View source for L-84-224, Rept of Changes,Tests & Experiments Made W/O Prior Commission Approval,Jul 1983 - June 1984

{{Adams
| number = ML20125A968
| issue date = 06/30/1984
| title = Rept of Changes,Tests & Experiments Made W/O Prior Commission Approval,Jul 1983 - June 1984
| author name = Williams J
| author affiliation = FLORIDA POWER &amp; LIGHT CO.
| addressee name = Oreilly J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000000, 05000250, 05000251
| license number = 
| contact person = 
| case reference number = FOIA-84-832
| document report number = L-84-224, NUDOCS 8506110263
| package number = ML20125A906
| document type = ANNUAL OPERATING REPORT, TEXT-SAFETY REPORT
| page count = 320
}}

=Text=
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TURKEY POINT PLAN UNITS 3 AND 4 DOCKET NUMBERS 50-250 AND 50-251 CHANGES, TESTS, AND EXPERIMENTS MADE WITHOUT PRIOR COMMISSION APPROVAL FOR PERIOD JULY I,1983 THROUGH JUNE 30,1984 IN COMPLIANCE WITH TITLE 10, SECTION 50.59 (b)
CODE OF FEDERAL REGULATIONS 8506110263 041220 EDRO   832        PDR T20:2

INTRODUCTION This report is submitted in accordance with 10 CFR 50.59 (b), which requires that reports of:
i) changes in the facility as described in the FSAR ii) changes in the procedures as described in the FSAR, and iii) tests and experiments not described in the FSAR which are conducted without prior commission approval be reported to the Commission at least annually.      This report is intended to meet this requirement for the period July 1,1983 through June 30,1984.
This report is divided into three sections; the first, Plant Change / Modifications, covering changes in the facility as described in the FSAR; the second, Procedure Changes- covering changes in the procedures as described in the FSAR; and the third, Tests and Experiments, covering tests and e periments not described in the FSAR.
T20:2 L

TITLE 10, SECTION 50.59 CFR REPORT
  .                                  (i) COMPLETED PCM LIST 3ULY 1,1983 THROUGH 3UNE 30,1984 UNITS COMPLETED PCM NO.                        PCM TTTLE DESCRIPTION                       THIS PERIOD 77-45B     Demineralizer Water Storage Tank Foundation and Retaining Wall    3 and 4 77-54G     Containment Modification for Steam Generator Repair                  4 77-54H     Containment Modification for Steam Generator Repair    .             4 77-54I     Containment Modification for S/G Repair (Electric)                   4 77-543     Containment Modification for S/G Repair Control System               4 73-31      Nuclear Maintenance Building                                      3 and 4 73-76      Breathing Air System                                                 4 73-34      Feedwater Recire System                                              4 73-104     Auxiliary Feedwater Pump Lube Oil Cociers                         3 and a 73-107     Steam Line Warm-up                                                   4 73 40A     Steam Generator Wet Lay-up System                                    4 73-82B     Condensate Polishing Demineralizer System                            4 79-14      Steam Generator Vent Valve Replacement                               4 79-27      Flow Transmitter (FI-1007)                                        3 and 4 79-34      Addition Steam Generator Alternate Feedwater Level Control           4 79 46      ThermalInsulation for Boric Acid System                              3 79 47      Thermal Insulation for Boric Acid System                             4 79-52      A.R.M.S. Enhancement                                                 3 79-33      Containment. Ramp Modification and S/G Haul Route                    2 79-114     Add RCS Venting                                                      3 79-127     RCP Seal Return Line Suppiy Modification                             4
     '9 - 133 C Add Containment Hydrogen Monitors                                    a 30-23      Post Accident Sampiing System                                     3 and 2 30-25      Add.Co6tainment High Range Radiation Monitors                        3 30-26      Containment High Range Radiation Monitoring                          3 30-35      Auxiliary Feedwater Line Support                                     3 30-33. RCS Venting System                                                   3 30-39      RCS Venting System                                                   4 30 40      Steam Generator Storage Compound                                  3 and a 30 43      Addition Steam Generator Access Platform                             4
                                                  -t-

