014 1016 1017 PZ-6.3.4, Power Range Nuclear Instrumentation System Channel 44 PZ-6.3.2, Power Range Nuclear Instrumentation System Channel 42 PT-6.3.1, Power Range Nuclear Instrumentation System Channel 41 45 45 45 PCN 4 78 Procedure a Title Meetin I 78 1008 1007 942 1006 1010 1009 1002 1005 PZ-6.1, Source Range NIS ET.2, NIS Intermediate Range A-1.2, Air Sampling Procedure CP-128.3, Charging Line Flow Transmitter FT-128 and Local Indicator FI-128A A-2.6, Incore Flux Map Data. Reduction and Review S-12.4, RCS Leakage Surveillance Record Instructions A-36, Station Holding Rules CP-128.0, Calibration and/or Maintenance of Changing Line Flow Channel "128" 45 45 45 45 45 45 45 1012 1020 309 1052 1092 1036 1059 CP-628, RHR Loop Reactor Coolant Test Bypass Flow SM 75-58.8, Modification of Walkway and Railings Around the Spent Fuel Pool SC-3.14.2, Fire Department and Fire Brigade Drill 0-6.9, Opeating Limits for Ginna Station Transmission

&I 76-16.1, Eddy Current Wiring Conduits 0-2.1, Normal Shutdown to Hot Shutdown PZ. 4, 'Excore/Incore Recalibration 45 45 46 46 46 46 1056 SM 77-1498.1, Zaw Power Steam Generator Feedwater ~s 46 Control Reification 1055 1053 1044 Rl 78-1048.1, Accumulator Relief Rx3ification for Accumulator Relief Line SM 76-01.2, Cable Installation for the DC Control Fuse Honitor System SM 75-41.31, Condensate Polishing System Control Board Operational Check 46 46 46 1089 a 1043 SM 75-5.40, Standby Auxiliary Feedwater Rework Inside Containment 46 1087 SM 75-34.23, Pipe Restraints and Jet Shields Rework for Steam Generator Blowdown Lines 46

PCN I 78 Procedure a Title Meetin I 78 1083 1042

& 1088 SM 75-5.50 Aux' Aux'.iary Feedwater Hanger AEW-51 Repair SM 75-58.8, Modification of the Walkw o

e ay and Railings 1084 SM 75-50.30, Rework of Jet Shield'n SM ze mg on Main Steam 46 1085 SM 75-48.30, Rework of the Auxilia'y Feedwater Crossover 46 1086 1050 1049 1041 1040 1028 1048 1054 990 1058 1057 1119 1123 1108 1107 1097 1099 SM 75-47.30 Re

, Rework of CVCS Hangers Inside Containment M-38.3,

1B Inveiter Maintenance o

Re or pair M 38 '

ia

, L~ Inverter Maintenance o

Re or paar M-38.4, 1A Constant Volta or Repair ge Transformer Maintenance M-38.5, 1B Constant Volta or Repair ge Transformer Maintenance 0-1.1C, Pre-Critical Technical Sheet x

~~cification Check 9 -2701, Quality Assurance Records 0-7 Al' Alignment and Operation of the Overpressure Prot t

'cion System e Reactor Vessel

, GS-26.1, Unocc ied up'ital Area Key Control and ccountability T-26, 125 Vo I

lt DC and Station Battery System PT-17.3 Source 7.3, RMS Channel Response to Po tab r

le Radiation M-11.8K, Reactor Coolant Pump Mototor Minor Inspection S-17B, Addition of 50% NaOH aOH to the Spray additive Tank TICP-.l, Test Instrument Calibration Procedure TICP-2, Test Instrument Calibration Procedure PT-13.1.9, Halon System Testing and'or (Resetting)

Comput Room mpu er Room and Relay Room PT-13.l. 3 Deluge Valve System Testing Numbe rs 1, 2, ll 46 46 46 46 46 46 46 46 48

'8 48 48 48 48

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

PCN 5 78 Procedure

& Title Meetin 4 78 1210 1211 1212 1213 1214 1215 1216 1217 1218 1046 1047 1160 1164 1230 1223 1224 1222 ISI-1.2.1, Quality Group A Inservice Inspection ISI-l.2.4, Quality Group A Inservice Inspection ISI-1.2.7, Quality Group A Inservice Inspection ISI-1.3.1, Quality Group A Inseryice Inspection ISI-1.3.4, Quality Group A Inservice Inspection ISI-1.3.7, Quality Group A Inservice Inspection ISI-1.4.1, Quality Group A Inservice Inspection ISI-1.4.4, Quality Group A Inservice Inspection ISI-1.4.7, Quality Group A Inservice Inspection PZ-23.14, Containment Isolation Valve Leak Rate Testing Containment Air Sample Inlet PT-23.15, Containment Isolation Valve Leak Rate Testing Containment Air Sample Outlet A-53. 0, Preventative Maintenance Program A-53.2, three bhnth Lubrication and Maintenance Inspection SM 76-21.7, Battery Room Air Conditioning Misc.

SM 76-21.4, Battery Rocm Air Conditioning Air Conditioner Discharge Duct South End of Battery Room PT-13.1.1, Protomatic Deluge Valve System Testing System Numbers 7, 8, 9, 10 SM 76-21.6, Battery Rocm Air Conditioning Air Supply Duct to the Air Conditioner 49 49 49 49 49 49 49 49 49 49 49 49 49 49 49 49 1221 1162 1163 SM 76-21. 5, Battery Bcxm Air Conditioning Service Water Piping Installation SC-3, Fire Emergency Plan A-50.2, R. E. Ginna Health Physics Orientation Program 49 49 49 PCN 5 78 Procedure a Title Meetin I 78 1161 1121 1165 964 1153 1151 SM 75.24, MSZ Jet, Shielding Installation Rework M-47.1, Inspection of Pressurizer Internals ET-l, Rod Control System M-43.8 Eddy Current Testing of Series 44 Steam Generator Tubes M-64.1, Periodic Surveillance and Minor Maintenance of Limitorque Rotor Operated Safeguard Valves M-37.53, RHR Core Deluge Valve 852A, and 852B Isolation and Packing 49 49 49 49 49 49 1152 M-37.55, Spray Additive Tank Discharge Valves HCV-836A/B 49 Inspection and Maintenance 1150 1149 1148 M-37.51, Component Cooling Water Surge Tank Local Vent Valve RCV-017 Repair and Inspection M-37.50, MOV-721 RHR to "B" Zoop Maintenance and Inspection M-37.49, Level Control Valve from "B" RCS Loop LCV-427 Maintenance and Inspection 49 49 49 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 Maintenance and Inspection 49 1145 1144 M-37.42, MOV-813 and/or MOV-814 Isolation and Maintenance 49 M-37.40, Maintneance cn Wtor Driven Auxiliary Feedwater 49 Pumps Discharge Valves MCV-.4007 or MOV-4008 1154 1143 1142 1141 M-64.2, Limitorque Valve Operator Maintenance and Inspection M-37.36.4, Nuclear Sample System Air Operated Valve Maintenance M-37.35, Valves 3504 and 3505; Main Steam to Turbine Driven Auxiliary Feed Pump Maintenance M-37.19, Removal of Limitorque Motors and/or Repacking of Gate Valves 860, A,B.C,GD 49 49 49 49

PCN 4 78 Procedure

& Title 1140 1139 1138 1137 1136 M-37.16J, Inspection and Maintenance of the Rotor Drive Auxiliary Feed Pump Recirculation Control Valve N-37.15.1, Inspection and Maintenance of 48" Butterfly Valve, Model R-lA8 Valve Operator M-37.15, Replacing or adjusting Rubber Seat Seat in Purge Supply and Exhaust Valves N-37.10, Grinnell Diaphragm Valves, Air-

Operated, Maintenance M-37.3, Maintenance on Copes-Vulcan Diaphragm Operated Control Valves for AOV 49 49 49 49 49 1131 1129 1128 1127 1134 1132 1135 1133 1130 None 1242

, 1288 M-ll.10, Major Inspection of Service Water Pump M-ll.14, Inspection and Maintenance of Ingersol Rand Pumps N-37.0, Repacking of Air Mtor Operated Valves M-11.15, RHR Pumps Inspection/Maintenance M-11.5B, Major Mechanical Inspection of the Auxiliary Feed Pumps for Pump N-ll.5K, Turbine Driven Auxiliary Feedwater Pump Major or Mechanical Inspection M-11.5C, Minor Mechanical Inspection of the Auxiliary Feed imps for Pump N-11.5E, Pipefitters Inspectxon of Nctor Driven Auxiliary Feed Pump for Pump M-ll.12.1, Safety Injection Pump, Mechanical

Inaction, A-54.6, Health Physics 'Ibur week of 6/12/78 ET-16, Auxilairy Feedwater System S-4.4, Spent Resin Removal to Shipping Casks 49 49 49 49 49 49 49 49 50 50

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

.Closure Time 50 50 50 50 50 1239 1240 1241 1271 1274 1275 1276 RSSP-7.0, Control Rod Drop Test RSSP-8.0, RTD Cross Calibration Check PR-5, Relay Calibration and Trip Test 4160 Volt Auxiliaries M-43.31, Hand Hold Gasket Seating Surface Repair M3.29, Steam Generator Inner Sleeve Removal and/or Split Ring Assembly Removal M-3.2, Reactor Cavity Cleanup and Decontami-nation M-54.2, Condenser Water Box Leak Testing with Freon 50 50 50 50 50 50 50 PCN I 78 Procedure

& Title Meeting I 78 1277 M-43.27, Steam Generator Secondary Side Handhole Cover Removal 50 1278 M-43.28, Steam Generator SEcondary Side Manway Cover Removal 50 1270 M-18.1, Drum Preparation for Waste Evaporator Bottoms 50 1281 1207 M-43. 26, Installation of Steam Generator Secondary Manway Cover S-3.3D, CVCS Cation Demineralizer Bed Opera-tions Using "A" Dekorating D. I.

Unit 50 50 1206 1205 S-3.3F, Reactor Coolant System pH Control S-3.4I, Recirculation of Monitor Tank for nArs or nBss Moni 50 50 1204 S-3.4K, Releasing Monitor Tank to Discharge Canal 50 1203 S-3.4M, b$onitor Tank Recirculation through Evaporator D. I.

50 1202 S-3.4N, Calculations for Boron Recycle Process Using 2 HVZ's 50 1201 1200 S-3.4P, Transferring Concentrates from Boric Acid Evaporator Feed Tank to Waste Evaporator Feed Tank for Drumming S-3.4R, Transfer of any CVCS HUZ to Another CVCS HVZ 50 50 1198 1197 S-3.4T, Regeneration of the Boric Acid Evaporator "B" Condensate D. I.

S-3.5, Deborating Demineralizer "B" Regen-eration 50 50 1196 S-4.1F, Waste Condensate Polisher Recircu-lation 50 1195 S-4.1L, Reverse Osmosis Unit Startup and Shutdown 50 1194 S-4.1N, Transfer Waste Holdup Tank to "A" Monitor Tank 50 PCN I 78 Procedure a Title Meetin I 78 1193 S-4.1R, Transfer of Chemical Drain Tank to Reverse Csmosis Feed Tank 50 1192 1191 1190 1189 1188 1187 1186 1185 S-4.1S, Alternating Waste Evaporator Cart-ridge Demineralizers S-.4.1T, Alternating Waste Evaporator Conden-sate Polishing Demineralizers S-4.1U, Velocity Flush of R-18 S-4.1Y, Laundry Tank Release Using Chemical Drain Pump S-4.5. 2, Waste Condensate Polishing Deminer-alizer Resin Replacement S-4.5.4, Boron Recycle Base Reneval D. I.

Resin Replacement S-4.5.5, Boron Recycle Cation D. I., Resin Replacement S-4.5.6, Spent Fuel Pit, D. I. Resin Replace-ment 50 50 50 50 50 50 50 50 1184 1183 1182 1181

,1199 1180 1179 1178 1177 S-4.5.7, Letdown Mixed Bed D. I. Resin Replace-ment S-4.5.8, Eetdown Cation D. I. Resin Re-placement S-5, Nuclear Sample Room Sampling System S-8, Component Cooling system S-3.4S, Regeneration of the Boric Acid Evaporator "A" Condensate D.

I.

S-9J, Blending to EST S-9K, Transferring Water From Monitor Tank to Spent Fuel Pit S-9L, Batching Boric Acid and Transferring

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

'0 50 50 50 PCN I 78 Procedure 6 Title Meetin 5 78 1176 1175 1209 1208 1174 1173 1172 1171 1170 1169 S-10.1, Part Length Rod Control S-14.2, Determination of the Percent of Tech.

Spec.

Limits for Radioactive Release S-3.2C,. Placing and Removing from Service "B" Hot Leg Charing Valve 392A S-3.3C, H2 or 02 Removal from Primary System by Bumping VCT with N2 S-16.3, Vent N2 from the "A" Accumulator S-16.4, Vent N2 from the "B" Accumulator S-16.9, Charging of the "A" Accumulator with Nitrogen S-16.10, Charging of the "B" Accumulator with Nitrogen S-16.13, Water Makeup to the Accumulator S-23.5, Post Accident Charcoal Filter Opera-tion 50 50 50 50 50 50 50 50 50 50 1168 1167 1267

,1260 1259 1258 1257 1018

'1229 1247 1226 S-25. 5, Steam Generator Radioactive Release S-26.4, Computor Rod Postion Alarm Program M-57.1, Power Range NIS Detector Replacement E-29.1, Zass of Normal Feedwater (Not Recover-erable)

E-26.4, Mrbine Trip Without Reactor Trip E-16.2, High Iodine 1313 in the Plant Vent E-13.1, Power Range NIS Malfunction (PR 41, 42, 43, 44)

A-l, Radiation Control Manual HP-6.2, Posting of Contaminated and Airkarne Areas 0-2.1, Normal Shutdown to Hot Shutdown PT-2.3.1, Post Accident Charcoal Filter Dmtpers 50 50 50 50 50 50 50 50 50 50 50 PCN N 78 Procedure 6 Title Meeting N 78 1269 1227 1264 1262 1268 1263 1286 1246 1245 1244 1248 1249 1250 HP-1.1, Issuing Personnel Dosimeters HP-1.3, External Exposure Records M-18, Acid Cleaning of Waste Evaporator HP-4.3, Work Permit Use T-7E, Water Treatment-Carbon Filter Backwash S-4.1D, Drumming Waste Evaporator Bottoms A.C.-1701, Quality Assurance Records 0-1.2, Plant From Hot Shutdown to Steady Load 0-1.3, Reactor Startup for Training PZ-34.0, Startup Physics Test Program PZ-23.16A, Containment Isolation Valve Leak Rate Testing "A" Steam Generator Blowdown PZ-23.16B, Containment Isolation Valve Leak Rate Testing "B" Steam Generator Blowdown PZ 23.17A, Containment Isolation Valve Leak Rate Testing Containment Pressure Sensing Transmitter PT-945 and PT-946 50 50 50 50 50 50 50 50 50 52 52 52 1251 PZ-23.17B, Containment Isolation Valve Leak Rate Testing Containment Pressure Sensing Transmitter PT-947 and PT-948 52 1252 ET-23.17C, Containment Isolation Valve Leak Rate Testing Containment Pressure Sensing Transmitter PT-949 and PT-950 52 1255 1256 1253 1254 PZ-23.18B, Containment Isolation Valve Leak Rate Testing "B" Containment Spray Header ET-23.19, Containment Isolation Valve Leak Rate Testing Safety Injection System ET-23.20, Containment Isolation Valve Leak Rate Testing R., C.

D.

T.

Gas Header PZ-23.21, Containment Isolation Valve Leak Rate Testing R.

C.

D.

T.

Gas Analyzer 52 52 52 52

1 PCN I 78 Procedure a Title Meetin I 78 719 1293 1287 1283 1279 1285 1317 1318 1328 1315 1329 1295 1348 1347 1343 1032 1323 1322 1342 1341 M-37.57, Containment D. I. Check Valve 8419 Mainteannce

&~~9.1, Manipulator Crane RF-2A, Requirements for Reactor Head Removal RF-8.1, Step-by-Step Fuel Loading and Maps M-15.1, "A" or "B" Diesel Generator Removal From Service M-15.3.1, 1A Diesel Generator Solenoid Valves 5907 and/or 5907A Maintenance HP.3, Air Ejector Gas Sampling HP-9.2, Primary to Secondary Leakage Detection and Measurement PZ-3, Containment Spray Pumps NaOH Additive System M-18, Acid Cleaning of Waste Evaporator 0-6.9, Operating Limits for Ginna Station Transmission S-9M, Adding Reactor Makeup Water to Spent Fuel Pit

. W-1701, Quality Assurance Records 0-6.11, Routine Operations Check Sheet

= A 37 1 I System Modification Requirements A-50.9.2, Non-Licensed Staff Retraining Program GS-31.0, Ecor Alarm System GS-28.0, Inspection of Personnel Vehicles and Packages A-37.0, Conduct of Operations for Safety-Related Evaluations as related to Facility or Rxiifications, Special Tests, Experiments A-50.2, R. E. Ginna Health Physics Orientation

Program, 52 52 52 52 52 52 52 52 52 52 52 53 53 53 53 53 53 53 53

PCN 5 78 Procedure a Title Meetin 5 78 1340 PC-18.3, Determination of Chloride kp Speci-fic Ion Electrode 53 1330

'-40.1, Hydraulic Snubber Reaaval and Rein-.

stallation Procedure 53 1324 1326 1325 1354 1355 1356 1357 1358 1359 1360 1361 1362 1363 1364 1366 1368 1367 XT-34.1, Initial Criticality and ARO Boron Concentration M-40.8, Functional Testing of Hydraulic Snubbers RSSP-12, Testing of Primary and Secondary Relief Valves in Test Stand AR-AA-'2, AVT Water Treatment Panel Trouble AR-AA-4, Standby Auxiliary Feedwater HVAC Trouble AR-AA-5, Standby Auxiliary Feedwater Pump CAR C or D Trip AR-AA-6, KS Overpressurization Army'Inhibit Loop "A" Select AR-AA-7, RCS Overpressurization Arrq/Inhibit Loop "B" Select AR-AA-9, Condensate Booster Pump Pressuriza-tion Trip AR-AA-10, Condensate Booster Pump Trip AR-AA-14, N2 Accumulator, V-801A Tow Pressure AR-AA-15, N Accumulator, V-801B Imr Pressure AR-AA-22, KS Overpressurization Protection High Pressure Train "A" AR-AA-23, RCS Overpressurization Protection High Pressure Train "B" AR-AA-25, Condensate System Low Pressure AR-AA-29, Condensate

+stem Low Pressure Drop AR-AA-30, Condensate Booster Pump Low Suction Pressure 53 53 53 55 55 55 55 55 55 55 55 55 55 55 55

PCN I 78 Procedure a Title Meetin I 78 1365 1332 1333 1331 1385 1386

. 1387 1388 1389 1390 1391 1392 1336 1337 1338 1339 1370 AR-AA-31, RCS Overpressurization Protection High Pressure Train "C" NC-1, A List of Sample Chemical Parameters and Sampling Schedule HP-7.3, Calibration of Alpha Survey Instruments GS-41, Photography at Ginna Station SC-3.17.3, Fire Brigade Drill Records SC-3.17.1,

Planning, Conduct and Evaluation of a Fire Emergency Drill SC-1.10, Planning Conduct and Evaluation of a Radiation Emergency Drill A-50.11.4, General Employee Fire Txaining A-S0.11.2, Fire Department Familiarization A-50.11.1, Fire Brigade Training A-50.11.0, Fire Fighting Organization and Training Program A-50.7, Emergency Coordinator Training Program PZ-6.3.1, Power Range Nuclear Instrumentation

System, Channel 41 PZ-6.3.2,

System, Channel 42 PT-6.3.3, Power Range Nuclear Instrumentation

System, Channel 43 PT-6.3.4, Power Range Nuclear Instrumentation

System, Channel 44 M-ll.8C, Reactor Coolant Pump Major Inspec-tion in Service Electrical 55 55 55 55 55 55 55 55 55 55 55 55 55 1371 M-ll.8B, Reactor Coolant Pump Seal Inspec-tion and Service Mechanical 55 1383 A-30.2, Plant Procedure Classification,

Review, Approval and Distribution Requirements 55 PCN I 78 Procedure

& Title Meetin I 78 1372 1377 1345 1335 1369 1373 1374 1376 1378 1384 1393 1382 1381.

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

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

PCN 5 78 Procedure a Title Meetin 5 78 1417 M-44.10, Isolation of MCC 1K and Restoring to Service 1418 1419 1420 M-31, Stator Replacement for Part-Length Control Rod Drive System M-37.18E, ~ction and Repair of Auxiliary Building Sump Pump Discharge Check Valves M-37.18F, Inspection and Repair of 1A Auxiliary Building Sump Tank Pump Discharge Check Valve 56 56 56 1421 1422 1423 1424 M-37. 43, Accumulator Drain Valves 844A and 844B Inspection and Repair M-37.27.1, Testing and Replacement of 1B Steam Generator Blowdawn Sample Isolation Valves CV-77 *5736) or Manual Valve 5734 M-ll.26.1, Heater Drain Pump Mechanical Seal Inspection and Maintenance M-11.26, Heater Drain Pump Inspection and Maintenance 56 56 56 1425 1426 1427 1428 M-1125, Main Feedwater Pump ~ed Increase Inspection and Maintenance M-11. 23, worthington Double-Helical Rotary Pump Inspection and Maintenance M-ll.24, Main Feed Pump Inspection and Maintenance M-ll.28, Rotary Air Samples Inspection and Maintenance 56 56 56 56 1429 1430 1431 1432 1433 M-S3.1, Containment Air Loc3cs Door Gasket Replacement M-53.2, Containment Air Lock equalizing Valve Cleaning and Inspection M-37.16M, Isolation of V-356 for Maintenance M-37.18D, Check Valve 1713 Isolation N2 to R.C.D.T.

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

PCN 5 78 Procedure a Title Meetin 5 78 1434 1435 1436 1397 1143 1444 1445 1446 1447 1443 1403 1405 1406 1407 1408 1409 M-37.18C, Inspection of Rockewell Check Valves in the Waste Gas and Nitrcxjen System M-37.2.1, Repacking Pressurizer Power Relief Guard Valves 515 and 516 M-37.44, Immediate Boration Valve MDV-350 Maintenance A-50.9.1, Ginna Station Engineers (Cadet, Assistant Station and Station) Training Program A-52.2, Control of Locked Valve Operation KT-5.10, Process Instrumentation Reactor Protection Channel Trip Test (Channel 1)

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

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

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

KT-16, Auxiliary Feedwater System KT-6.3. 2, Power Range Nuclear Instrumentation

System, Channel 42 PZ-23.18A, Containment Isolation Valve Leak Rate Testing "A" Containment Spray Header PZ-23.24, Containment Isolation Valve Leak Rate Testing Reactor Support Goolers (Inlet and Outlet)

PZ-23.26, Containment Isolation Valve Leak Rate Testing Auxiliary Coolant System to "A" Reactor Coolant Pump PT-23.27, Containment Isolation Va1ve Leak

.Rate Testing Auxiliary Coolant System to "B" Reactor Coolant Pump PZ-23.28, Containment Isolation Valve Leak Rate Testing Auxiliary Coolant System Frcm "A" Reactor Coolant Pump 56 56 56 56 56 56

'56 56 56 56 58 58 58 58 58 PCN 5 78 Procedure 6 Title Meetin 5 78 1410 1411 1455 1450 1449 1451 PZ-23.29, Containment Isolation Valve Leak Rate Testing Auxiliary Coolant System From "B" Reactor Coolant Pump PT-23.30, Containment Isolation Valve Leak Rate Testing Auxiliary Coolant System Excess Letdown (Supply and Return)

A-30.3, Plant Procedure Content and Foremat Requirements AR-K31, Fire System Alarm Panel M-71. 2, Module Rework/Test Procedure 0-6.2, Main Control Board System Status Verification 58 58 58 58 58 58 1456 1438 ET-2. 2, Residual Heat Removal System RSSP-6. 0, Containment Integrated Leakage Rate Test 58 58 1334 M-40, Surveillance and Maintenance of Hydraulic Snubbers 58 1475 S-7C, Transferring and Purification of ERST Water Frcm RWST to SFP 58 1489 1496 HP-12.3, Selection of Respirators HP-7.5, Pocket Dosimeter Accuracy and Leak

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

PCN 4 78 Procedure a Title Meetin I 78 1704 1705 1613 1614 1615 h

1666 I'708 1747 1728 1729 1785 1787 1783 1782 1781 1780 1778 1777

-- 1776 CP-80.2, Calibration Procedure for Inside MicnxLeters CP-80.3, Calibration Procedure for Venier Calipers PZ-13.4.7, Protomatic Deluge Valve System Testing System XT-13.4.8, Protomatic Deluge Valve System Testing

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

, PZ-13.4.10, Protomatic Deluge Valve System Testing System 510 S-4.1.22, Waste Evaporator Feed Tank Pump Isolation Restoration ET-13.1.12, Containment Post-Accident (Recirc) and/or Auxiliary Filter RPD Testing PZ-23.36, Containment Isolation Valve Leak Rate

Testing, Purge Exhibit RSSP-8. 0, RTD Cross Calibration Check GS-28.1, Electronic Seatch Ekpipment Testing E-1.2, Loos of Coolant Accident CP-37.2, law Voltage Power Supply NQ-402 Adjustments CP-35. 3, Intermediate Raneg N-35 Calibration CP-35.4, Intermediate Range N-35 Bistable Relay Drivers Calibration CP-36.0, Intermediate Range Channel N-36 Calibration and/or Maintenance CP-36.2 N-36, General Reinstate Procedure CP-36.3, Intermediate Range N-36 Calibration CP-36.4, Intermediate Range N-36 Bistable Relay Drivers Calibration 69 69 69 69 69 69 69 69 69 69 69 69

PCN I 78 Procedure 6 Title Meetin I 78 1775 1774 1773 1772 1771 1770 1769 1768 1767 1766 CP-37.0, Calibration and/or Maintenance of

.Comparator Drawer N-37 CP-37.1, Zaw Voltage Polar Supply NQ-401 Adjustments CP-37.3, Low Voltage Power Supply NQ-403 Adjustments CP-37.4, Calibration of Level Trip Bistable Relay Driver NC-401 CP-38.0, Calibration and/or Maintenance of Detector Current Gomparator Drawer CP-38.1, Calibration and/or Maintenanoe of Power Supply NQ-601 CP-38.2, Calibration and/or Maintenance of Power Supply NQ-602 CP-38. 3, Calibration and/or Maintenance of Averaging Circuit NM601 CP-38. 4, Calibration and/or Mainenance of Averaging Circuit %1602 CP-40.0, Calibration and/or Maintenance of Delta Flux Controllers CHannel 4

69 69 69 69 69 69 69 1765 1764 1763 1754 CP-ill.ll, Reactor Nakeup Water Flow Power Supply FQ-ill CP-209.3, Nx3el HFM-3, Hand and Foot Monitor Calibration CP-210.0, Calibration and/or Maintenance 5KS Channel R-10A or R-10B CP-212. 0, Calibration and/or Maintenance of MS Channel R-12 69 69 69 69 1750 1730 1732 CP-213.0, Calibration and/or Maintenance of %IS Channel R-13 CP-35. 2, General Reinstate Procedure CP-40.0, Calibration and/or Maintenance of Delta Flux Controllers Channel 4

69 69 69

PCN I 78 Procedure 6 Title Meetin I 78 1733 1734 1735 1736 1737 1738 1739 1740 1741 1742 1743 1744 1745 1751 1752 1760 CP-30.0, Calibration and/or Maintenance of Delta Flux Controllers, Channel 3

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

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

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

CP-7.0, Calibration Alignment of T Avg. and Delta T at Zero Power Channel 3, Zaop B, Unit 1 CP-6.0, Calibration Alignment of T Avg. and Delta T at Zero Power, Channel 2, Zaop A, Unit 2 CP-5.0, Calibration Alignment pf T Avg. and Delta T at Zero Power, Channel 1, Zaop A, Unit 1 CP-2.20.5, Calibration Alignment of Pulse to Analog Converter Bank CP-2.20.4, Calibration Alignment of Pulse to Analog Converter Bank "C" CP-2.20.3, Calibration Alignment of Pulse to Ana1og Converter Bank "B" CP-2.20.2, Calibration Alignment of Pulse to Analog Converter Bnak "A" CP-2.20.1, Calibration of Pusle to Analog Converter Power Supply CP-2.20.0, Calibration and/or Maintenance of RPI Pulse to Analog Converter CP-212.3, Replacement of Detector for BNS Channel R-12 CP-212.2, Calibration of R-12 Detector CP-210.3, Replacement of Detector for RMS Channel R-10A or R-10B 69 69 69 69 69 69 69 69 69 69 1759 1758 CP-211.0, Calibration and/or Maintenance of RES Channel R-ll CP-211.1, Calibration of Ratemeter Drawer R-ll 69 PCN I 78 Procedure a Title Neetin I 78 1757 1756 CP-211.2, Calibration of R-11 Detector CP-211.3, Replacement of Detector for R'%hannel.

R-ll 69 69 1755 CP-211.4, Check of Flew Control Systen for R-ll and R-12 69 1762 CP-210.1, Calibration of Bate Meter Drawer R-10A or R-10B 69 1761 1779 1731 1753 1701 1905 1906 1907 2022 1788 1789 1790 1791 CP-210.2, Calibration of R-10A or R-10B Detectors CP-36.1, N-36, General Defeat CP-35.1, N-35, General Defeat CP-212.1, Calibration of Batemeter Drawer R-12 Rl 76-17.3, Screen House Intake Heater Cable Tray Rework EM-207, Replacing Splices and Splice Sleeves for Pressurizer Level and Pressure Channels B4-208, Containment Recirculation Fan Splices

220209, YDV-852A and 852B Splices 9 IP-30, Visual Examination of Supports CP-220.3, Replacement of Detector for R1S Channel R-20 CP-220.2, Calibration of R-20 Detector CP-220.1, Calibration of Batemeter Drawer R-20 CP-220. 0, Calibration and/or Maintenance of EBS Channel R-20 69 69 69 71 71 71 71 72 72 72 72 72 1792 1793 1794 1795 CP-219.3, Replacement of Detector for RMS Channel

-R-19 CP-219.2, Calibration of R-19 Detector CP-219.1, Calibration of Batemeter Drawer R-19 CP.-219.0, CAlibration and/or Maintenance of MS Channel R-19 72 72 72 72 PCN 5 78 Procedure a Title Meetin N 78 1796 1797 1798 CP-218.3, Replacement of Detector for EHS Channel R-18 CP-218.1, Calibration of Batemeter Drawer R-18 CP-218.0, Calibration and/or Miantenance of Et1S Channel R-18 72 72 72 1799 1800 1801 1802 CP-217.3, Replacement of Detector for EBS Channel R-17 CP-217.2, Calibration of R-17 Detector CP-217.11 Calibration of Ratemeter Drawer R-17 CP-217.0, Calibration and/or Maintenance of NS Channel R-17 72 72 72 72 1803 1804 1805 1806 CP-216.3, Replacement of Detector for RNS Channel R-16 CP-216.2, Calibration of R-16 Dtector CP16.1, Calibration of Batemeter Drawer R-16 CP-216.0, Calibration and/or Maintenance of RMS Channel R-16 72 72 72 72 1807 1808 1809 1810 1811 1812 1813 1814 1815 CP-215.3, Replacement of RIS Channel R-15 Detector CP-215.1, Calibration of Batemeter Drawer R-15 CP-215.0, Calibration and/or Maintenance of MS Channel R-15 CP-214.3, Replacement of Detector for R4S Channel R-14 CP-214.2, Calibration of R-14 Detector CP-214.1, Calibration of Ratemeter Drawer R-14 CP14.0, Calibration and/or Maintenance of %IS

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

P PCN 4 78 Procedure a Title Meetin I 78 1482 1476 1479 1478 1457 0-1.2, Plant From Hot Shutdown to Steady Load 0-2.1, Normal Shutdown to Hot Shutdown PT-6.1, Source Range Nuclear Instrumenta-tion System, Channels PZ-16, Auxiliary Feedwater System M-40.1, Hydraulic Snubber Removal and Re-installation Procedure 59 59.-

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

PCN I 78 Procedure a Title Meetin I 78 1468 1469 1470 1471 1474 M-51.2, D. C. Voltage Monitor Relays for Safeguard rains M-71.1, Bistable 431B for Pressure Controller PRV-431C Replacement M-72.1, Replacement Primary Zoo RPD p

EM-154, Steam Generator, Handhole Cover Gasket Leak Repair Using "Furmanite" Process M-43.1.1, Steam Generator Insert Removal Steam Generator 59 59 59 59 1472 1473 M-16.1, Service Water Discharge Header For Turbine Building Isolation M-43. 20A IIAI'team Generator Secondary Side Pressure Test 59 59 1065 A-2.1 Re Fuel

~

f Re ce iving, Inventory and Sh ipn t f en o

59 1497 Check PL'-31, Safeguard Pump Bearing Temperature 59 1490 HP-7.4 ments

, Calibration of Neutron Surve In t ey s ru-59 1352 1508 1509 1549 1562 1558 WC-3, Alkalinity Determination SC-l. 7F, Emergency Radiation bhnitoring Off-Site Survey Team N9F SC-1.7H, Emergency Radiation bbnitorin Off-Site Survey Team N9H A-50.12, Emergency Plan Training Program Inst A-60.3, Calibration Surveillance Program f trumentation/equipment of Safet Rel ed ram or y

at Components Fix PZ-13.1.0, Testing and/or Maintenan f th

'd Fire Detection and Extinguishiceo e

System 1ng 59 60 60 60 60 60

PCN I 78 Procedure 6 Title Meetin I 78 1563 1517 1570 1566 1610 6

1659 1576 1519 1520 1590 ET-13.1.9, Halon System Testing (Resetting)

Computer Room and Relay Room M-40. 6, Steam Generator Hydraulic Shock Suppressors Leakage Test and Inspection EC-.18. 2, Fluoride Determination PC-18.1, Chloride Determination RI-199, Sludge Removal from Waste Holdup Tank NC-7.2, Determination of Chloride ky Specific Ion Electrode WC-8, Amperometric Determination of Chlorine in Water WC-8.1, Chlorimetric Determination of Chlorine Water WC-10.0, Solution pH Determination ky Glass Electrode Method 60 60 60 60 61 62 62 62 62 1602 1605 1604 1603 1609 1610 ET-5.10, Process Instrumentation Reactor Protection Channel Trip Test (Channel 1)

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

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

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

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

EM-199, Sludge Removal from Waste Holdup Tank 62 62 62 62 1643 1654 1648 EM-158, Seal Welding MOV-721 RHR to "B" Loop M-12. 2, Inmdiate-Boration ET 113 Gaskets Replacement M-18.3, Waste Evaporator Inlet Check Valve 1769 Replacement 62 62 62

PCN 5 78 Procedure 6 Title Meetin 0 78 1649 1647 1645 M-37.1A, Repacking of Pressurizer Spray Valves 431A and 431B M-37.18G, Inspection and Repair of 1B Auxiliary Building Sump Tank Pump Discharge Check Valve M-37.18H, Containment Spray Pump Discharge Check Valve 862A and/or 2B Inspection and Maintenance 62 62 1644 1651 1650 1646 M-37.26.1, Testing and Repair of 1A Steam Generator Blowdown Sample Isolation Valves CV6 (5735)

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

M-37.47, RHR Pump Suction MOV-851A or MOV-851B Maintenance and Inspection M-37.48, Component Cooling from RC Pumps MOV-759A and/or MOV-759B Isolation and Maintenance 62 62 62 62 1652 1653 1594 1066 1591 1574 1575 1573 1598 M-37.49, Level Control Valve From "B" RCS Loop ZCV-427 Maintenance and Inspection M-37.50, MOV-721 RHR to "B" Loop Maintenance and Inspection PC-2, Gross Degassed Beta-Gamma Activity in Primary Coolant A-2.8, Special Nuclear Materia1 Inventoey and Record Requirements RD-8, Liquid Radwaste Compositing and Analysis PC-21, Hydrogen Peroxide Analysis PC-88 Reactor Coolant System Chemical Additions XC-10, Radioiodine Determination in Primary Coolant Unit T-10A Extraction RSSP.3, Air Supply for Integrated Leak Rate Test 62 62 62 62 62 62 62 62 62 PCN N 78 Procedure 6 Title Meetin N 78 1597 1592 1642 1513 1512 1608 1595 1607 1606 1572 1611 1577 1578 1596 1612 Hone None None None 1695 RSSP-7.3, Reactor Trip logic Relays Drop Out T>i&s PC-5, Gamma Isotopic Analysis of Degassed Primary Coolant RI-157, Repair of Piping Leak on the B. A.

Concentrates Holding Tank Pump Discharge KT-23.25, Containment Isolation Valve Leak Rate Testing Purge Supply Pl'-23.36, Containment Isolation Valve Leak Rate Testing Purge Exhaust HP-4.3, Work Permit Use HP-12.2, Medical Check, Fitting and Training of Personnel Using Respirators HP-12.5, Maintenance of Respirators M-53.1, Containment Air Lodges Gasket Re-placement 0.4.1, equilibrium Indicated Axial Flux Difference Determination 0-6.11, Routeine Operations Check List PC-18.3, Determination of Chloride by Specific Ion Electrode PI'-2.2, Residual Heat removal System A-l.l, Locked Radiation Areas A30.3, Plant Procedure Content and Format Requirements GS-1.2, Ginna Station Security Event Report (2) 8/12/78 and 8/18/78 A-54. 4, Duty Engineer Responsibilities 8/14/78 A-54.6, Health Physics Tour 8/148 0-6.7, Weekly Alarm Status Check 8/7/78 S-27.348A, Valve 348A, Isolation 62 62 62 62 62 62 62 62 62 62 62 62 62 62 62 65 PCN I 78 Procedure a Title Meet'in 5 78 1499 1699 1660 1661 1665 1698 1697 1696 1666 1690 PZ-13.1.10, Smoke Detector System Testing A-30.3, Plant Procedure Content and Format Retirements E-l.l, Safety injection System Actuation E-l.2, Loss of Coolant Accident E-16.1, High Activity Radiation Ronitoring System PZ 6.3.1, Power Range Nuclear Instrumentation

System, Channel 41 PT-6. 2, N.I.S. Intermediate Range Channels PZ-6.3. 2, Power Range Nuclear Instrumentation

.System Channel 42 M-ll.SB, Major bhchanical Inspection of the Auxiliary Feed Pumps RF-52, Inspection Procedure for Exxon Nuclear Fuel Assemblies at R.

E.

Ginna 66 66 66 1686 1691 1579 1580 1581 1978 1583 1584 SC-1.12B, Station Call List HP-12.6,

Issuance, Prayer Use and Return of Respirators

, ET-23.44, Containment Isolation Valve Leakrate Testing Leakage/Test Depressurization PT-23.45, Containment Isolation Valve Leakrate Testing Leakage Test/Instrumentation PT-23.48, ll Testing Deadweight Tester PT-23. 49, Containment Testing Construction Fire Service Water PT-23 50A ll ll ll ll Testing Containment Post Accident Air Sample (Clean Int.

Building)

PZ-23.50B, Containment Isolation Valve Leak rate Testing Containment Post Accident Air Sample (Controlled Int.

Building) 66 66 66 66 66 66 PCN I 78 Procedure 6 Title Meetin I 78 1585 1586 1587 1588 1514 1515 1516 1551 1552 1553 1554 1555 PT-23. 50C, II If II Testing Containnent Post Accident Air Salrple (Auxiliary Building)

PT-23 o 51A, If II I'I Testing "A" Hydrogen Recombiner (Pilot and Main)

PT-23. 51B, If tl If II Testing "B" Hydrogen Recombiner (Pilot and Main)

PZ 23 51CI If If II Testing "A" and "B" Hydrogen Recombiner Oxygen Makeup PT 23 34 tf If It Testing Depressurization at Power PZ-23.33, Testing Service Air ET-23. 32, Testing Instrument Air PZ-23.43, II n

If Testing Leakage Test Supply Header ET-23. 42, I'I II II Testing Leakage Test Depressurization PZ-23.40, Containment Isolation Valve Leakrate Testing Auxiliary Steam Supply and Condensate Return PZ-23.39, Containment Isolation Valve Leakrate Testing Demineralized Water PT-23.46, Containment Isolation Valve Leakrate Testing Nitrogen to Accumulators 66 66 66 66 66 66 66 66 1556 PT-23.22, Testing R.

C.

D.

T.

Discharge 1557 pg 23 23 If II II II Testing Sump "A" 66 1617 1618 PT-22, Containment PT-22. 1, Hquipnent Penetration Leakrate Testing Hatch Door Seal Leakrate Test 66 PCN O 78 Procedure a Title Meetin I 78 1619 1620 PZ-22.2, Personnel Hatch Door Seal Leakrate Test PZ-22.3, Persnel Hatch Between Door Volume Leakrate Test 66 1621

~22.4, shipment Hatch Between Door Volume Leakrate Test 66 1622 1623 1624 1625 PZ-'22.5, Personnel Hatch Canopy Leakrate Test PZ-22. 6, equipment Hatch PZ 22.7, Hcpipment Hatch 0-Ring PZ-22. 8t Mechanical Manifold "A" 66 66 66 1626 1627 1628

,1629 1630 1631 1632 ET-22. 9, ET-22.10, PZ-22.11, PZ-22.12, PT-22.13, PT-22.14, PT-22.15, II IIBtt II IICII II ItEII ft IIFII ll IIQII II IIHI'I II II1 tl If 66 66 66 66 1633 1634 1635 1636 PT-22.16, Mechanical Manifold "J" Leakrate Test

'Z-22.17, II tfKfl It II PZ-22.18 Electrical Manifold IX, Leakrate Test PT-22.19, II II Ngl It If 66 66 66 1637 PZ-22.20, Illl tl

'I 66 1638 1639 1640 1673 1672 PT-22. 21, Mechanical Manifold "L" Leakrate Test PZ22..22, Fuel Transfer Flange Leakrate Test PZ-23, Containment Isolation Valve Leakrate Testing M-73.3, Welding on Carbon Steel Piping or Components M-73.2, Welding on Stainless Steel Piping or Components 66 66 66 66

PCN 0 78 Procedure a Title Meetin I 78 1589 1593 1565 1569 1571 1550 1568 1712 1713 1671 1693 1694 1715 1670 1714 PC-15. 1, Solution pH Determination ~

Gl Electrode Method ion ass PC-7, Iine 131, equivalent Calculat'C9.

.0, Determination of Chromate NC-7.1, Fluoride Determination WC-9.1, Determination of Total Chromium in Water HP-l. 5.5, Dosimeter Discrepancy Evaluation RI 78-1458 nt

, Spe Fuel Pat Roughing Filter Frame 0

A-30.2, Plant Procedure Clas f

pproval and Distribution S-3.4F Bo

, Boron Recycle Process Shutdown SC-1.15, In ct'pe ion of Emergency Ekpipment PT-ll.l, Heat Trace ace Circuitry Functional Check PZ-ll. 60, Cell Battery Banks "A" and "B" imitations and Setpoints P-l, Precautions L'ac r Control and Protection System HP-12.4, Fitti'ng and Testing of Respirators Heat Exchanger Valve, HCV 625 66 66 67 67 67 67 1711 1709 1688 1786 1702 1703 GS-34.0, Vital Areas RF-S.O, Fuel Assembly and Core Co nent ment Prerequisites and Pre an Precautions GS-42.0, Site Designated Vehicles EM-2 1 '

Sp ice Covering Removal on the lD tainment Recirculation Fan e

Con-CP-80.0 Cal'eters ibratxon Procedure for Outs'd r

i e Micro-

'on Procedure for Micrometer CP-80.1, Calibration 67 67 67 69

PCN 5 78 Procedure a Title Meetin 4 78 1816 1817 1818 1819 1820 1821 1822 1823 1824 1825 1826 1827 1828 1829 1830 1831 1832 1833 CP-213.2, Calibration of R-13 Detector CP-213.1, Calibration of. Ratemeter Drawer R-13 CP-403.5, T Avg (3 Sec)

Lag Unit IN-403BB CP-403.4, T Avg Dana Amplifier PN03A CP-403.3, T Avg Dual Current Source TT-403 CP-403.2, Reinstate of T Avg Signal for Channel 3

CP-403.1, Defeat of T Avg Signal Channel 3

CP-402.9, T Avg Indicator TI-402 CP-402.8, T Avg Repeater

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

'IN-402C CP-402.5, T Avg (3 Sec)

Lag Unit 'IN-402BB CP-402.4, T Avg Dana Amplifier IN-402A-CP-402.3, T Avg Dual Current Source TT-402 CP-402.2, Reinstate T Avg Signal for Channel 2

CP-402.1, Defeat of T Avg Signal Channel 2

CP-401.8, T Avg Repeater IN-401W CP-401.7, T Avg Repeater

'IN-401C CP-401.6, T Avg Bistable TC-401A 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 1834 1835 CP-401. 5, CP-401.4, T Avg (3 Sec)

Lag Unit 'IN-401BB T Avg Dana Amplifier 'IN-401A 72 72 1836 1837 1838 1839 1844 1845 CP-401.3, T Avg Dual Current Source TZ-401 CP-401.1, Defeat of T Avg Signal Channel 1

CP-401.2, Reinstate T Avg Signal Channel 1

CP-221.2, Calibration of R-21 Detector CP-426.8, Pressurizer Level Indicator LI-426 CP-426.7, Pressurizer Level Repeater LN-426B 72 72 72 72 PCN I 78 Procedure 6 Title Meetin 4 78 1846 1847 1848 1849 1850 1851 CP-426.6, Pressurizer Level Repeater LM-426A CP-426.5,'ressurizer Level Bistable LC-426A/B CP-426.4, Pressurizer Level Power Supply LQ-426 CP-426.2, General Reinstate 426 Pressurizer Level CP-426.1, General Defeat Procedure 426 Pressurizer Level CP-426.0, Calibration and/or Maintenance of 426 Pressurizer Level Channel 72 72 72 72 72 72 1852 1853 1854 1855 1856 1857 1858 1859 1860 1861 1862 1863 1864 1865 CP-416.7, Reactor Coolant Flow Indicator FI416 CP-416.6, Reactor Coolant Flow Repeater FM-416 CP-416.5, Reactor Coolant Flow Bistable FC-416 CP-416.4, Reactor Coolant Flow Power Supply FQ-416 CP-416.2, General Reinstate Procedure of Reactor Coolant Flow Channel 416 CP-416.1, General Defeat Procedure of Reactor Coolant Flow Channel 416 CP-416.0, Calibration and/or Maintenance of Reactor Coolant Flow Channel 416 CP-415.7, Reactor Coolant FLow Indicator FI-415 CP-415.6, Reactor Coolant Flow Repeater B4-415 CP-415.5, Reactor Coolant Flow Bistable EC-415 CP-415.4, Reactor Coolant FLow Power Supply FQ15 CP-415. 2, General Reinstate Procedure for Reactor Coolant Flow Channel 415 CP-415.1, General Defeat Procedure of Reactor Coolant Flow Channel 415 CP-415.0, Calibration and/or Maintenance of Reactor Coolant Flow Channel 415 72 72 72 72 72 72 72 72 72 72 72 72 72 72 PCN N 78 Procedure a Title Meetin 5 78 1866 1867 CP-414.6, Reactor Coolant Flow Repeater Fill-414 CP-414.5 Reactor Coolant Bistable Flow FC-414 72 72 1868 1869 CP-414.4, Reactor Coolant Flow Power. Supply FQ14 CP-414.2, General Reinstate Procedure of Reactor Coolant Flow Channel 414 72 72 1870 1871 CP-414.1, General Defeat Procedure of Reactor Coolant Flow Channel 414 CP-414.0, Calibration and/or Maintenance of Reactor Coolant Flow Channel 414 72 72 1872 1873 1874 1875 1876 CP-413.7, Reactor Coolant Flow Indicator FI-413 CP-413. 6, Reactor Coolant Flow Repeater Fill-413 CP-413.5, Reactor Coolant Flow Bistable PC-413 CP-413.4, Reactor Coolant Flow Polar Supply FQ13 CP-413.2, General Reinstate Procedure Reactor Coolant FLow Channel 413 72 72 72 72 72 1877 CP-413. 1, General Defeat Procedure Reactor Coolant Flow Channel 413 72 1878 CP-413.0, Calibration and/or Maintenance of Reactor Coolant Flow Channel 413 72 1879 1880 1881 1882 1883 CP-412.7, Reactor Coolant FLow Indicator FI-412 CP-412.6, Reactor Coolant Flow Repeater EH-412 CP-412.5, Reactor Coolant Flow Bistable EC-412 CP-412.4, Reactor Coolant Flow Power Supply FQ-412 CP-412.2, General Reinstate Procedure Reactor Coolant Flow Channel 412 72 72 72 72 72 1884 1885 CP-412.1, General Defeat Procedure Reactor Coolant Flow Channel 412 CP-412.0, Calibration and/or Maintenance of Reactor Coolant Flow Channel 412 72 72 PCN 5 78 Procedure a Title Meetin N 78 1886 1887 1888 1889 1890 CP-411.7, Reactor Coolant Flow Indicator FI-411 CP-411. 6, Reactor Coolant Flow Repeater ETC-411 CP-411.5, Reactor Coolant Bistable EC-411 CP-411.4, Reactor Coolant Flow Power Supply FQ-411 CP-411. 2, General Reinstate Procedure of Reactor Coolant Flow Channel 411 72 72 72 72 72 1891 1892 1893 1894 1895 1896 1897 1898 1899 1900 1901 1902 1903 1904 1909 1910 1911 CP-411.1, General Defeat Procedure of Reactor Coolant Flow Channel 411 CP-411. 0, Calibration and/or Maintenance of Reactor Coolant Flow Channel 411 CP-406.10.1, Defeat of Dleta T Setpoint 1 Channel 2

CP-404.9, T Avg Indicator TI-404 CP-404.8, T Avg Repeater 1H-404W CP-404.7, T

Avg Repeater TM 404C CP-404.5, T Avg (3 Sec)

Lag Unit KM-404BB CP-404.4, T Avg Dana Amplifier 'IR-404A CP-404.3, T Avg Dual Current Source TZ-404 CP-404.2, Reinstate of T Avg Signal for Channel 4

CP-404.1, Defeat of T Avg Signal Channel 4

CP-403.8, T Avg Repeater

'BI-403W CP-403.7, T Avg Repeater XK-403C CP-403.6, T Avg Bistable XC-403A CP-463.7, Steam Generator Level Repeater LM-463B CP-463.6, Steam Generator Level Bistable LC-463E CP-463.5, Steam Generator Level Bistable LC-463C/D 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 PCN N 78 Procedure

& Title Meetin N 78 1912 1913 CP-463.4, Steam Generator Level Pomr Supply LQ63 CP-463.2, Reinstate of A Steam Generator Level Channel 463 72 72 1914 1915 1916 1917 1918 1919 1920 CP-463.1, Defeat of A Steam Generator Level

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

~462 CP-462.0, Calibration and/or Maintenance of Steam Generator Level Channel 462 72 72 72 72 72 72 72 1921

.1922 1923 1924 1925 1926 1927 1928 1929 1930 1931 1932 CP-461.8, Steam Generator Level Indicator LI-461

'P-461.7, Steam Generator Level Repeater ZZ-461B CP-461.6, Steam Generator Level Repeater LM-461 CP-461.5, Steam Generator Level Bistable LC-461A/B CP-461.4, Steam Generator Level Power Supply

,LQ-461 CP-461.0, Calibration and/or Maintenance of Steam Generator Level Channel 461 CP-449.11, Pressurizer Pressure Indicator PI-449B CP-449. 9, Pressurizer Pressure Repeater PM-449C CP-449.10, Pressurizer Pressure Indicator PI-449 CP-449.8, Prewsurizer Pressure Repeater EM-449A CP-449.6, Pressurizer Pressure Bistable PC-449A CP-449.5, Pressurizer Pressure Lead/Lag Unit PM49B 72 72 72 72 72 72 72 72 72 72 72 PCN N 78 Procedure a Title i

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

.1950 CP-430. 4, Pressurizer Pressure Power Supply PQ-430 72 1951 CP-430.2, General Reinstate Procedure 430 Pressurizer Pressure Channel 72 1952 CP-430.1, General Defeat Procedure 430 Pressurizer Pressure Channel 72 PCN N 78 Procedure

& Title Meetin 5 78 1953 CP-430.0, Calibration and/or Maintenance of 430 Pressurizer Pressure cannel 72 1954 1955 1956 1957 1958 CP-429.9, Pressurizer Pressure Bistable PC-429E CP-429.6, Pressurizer Pressure Bistable PC-429A CP-429.5, Pressurizer Pressure Lead/Lag PM-429B CP-429.4, Pressurizer Pressure Power Supply CP-429. 0 Caiibration and/or Maintenance of Pressurizer Pressure Channel 429 72 72 72 72 72 1959 CP-428.0, Calibration and/or Maintenance of Pressurizer 72 Pressure Channel 428 1960 1961 1962 1963 1964 1965 1966 1967 1968 1969 CP-427. 7, Pressurizer Level Indicator LI-427 CP-427. 6, Pressurizer Level Bistable LC-427A/C CP-427.5, Pressurizer Level Bistable LC-427A/C CP-427.4, Pressurizer Level Power Supply ZQ-427 CP-427.0, Calibration and/or Maitnenance of Pressurizer Level Channel 427 CP-427.1, Defeat of 427 Pressurizer Level CP-427.2, Reinstate 427 Pressurizer Level CP-428.1, Defeat of 428 Pressurizer Level CP-428.2, Reinstate 428 Pressurizer Level CP-429. 2, General Reinstate Procedure of Pressurizer Pressure Channel 429 72 72 72 72 72 72 72 72 72 72 1970 CP-429.1, General Defeat Procedure of Pressurizer Pressure Channel 429 72 1987 1988 1989 1990 CP-466.4, Feedwater Flow Power Supply FQ-466 CP-466.2, Reinstate of A Feedwater Flow Channel 466 CP-466.1, Defeat of A Feedwater Flow Channel 466 CP-466.0, Calibration and/or Maintenance of Feedwater Flow Channel 466 72 72 72 72 PCN 5 78 Procedure a Title Meetin N 78 1991 1992 1993 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 1982 1984 1985 1840 CP-465.11, Steam Flow Recorder FR-465 CP-465.10, Steam Flow Indicator FI-465 CP-465.9, Steam Flow Repeater PR-465D CP-465.8, Steam Flow Repeater ER-465C CP-465.7, Steam Flow Square Root Extractor PR-465B CP-465.6, Steam Flow Multiplier/Divider FM-465A CP-465.5, Steam Flow Bistable FC-465A CP-465.4, Steam Flow Power Supply FQ-465 CP-465.2, Reinstate of A Steam Flow Channel 465 CP-465.1, Defeat of A Steam Flow Channe; 465 CP-464. 9, Steam Flow Repeater FN-464D CP-464.8, Steam Flow Repeater EN-464C CP-464.7, Steam Flow Square Root Extractpr FM-464B CP-464. 5, Steam Flow Bistable FC-464A CP-464.4, Steam Flow Power Supply FQ-464

~ CP-464.2, Reinstate 'of A Steam Flow Channel 464 CP-464.1, Defeat of A Steam Flow Channel 464 CP-463.8, Steam Generator Level Indicator LI0463 CP-466.5, Feedwater Flow Square Root Extractor FM-466A PZ-28, Control Room Air Handling Unit Efficiency Test of HEPA and Charcoal Filter Banks in the Accident Axle PT-29.1, Auxiliary Building HEPA and Charcoal Filter Efficiency 'I@st ET-29.2, Controlled Access HEPA and Charcoal Filter Efficiency 'Ihst PC-7, Iodine 131 Calculation 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 72 PCN N 78 Procedure 6 Title Meetin N 78 1841 2011 1980 1843 PC-6, E Total Activity and Maximum Acitivity in the Primary Coolant RD-5, Ventilation System Releases P 9g Precautions, Limitations and Setpoints, P-9g Radiation Honitoring System A-54.5, Bulk Storage of Ccanbustible Materials and Their Use 72 72 72 72 1976 1842 1977 1981 FT-16, Auxiliary Feedwater System A-60.1, Ginna Station Technical Specification Surveillance Program M-67.1, Protomatic Deluge Valve System Maintenance System Numbers 7, 8, 9, 10 M-37.13, Inspection and Maintenance of A loop Accumulator Discahrge Check Valve V-842B 72 72 72 72 1986 A-54, Ginna Station Administrative and Enginering Staff 72 Responsibilities 1974 PT-18.3, 1C Instrument Air Gompressor Air Capacity Check 72 1975 1973 1972 1971 1994 1983 1908 1784

~18.2, 1B Instrument Air Gompressor Air Capacity Check PT-20.1, Control Air System Integrity for Steam Line Power Relief Valves PZ6, Containment Fan Recirculation Unit HEPA Filter Bank 'lbsting ISI-1.2.9, Quality Group A Inservice Inspection RSSP-2. 4, Containment Recirculation Fan Service Mater Flow Test XT-29, Containment Purge and Exhaust A and B Efficiency Xhst of HEPA and Charcoal Filter Banks A-50.12, Emergency Plan Training Program SM 75-34.24, Rework of Hanger SGB-19 S-12.2, Operator Action in the Event of Indication of Significant Increases in Leakage Items a-i 72 72 72 72 72 72 72 72 72 PC@ 4 78 Procedure

& Title Meetin N 78 2039 2040 2019 2014 2015 2016 2017 2018 2020 2038 A-20, Control Room Logs A-3, Containment Access SC-1.12C, Specialized Call List SC-l, Radiation Emergency Plan SC-l. 7E, Emergency Radiation monitoring On-Site Survey Team 59E SC-1.7G, Emergency Radiation monitoring On-Site Survey Team 59G SC-1.3B, Site Radiation Emergency (Emergency Coordinator and Survey Center Assignees)

SC-1.15, Inspection of Bnergency equipment SC-l. 11A, Immediate Re-entry CP-429. 2, General Reinstate Procedures of Pressurizer Pressure Channel 429 73 73 73 73 73 73 73 73 73 73 2024 CP-430.1, General Defeat Procedure 430 Pressurizer Pressure Channel 73 2026 2027 CP-429.1, General Defeat Procedure of Pressurizer Pressure Channel 429 CP-429.2, General Reinstate Procedure of Pressurizer Pressure Channel 429 73 73 2028 2029 CP-449.1, General Defeat Procedure for Pressurizer Pressure Channel 449 CP-449.2, General Reinstate Procedure for Pressurizer Pressure Channel 449 73 73 2030 2031 CP-431.1, General Defeat Procedure 431 Pressurizer Pressure Channel CP-431. 2, General Reinstate Procedure Pressurizer Channel 431 73 73 2043 2042 2044 HP-12.1, Usage of Respirators HP-12.4, Fitting and Testing of Respirators HP-12.2, Medical Check Fitting and Training of Personnel Using Respirators 73 73 73 PCN I 78 Procedure 6 Title Meetin 5 78 2041 2035 2037 2033 2013 2034 2032 2045 2073 HP-12.3, Selection of Respirators RD-7, Liquid Waste Release HP.1, Controlled Area Entry QC-1502, Non-Conformance Report E-6.1, Loss of Component Coolaing During Power Operation S-3.4P, Transferring Concentrates frcm Boric Acid Evaporator Tank to Waste Evaporator Feed Tank for Dnzraning PT-2. 3, Safeguard Valve Operation SN 75-10.28, Service Water Piping to Air Handling Units for Auxiliary Building Addition Remrk CP-467.0, Calibration and/or Maintenance of Feedwater Flow Channel 467 73 73 73 73 73 73 73 73 74 2072 2063 2064 CP-467.1, Defeat of A Feedwater Flow Channel CP-468.11 Defeat of A Steam Generator Pressure Channel 468 CP-468.0, Calibration and/or Maintenance of Steam Generator 468 74 74 74 2046 CP-471. 0, Calibration and/or Maintenance of Steam Generator Level Channel 471 74 2159 2152 2151 2138 2139 CP-471.1, Defeat of Steam Generator Level Channel 471 CP-472.0, Calibration and/or Maintenance of Steam Generator Level Channel 472 CP-472.1, Defeat of Steam Generator Level Channel 472 CP-473.0, Calibration and/or Maintenance of Steam Generator Level Channel 473 CP-473.1, Defeat of B Steam Generator Level Channel 473 74 74 74 74 74

PCN I 78 Procedure a Title Meetin I 78 2133 2124 2113 CP-474.1, Defeat of B Steam Flow Channel 474 CP-475.0, Calibration and/or Maintenance of Steam Flow Channel 475 CP-476.0, Calibration and/or Maintenance of B Feedwater Flow Channel 476 74 74 74 2112 CP-477.0, Calibration and/or Maintenance of Feedwater Flow Channel 477 2103 2123 CP-477.1, D feat of B Feedwater Flow Channel 4

CP-475.1, General Defeat Procedure Steam Flow Channel 475 74 74 2055 2091 2162 2161 2084 2168 2163 2164 2165 2077 2166 2086 2087 2088 2089 2167 CP-469.1, Defeat of A Steam Generator Pressure Channel 469 S-1BB Shutdown of Rx3 Drive Motor Generator Sets HP-12.6,

Issuance, Proper Use and Return of Respirators HP.3, Work Permit Use ISI-4.1.6, High Energy Inservice Inspection QC-1701, Quality Assurance Records E-1.2, Zass of Coolant Accident E-1.3, Steam Line Break Accident E-1. 4, Steam Generator Tube Rupture Accident SC-1.12B, Station Call List ET-6.1, Source Range Nuclear Instrumentation System PT-2.3, Safeguard Valve Operation PZ-2.4, Gold/Refueling MOV's Surveillance PZ-2.5, AOV's Quarterly Surveillance PZ-2.6, Gold/Refueling AOV's Surveillance ET-30, Containment Spray Nozzle Check of A & B Rings 74 74 74 74 74 74 74 74 74 74 74 74 74 74 74 PCN 5 78 Procedure

& Title Meetin N 78 2090 2048 PZ-16.1, Auxiliary Feedwater System Flow Balance EM-. 210, Auxiliary Building Main Crane Replacement of Driver Axle 74 74 2180 2160 2083 2190 2191 2192 RI-211, Replacing Splices and Splice Sleeves for Pressurizer Level and Pressure Channels S-3A, Startup of Rxl Drive Wtor Generator Sets EN-190, Repair of Auxiliary Feedwater

Hanger, FNH-39 M-40.4, Visual Leakage Inspection of High Energy Piping E-4.1, Safeguard Buses Low Voltage Condition E-9,

?leakage Into the Component Cooling Loop E-23.2, Malfunction of N2 Reactor Coolant Pump Seal 74 74 74 74 76 2193 E-23.3, Malfunction of N3 Reactor Coolant Pump Seal 2194 2195 2196 2197 2198 2188 2021 2187 2185 E-23.4, Zass of Reactor Coolant Pump Seal Injection Supply E-26.1, Erergency Shutdown Resulting from a Reactor Trip from 8.5% Power or Less E-26.2, Emergency Shutdown Resulting from a Reactor Trip When Between 50% and 8.5% Power E-31, Automatic Turbine Load Runback E-36, orator Actions to be Taken in the Event of Alarm Conditions on the Turbine Vibration Instruments M-40.6, Steam Generator Hydraulic Shock Suppressors Leakage Test and Inspection SC-1.12A, Immediate Call List S-15.3, Incore Wvable Detector Alignment A-54.3, Cpen Flame, Welding and Grinding Permit 76 76 76 76 76 76 76 76 PCN 4 78 Procedure a Title Meetin 5 78 2183 2189 2199 A-52.1, Shift Organization Relief and Turnover M-25, Adjustment Procedure for thermally Compensating Supports cn Main Steam Header Safety Valves and Power Operated Relief Valves O-l.l, Plant Heatup from Cold Shutdown to Hot Shutdown 76 76 2203 2170 2171 2172 2173 HP-10.3, Flow Rate Calibration of High Volume Air Samples GS-l.l, Security Cgerations Plan GS-7.0, Security Officer's Report GS-14.0, Security Guard Response to Trespassers GS-15.0, Security Guard Action if There is a Portal Monitor Alarm 76 76 2174 2175 2176 2177 2178 2179 2023 2217 1560 1498 2212 2216 GS-16.0, Property Removal GS-21.1, Site Access Control (Security) for Emergency Situations GS-21.1, Unoccupied Vital Area Access Control GS-24. 0, Security Surveillance Requirements and Procedures GS-28.0, Search of Personnel,

Vechiles, and Packages GS-21. 0, Door Alarm System A-50.9.3, Health Physics Technician Training and Responsibility Limits SC-1.12D, Management Call List XT-13. 5, Fire Spray System External Header/Nozzle Inspection PT-13.1.14, Fire Barrier Penetration Seals A-3, Containment Access RSSP-l. 1, Interlock Verification Residual Heat Removal System 76 76 76 76 76 76 76 77 78

,78 78 78 PCN I 78 Procedure

& Title Meetin I 78 2215 2220 ET-2.10.2, RHR System Core Deluge Check Valves A-17, Plant Operations Review Committee Operating Procedure 78 78 2219 2221 2182 2225 2233 2232 2231 2230 2229 S-4.1S, Lictuid Waste Process Operation and Shutdown S-4. 1E, Waste Condensate Releases PT-2.5.1, Air Operated Valve Quarterly Surveillance (Containment)

S-4.2.9, Nitrogen Backup Supply to Auxiliary Building S-2. 1A, Pre-Startup Lineup of Reactor Coolant Pump S-3. 3B, Hydrogen Concentration Control S-4.2.2, 1A Waste Gas Compressor Startup S-4.2.4, Gas Decay. Tank Opeations S-4.2.6, Isolating Reactor Coolant Drain Tank from Vent Header 78 78 78 79 79 79 79 79 79 2228

'224 2251 2252 2247 2235 2237 2241 2242 S-6, Nuclear Instrumentation System S-14, Area and Process Radiation Monitoring System

~ KT-23.37, Containment Isolation Valve Leakrate Testing Reactor Compartment Cooling Unit A PT-23.28, Containment Isolation Valve Leakrate Testing Reactor Compartment Cooling Unit B P-4, Precautions, Limitations and Setpoints Auxiliary Coolant System PZ-29.3, Auxiliary Building Ventilation Main HEPA Filter Bank 'lhsting RSSP-2. 2, Diesel Generator Load and Safeguard Sequence Test RSSP-2.1A, Safety Injection Functional Test Alignment RSSP-1. 3, Valve Interlock Verification Chemical Volume and Control System 79 79 79 79 79 79 79 79 79 PCN 5 78 Procedure s Title Meetin 5 78 2261 EM-190, Repair of Auxiliary Feedwater

Hanger, FNH-39 79 2262 2263 2264 2265 2269 2254 EM-206, Spl-ice Covering Removal on the 1D Containment Recirculation Fan EM-207, Replacing Splices and Splice Sleeves for Pressure Level and Pressure Channels EM-208, Containment Recirculation Fan Splices EM-209, MOV-852A and 952B Splices HP-8.4, RAdioactive Source Inventory S-15. 2, Flux Mapping Emergency and Calibration Procedure 79 79 79 79 79 79 2250 2255 2256 2257 2259 2260 2249 2248 2270 2271 2244 2245 2234 2236 PZ-31, Safeguard Pump Bearing Temperature Check PZ-2.1, Safety Injection System Pumps

~2. 2, Residual Heat Reaaval System PT-2.7, Service Water System PT-3, Containment Spray Pumps and NaOH Additive

.System PT-16, Auxiliary Feedwater System

. A-60.3, Calibration Surveillance Program for Instrumentatio@+uipnent of Safety Related Components M-45. 4, Safeguard Motors Inspection HP-12.6, Issuance Proper Use and Return of Respirators SM 75-7.25, HVAC Backfits Rework RF-2, Reactor Refueling.Outage Cgerations and Activities SC-1.12B, Station Call List A-54.6, Health Physics Tour ET 9, Undervoltage and Underfrequency Protection 11A and 11B 4160 Volt Buses 79 79 79 79 79 79 79 79 79 79 79 79 79 PCN I 78 Procedure

& Title Meetin I 78 2238 2239 2240 2243 2252 2267 RSSP-13.1, Hydro cn CVCS Class C Safety Related Piping, Part 1 RSSP-13.2, Hydro on CVCS Class C Sagety Belated Piping, Part 2

BSSP-14.1, Condenser Steam Dump Interlock Zoic Test RSSP-1. 2, Valve Interlock Verification Safety Injection System PT-13.1.1, Protomatic Deluge Valve System Testing System Numbers 7, 8, 9, 10 CP-70.6, West Pyrometer Calibration or Maintenance Serial No.

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

System, Channel 41 PZ-6.3.2, Power Range Nuclear Instrumentation

System, Channel 42 79 79 79 79 79 79 79 80 81 81 81 81 81

PCN I 78 Procedure

& Title Neetin I 78 2314 2313 2310 2309 2323 2266 2036 2324 2327 2328 2304 2331 PT.3. 3, Power Range Nuclear Instrumentation

System, Channel 43 PT.3.4, Power Range Nuceear Instrumentation

System, Channel 44 N-38.4, lA Constant Voltage Transformer Maintenance

'P-250.6, Calibration and/or Maintenance of Wind Speed Voltage Signal Conditioner PT-13.4.10, Protomatic Deluge Valve System Testing System 510A (412A Transformer)

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

KT-35, Welding Rod Oven 'Ihermmeters PZ-13.4.10A, Protomatic Deluge Valve System Testing System 10A (512A Transformer)

S-4.5.4, Boron Recycle Base Removal DI Resin Replacement S-4.5.5, Boron Recycle Cation DI Resin Replacement O-l.2. 2, Critical Rod Position Calculation SC-13.15.15, Emergency Fire shipment Locker Inventory and Inspection 81 81 81 81 81 81 81 81 81 81 81 2369 M-38. 9, Repair Battery Charger Maintenance and/or 82 2333 2326 2359 2316 2373 2329 2353 2354 A-20, Control Room Zags N-56.1, Placement of Ceramic Fiber Penetration Seals RD-2, Containment Purge Releases T-32C, Velocity Flush of the Fire Water System T-32C, Velocity Flush of the Fire Water System HP. 2, Self-Reading Dosimeter Use PC-22, Hydrazine Determination PC-15. 2, Specif ic Conductance 83 83 83 83 83

, 83 83 83 PCN 5 78 Procedure 6 Title Meetin 5 78 2357 2367 2360 2358 PC-13, Dissolved Oxygen Determination CP-250. 7, Calibration and/or Maintenance of Synchro to DC Converter A-l.1, Locked Radiation Areas K',-l.l, Primary Coolant Anaylsis Schedule and Limits 83 83 83 83 2347 2273 2273 2339 2342 2343 2344 2361 2345 M-37.38.1, Crosby Safety and Relief Valve Maintenance for Valve No.

A-30. 2, Plant Procedure Classif ication, Review, Approval and Distribution Requirements A-30.3, Plant Procedure Content and Format Requirements RD-6, Gas Decay Tank Releases CP-424.1, Calibration and/or Maintenance of Pressurizer Liquid Temperature +I Converter CP-425. 3, Calibration and/or Maintenance of Pressurizer Vapor Temperature Indicator TI-425 CP-425.1, Calibration and/or Maintenance of Pressurizer Vapor Temperature +I Concerter PC-16, Solids Determination ZN-211, Replacing Splices and Splice Sleeves for Pressurizer Level and Pressure Channels 83 83 83 83 83 83 83 83 83 2346 2335 2236 2330 2372 2305 ZM-212, Review of B. A. Recycle Cation DI Backwash Drain Valve 1163 QCIP-21, Shipping Package LL-50-100 Inspection QCIP-22, Shipping Package HN-100 Series 1

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

&I 75-5.43, Final Reowrk for Standby Auxiliary Feedwater A-30.3, Plant Procedure Content and Format Requirements 83 83 83 83 83 84 PCN I 78 Procedure a Title Meetin I 78 2463 2456 2457 2458 2459 2451 2452 2453 2454 2375 2383 2382 2381 2378 2379 2380 2377 2376 2386 2394 SM 75-5.38, Standby Auxiliary Feedwater System Operational Testing CP-103. 0, Calibration and/or Maintenance of Boric Acid Temperature Controller TIC-103 CP-104.0, Calibration and/or Maitenance of Boric Acid Tank ~rature Indicator TI-104 CP-105.0, Calibration and/or Maintenance of Boric Acid Tank lhmgerature Indicator TI-105 CP-107.0, Calibration and/or Maintenance of Boric Acid Tank ~rature Controller TCI-107 S-4.4.1, Spent Resin Package Site Receipt and Shigrent RD-10, Shipping Radioactive Material A-50.10, Operator Incident Review 0-2.1, Normal Shutdown to Hot Shutdown RD-S, Waste Water Composite Calculations HP-4.1, Controlled Area Entry A-3, Containment Access Pl.3.1, Power Range Instrumentation System Channel 41 ET.3. 2, Power Range Instrumentation System Channel 42 PT-6.3.3, Power Range Instrumentation System Channel 43 PX 6.3. 4 Power Range Instrumentation System Channel 44 RF-8.1, Step by Step Fuel Loading and Maps SC-1.12B, Station Call List CP-934. 1, Accumulator Level Transmitter LT-934 CP-920.1, Placing of Refueling Water Storage Tank Level Channel 920 Out of Service 84 84 84 84 84 84 84 84 84 84 84 84 84 84 84 84 84 84 PCN N 78 Procedure 6 Title Meetin N 78 2413 2434 2441 2448 2348 2322 2341 2364 2362 2351 2355 2356 2363 CP-485.1, Defeat of Turbine First Stage Pressure Channel 485 CP-482.1, Defeat of A Steam Generator Pressure Channel 482 CP-479.1, Defeat of B Steam Gnerator Pressure Channel 479 CP-478.1, Defeat of B Steam Generator Pressure Channel 478 HP-7.7, Calibration of Beta Survey Instruments M-43.16.1, Steam Generator Tube Sheet Photo-Mapping PC-1.4, Operation of Gamma Analyser WC-3. 1, Sodium Sulfate Determination WC-3. 2, Solids Determination WC-3. 3, Hardness Determination WC-10.1, Specif ic Conductance WC-12.0, Dissolved Oxygen Determination WC 12 1 g Dissolved Oxygen Determination AZIDE Method 84 84 84 84 84 84 84 84 84 84 84 84 84 2352 2350 2365 2366 2349 2384 2385 2387 W-13.0, Hydrazine Determination NC-13.1, Free Hydroxide Determination WC-13. 2, Silica Determination WC-13. 3, Phosphate Determination WC-14.0, Oil and Grease Determination QC-801, PDR Control of Accepted Materials, Parts 85 and Components CP-934.3, Accumulator Level~ Indicator LI-934 CP-934.2, Accumulator Level Bistable LC-934 CP-920.7, Hefueling Water Storage Tank Level Indicator LI-920 84 84 84 84 84 86 86

,I a.

J PCN I 78 Procedure

& Title Meetin

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

OTHER CHANGES, TESTS AND EXPERIMENTS PCN 0 78 Procedure

& Title Meetin N 78 2408 CP-486.6.6, Turbine First Sl'age Pressure I

'nit PM-486B

.,~se 2409 2411 CP-486.5 PC-486~C

.5, TUrbine First Stage Pressure B'abl is e

CP-486.4.4, Turbine First Stage Pressure Power Supply PQ-486 86 2412 2414 2415 CP-485.9, PI-485 CP-485.8, CP-485.7, PM-485A Turbine First Stage Pressure Indicator Turbine First Stage Pressure Repeater PM-485B Turbine First Stage Pressure Re t

pea er 86 2416 PC-485C CP-485.6, Turbine First Stage Pressure B'abl is e

86 2417 2418 2419 2420 2421 2422 CP-485.5 PC-48~, Turbine First Stage Pressure B'abl is e

CP-485.4, Turbine First Stage Pressure Power Supply PQ-485 CP-483.9, Steam Generator Pressure Indicator PI-483 and PI-483B CP-4 PM-483C 83.8, Steam Generator Pressure Re t

pea er

~ CP-483..7, Steam Generator Pressure Repe t PM-483B pea er CP-483. 6 S

.PC-483A

, Steam Generator Pressure Bistabl PC8 e

3A 86 86 86 86 86 2423 CP-483.5, Steam Generator Pressure Lead~~"

Unit PM-483A a g~g 86 2424 2425 2426 CP-483.4, Steam Generator Pressure Power Supply PQ-483 Channel 483 CP-483.2, Reinstate of B Steam Generator Pr or essure CP-482. 9, Steam Generator Pressure Indicator PI-482A and Remote PI-4828 86 86 PCN 5 78 Procedure 6 Title Meetin I 78 2427 CP-478.8, Steam Generator Pressure Repeater PM-478C 86 2428 CP-483.1, Defeat of B Steam Generator Pressure Channel 483 86 2429 CP-482.7, Steam Cinerator Pressure Repeater PM-482B 86 2430 CP-482. 6, Steam Generator Pressure Bistable PC-482A 86 2431 CP-482.5, Steam Generator Pressure Lead/Lag Unit PM-482A 2432 2433 CP-482.4, Steam Generator Pressure Power Supply PQ-482 CP-482.3, Steam Generator Pressure Transmitter PT-482 86 86 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 PC-479A 86 2438 CP-479. 5, Steam Generator Pressure Lead/Lag Unit PM-479A 86 2439 2440 CP-479.4, Steam Generator Pressure Power Supply FQ-479 CP-479.2, Reinstate of B Steam Generator Pressure Channel 479 86 2442 CP-478.10, Steam Generator Pressure Indicator PI-478 86 2443 CP-478.8, Steam Generator Pressure Repeater Pi<1-478C 86 2444 2446 CP-478.7, Steam Generator Pressure Repeater PM-478B CP-478.6, Steam Generator Pressure Bistable PC-478A 86 86

-100-PCN I 78 2447 Procedure

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

(~

-101-PCN 5 78 Procedure a Title Meetin N 78 2461 2462 M-43.0, Steam Generator Maintenance Test and Repair Procedures M-43.16, Steam Generator Explosive Tube Plugging Steam Generator 86 86 2467 2483 2484 2371 2085 2334 2471 2307 2492 2493 2494 2496 2495 2497 2486 2487 HP-7.5, Pocket Dosimeter/Accuracy and Leak T st XT-13. 5, Fire Spray System External Header/h7ozzle Inspection ET-2.9. 2, Accumulator Discharge Check Valves Quarterly Exercising SC-3.3.3, Fire Brigade Recall List SC-3.15.6, Fire Hose Reel Assembly Inspection S-12.4, RCS Leakage Surveillance Record Instructions S-12. 4, RCS Leakage Surveillance Record Instructions

~13.1.9, Halon System Testing (Resetting)

Computer Room and Relay Bxxn SC-3.3.1, Immediate Fire Notification SC-3. 15. 2, Fire Protection shipment Impairment SC-3.16. 6, Operating Instructions Fusible Link Sprinkler System SC-3.16.7, Operating Instructions, Automatic Deluge System SC-3.16. 8, Operating Instructions, Manual Deluge Systems SC-3.16. 9, Operating Instructions, Halon 1301 Systems PP-20.1, Control Air System Integrity for Steam Line Pawer Relief Valve PZ-5.10, Process Instrumentation Reactor Protection Channel Trip Test (Channel 1) 86 86 86 86 87 87 87 87 87 87 87 87 87 87

-102-PCN I 78 Procedure

& Title Meetin I 78 2488 2489 2490 2472 2479 2538 2537 2543 2512 2525 2526 2527 2517 2518 2519 2520 2521 2499 2540 ET-5. 20, Process Instrumentation Reactor Protection Channel Trip Test (Channel 2)

FZ-5. 30, Process Instrumentation Reactor Protection Channel Trip Test (Channel 3)

ZT-5. 40, Process Instrumentation Reactor Protection Channel Trip Vest (Channel 4)

PT-13.7, Fire Hose Reel Assembly Inspection A-30.3, Plant Procedure Content and Format Retirements HP-l. 1, Issuing Personnel Dosimeters HP-l. 3, External Exposure Records HP-2.2, Whole Body Counter Operation HP-11.4, High Volume Air Sampling AR/Fl, High Condenser Pressure or Loss of Both Recirculating Water Pumps AR/H, High Condenser Pressure AR/K-17, Zaw Vacuum Trip PT-23.17A, Containment Isolation Valve Leak Rate Testing Containment Pressure Sensing

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

, Rate Testing Safety. Injection System PT3.21, Containment Isolation Leak Rate Testing RCDZ to Gas Anaylser S-27. 365A, V-365A Isolation 0-6, Cperation and Process Nonitoring 87 87 87 87 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88

-103-PCN 5 78 Procedure a Title Meetin I 78 2513 2500 2501 2514 2544 2522 2531 2532 2533 2524 2535 2536 2542 2523 2535

'2515 RD-1.3, Tritium in Containment Air Sampling

. and Analysis RD-3, Plant Vent Iodine and Particulate Releases Sampling and Anylysis RD-6, Gas Decay 'ink Releases RD-12, Tritium in Air Sampling and Analysis GS-8.0, Detex Tours ky Security Guards CP-134.0, Zetdown Line Flaw Iaop 134 Calibration and/or Maintenance CP-501.1, Voltmeter Calibration for 480V Circuit Bus 513 CP-S01.2, Voltmeter Calibration for 480V Circuit Bus 315 CP-501.3, Voltmeter Calibration for 480V Circuit Bus 114 (Safeguard)

CP-501.4, Voltmeter Calibration for 480V Circuit Bus 117 CP-501.5, Voltmeter Calibration for 480V Circuit Bus 116 Safeguard Device NN CP-501.6, Voltmeter Calibration for 480V Circuit Bus 118 (Safeguard)

CP-2030.0, 1B Mtor Driven Auxiliary Feedwater Pump Discharge Pressure Loop 2030 PC-13, Dissolved Oxygen Determination PC-1.4, Cperation of Gamma Analyzer PC-l.l, Analysis Schedule and Limits, Primary Coolant 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 2473 6 2455 A-l, Radiation Control Manual 88 2528 2529 T-6.1, Regeneration of the Condensate Polishing Mixed Bed Demineralizer Unit T-6.2, Air Bump and Rinse Cleaning of the Condensate Polishing Mixed Bed Demineralizer Units 88 88

-104-PCN 4 78 Procedure a Title Meetin O 78 2516 2503 2504 2505 2506 2475 2476 2477 2482 2637 2636 2633 2632 2629 2628 2627 2626 T-6.1, Regeneration of the Condensate Polishing Mixed Bed Demineralizer Unit PV-6.3. 1, Power Range Nuclear Instrumentation

System, Channel 41 PZ-6.3. 2, Power Range Nuclear Instrumentation

System, Channel 42 PZ 6.3.3, Power Range Nuclear Instrumentation

System, Channel 43 PZ-6.3. 4, Power Range Nuclear Instrumentation

System, Channel 44 PT-13.4.12, Alarm Valve System Testing Fire System 512, Turbine Island Sprinkler PZ-13.4.13, Alarm Valve System Testing Fire System f13 Service Building Sprinkler PZ-13.4.15, Alarm Valve System Testing, Fire System 515 Warehouse Rl 74-28.1, Installation of i~cup Lines to Condensate Storage Tanks CP-2093.3, Atmospheric Relief Valve 1B (CV-57) Control Pressure Switch 2093 CP-2093. 2, General Reinstate Procedure 2093 Ahnospheric Relief Valve 1B (CV-57) Control CP-2092.3, Atmosheric Relief Valve 1A (CV-56)

Control Pressure Switch 2092 CP-2092.2, General Reinstate 2092 Atmospheric Relief Valve 1A (CV-56) Control CP-950.7, Containment Pressure Indicator PI-950 CP-950.6, Containment Pressure Repeater PM-950 CP-950. 5, Containment Pressure Bistable PC-950k/8 CP-950.4, Containment Pressure Power Supply PQ-950 88 88 88 88 88 88 88 88 88 90 90 90 90 90 90 90 90

-105-PCN N 78 Procedure a Title Meetin g 78 2625 CP-950. 3, Containment Pressure Transmitter PT-950 90 2624 2621 2620 2619 2618 2617 2616 2613 2612 2611 2610 2609 2608 2605 2604 CP-950. 22 Reinstate of B-3 Containment Pressure Channel 950 CP-949. 7, Containment Pressure Indicator PI-949 CP-949. 6, Containment Pressure Repeater PM-949 CP-949. 5, Containment Pressure Bistable PC-949A/8 CP-949. 4, Containment Pressure Power Supply PQ-949 CP-949.3, Containment Pressure Transmitter PT-949 CP-949. 2, Reinstate of B-1 Containemnt Pressure Channel 949 CP-948.7, Containment Pressure Indicator PI-948 CP-948.6, Containment Pressure Repeater PM-948 CP-948. 5, Containment Pressure Bistable PC-94~

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

-106-PCN I 78 Procedure 6 Title Meetin I 78 2603 2602 2601 2600 CP-947.5, Gontainment Pressure Bistable PC-947~

CP-947. 4, Containment Pressure Power Supply PQ-947 CP-947. 3, Containment Pressure Transmitter PT-947 CP-947.2, Reinstate A-3 Containemnt Pressure Channel 947 90 90 90 90 2597 CP-946. 7, Containment Pressure Indicator PI-946 90 2596 2595 2594 2593 2592 2589 2588 2587 2586 2585 2584 2635 CP-946. 6, Containment Pressure Repeater PM-946 CP-946. 5, Gontainment Pressure Bistable PC-946A/8 CP-946.4, Containment Pressure Power Supply PQ-946 CP-946. 3, Containment Pressure Transmitter

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

-107-PCN N 78 Procedure

& Title Meetin N 78 2631 2623 2615 2607 CP-2092.1, General Defeat Procedure 2092

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

'579 2578 CP-941.3, Accumulator Pressure Bistable PC-94~

CP-941.2, Accumulator Pressure Power Supply PQ-941 CP-941. 1, Accumulator Pressure Transmitter PT-941 90 90 90 2576 CP-940. 4, Accumulator Pressure ~

Indicator PI-940 90 2575 2574 CP-940.3, PC-940~

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

1

-108-PCN N 78 Procedure a Title Meetin N 78 2571 CP-939. 3, Accumulator Level Indicator LI-939 90 2570 2569 CP-939. 2, Accumulaotr Level Bistable LC-939A/8 CP-939.1, Accumulator Level Transmitter LT-939 90 90 2567 CP-938. 3, Accumulator Level Indicator LI-938 90 2566 2565 CP-938. 2, Accumulator Level Bistable LC-938A/B CP-938. 1, Accumulator Level Transmitter LT-938 90 90 2563 CP-937. 4, Accumulator Pressure Indicator PI-937 90 2562 2561 2560 CP-937.3, Accumulator Pressure Bistable PC-937~

CP-937. 2, Accumulator Pressure Power Supply PQ-937 CP-937.1, Accumulator Pressure Transmitter PT-937 90 90 90 2558 CP-936.4, Zoop A Accumulator Pressure Local Indicator 90 2557 2556 2555 2553 2552 2551 CP-936. 3, Accumulator Pressure Channel Bistable PC-936Ajh CP-936.2, Accumulator Pressure Power Supply PQ-936 CP-936.1, Accumulator Pressure Transmitter PT-936 CP-935.3, Accumulator Level Indicator LI35 CP-935. 2, Accumulator Level Bistable LC-935~

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

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

-110-PCN 4 78 Procedure a Title Meetin 4 78 2545 2548 2641 2644 2645 2643 S-26.1, Gomputer Program Check M-38.9, 1B1 Battery Charger Maintenance or Repair PT-5. 40, Process Instrumentation Reactor Protection Channel Trip Test (Channel 4)

RD-2, Containment Purge Release HP-10.1, Quality Control of Counting Systems HP-10.6, Calibration of the Liquid Scintillation Counter 90 90 90 90 90 90 2649 2549 2647 2640 2654 2655 2530 2507 2511 2508 2510 2509 2638 HP-7.4, Calibration of Neutron Survey Instruments HP-1.2, External Exposure Limits A-19, Changes in Written Procedures M-51.3, Non-Controlling Relay Replacement for K',39X T-14A, Feedwater Heaters Valve Alignment T-5A, Condensate System Lineup, Charging and Venting T-6.9, Condensate Polishing Mixed Bed Demineralizer Units:

Bed Startup Operation and Bed Removal frcm Service Operation CP-209.5, Calibration and/or Maintenance of RMS Ratemeter for Channels R-8, R, and R-23 through R-28 CP-222.0, Calibration and/or Maintenance of RMS Channel CP-222.1, Calibration of Ratemeter Drawer R-22 CP-222.2, Calibration of R-22 Detector CP-222.3, Replacement of Detector for R4S Channel R-22 SM 78-1657.1, Installation of 42" Duct for Control Room Ventilation 90 90 90 90 90 90 90 90 90 90 90 90 90

PCN 5 78 f

Procedure a Title Meetin N 78 2671 M-ll.4.10, Charging Pump Gear Reducer Inspection 91 2704 PZ-2. 5, Air Operated Valves, Quarterly Surveillance 93 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.

/I I

/

-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 modification.

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 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 76-26.2 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 System Modification SM 77-1474.1, RCP Seal Bypass Modification.

This procedure involved relocating the 41 Seal ~s piping and necessary hangers on the Reactor Coolant 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 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 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.

-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 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 76-01.2 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 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.

fr

-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.

Cf

-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 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.

l

)

I I

I

-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 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.

-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 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 75-5.43 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.

ML17244A797

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