TITLE 10, SECTION 50,59 CFR REPORT
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COMPLETED PCM LIST JULY 1,1983 THROUGH 3UNE 30,1984 UNITS COMPLETED PCM NO.                       PCM TITLE DESCRIPTION                  THIS PERIOD 30-51    Modify Containment Penetration Isolation System                  3 30-52    Modification of, Containment Penetration Isolation System        4 30-56    Uograde AFW Flow Control and Initiation                          4 30-57    Main Steam Line Support Modification                          3 and 4 30-62    Gas Stripper Bottoms Pumo Replacement                         3 and 4 30-64    P. A.S.S. Shielding Modification                                 4 30 72    Modification to Lo-HSI per IEB 79-14                             3 30-30    RCS Isolation Check Valve Testing                                3 30-95    Emergency Containment Filter Modification                        3 30-96    Emergency Containment Filter Modification                        4 30-115   Replace Feedwater Lines Snubbers                                 3 30-122   Condensate Storage Tank Piping and Structural Modification       4 30-12h   MHSI Refueling Isolation Valve                                   3 30-126   Steam Flow Transmitter Modification                              3 30-136   Containment Spray System Modification (I.C.)                     4 30-143   'Vaste Evaporator Package Removal                             3 and 4 30-144   Modify Feedwater Line at Steam Generator 'C'                     3 30-149   Containment Air Samole System                                    3 30-154   Feedwater Warm-up Line Modification                              3 30-155   Feedwater Warm-uo Line Modification                              4 30-170   NIS Cable Replacement                                            4 Addition Mechanical Stoos for Purge Valves                       2 31-07 31-03    Replace Pressurizer Level Transmitter                            3 31-10    Modify Feedwater Line at Steam Generator 'C'                     4 31-11    PRT Drain Modification                                           3 31-17    4160 Volt Switchgear Conc. Repair                             3 and a 31-20    Access and Dress Facility Potable                             3 and a 31-24    Add Fire. Detector 3B and 4B to 4160 volt                     3 and 4 31-29     Pressurizer Heater '<ey Lock Switch                             3 PZR Heater '<eylock Switch                                       2 31-30 Th:2

I 1
TITLE 10, SECTION 50,59 CFR REPORT COMPLETED PCM LIST JULY 1,1983 THROUGH JUNE 30,1984 UNITS COMPLETED PCM NO.                      PCM TITLE DESCRIPTION             THIS PERIOD 31 45  Dry Storage Tarehouse Firewater Service Air Sucoly        3 and 4 31-56  Hagan Power Sucoly Test Point                                3 31 71  Reactor Cavity and Transfer Canal Liner                   3 and 4
                                                         ~
31 73  (CPWO) Service Air Check Valve //205                      3 and 4 31 77  Addition 430 Volt Power for Temoorary Trailers               3 31-31  W-2 Switch Replacement                                       3 31-32  W-2 Switch Replacement                                       4 31-37  RAB Scaffolding Racks                                     3 and 4 31-92  Emergency Diesel Generator Louvers                        3 and 4 31-93  Add New Trays and Raceways in Cable Soreading Room        3 and 4 31 94  New Fuel Storage Rack Handrails                              3 31-95  New Fuel Storage Rack Handrails                              4 31-93  Charcoal Filter ' thermocouple                               3 31-99  Charcoal Filter Thermocouole Replacement                     4 31-103 Containment Evacuation Alarm Niodification                   3 31-140 Install new Reactor Head 0-Ring Clios                        4 31-147 Install Qualified Conn. Solenoid Valves                      3 31-150 Personnel Door Inter. -\nnunciator                           3 31-152 HHSI Pumo Recirc Lines                                       3 31-153 HHSI Pumo Recirc Lines                                       4 31-169 Remove PZR Instrument Heater Cubicles                        3 32-02  Nitrogen Back-uo for Steam Dumo to -\tmosohere Valve         4 32-05  Modification to CVCS (O.C.) per IEB 79-14                    3 32-03  Modification to SI and RHR (O.C.) per IEB 79 14              3 32-21  Modification to Containment Spray (I.C.) per IEB 79-14       3 l    32-22  Modification to CCW per IEB 79-14                            3 32-26  Modification to CVCS (I.C.) per IEB 79-14                    3 32-37  Modification to Main Steam to Relief Valve                   3 32-33  Modification to 'iain Feedwater (I.C.) per IEB 79-14         3 i    32-39  Modification to CVCS (O.C.) cer IEB 79-14                    3 5:?                                       _ _.                             ._

TITLE 10, SECTION 50,59 CFR REPORT COMPLETED PCM LIST JULY 1,1983 THROUGH 3UNE 30,1984 UNITS COMPLETED PCM NO.                      PCM TITLE DESCRIPTION                         THIS PERIOD 32 44   Modification to SI and RHR (I.C.) Der IEB 79-14                         3 32-52   Manipulator Crane Modification                                          3 32 56   Modification to CCW (I.C.) per IEB 79-14                                3 32 71   Modification to CVCS (I.C.) per IEB 79-14                               3 32 72   Modification to RCS (I.C.) per IEB 79-14                                3 32-73   Modification to Auxiliary Coolant System per IES 79-14                  3 32 74   Modification to Olesel Oil and Cond. Recovery System per IEB 79-14      3 32-75   Modification to CCW (I.C.) per IEB 79-14                           ,
4 32-73   Modification.to Primary Water (O.C.) per IEB 79-14                   3 and 4 32 79   Modification to Taste Disoosal(I.C.) oer IEB 79-14                      3 32-30   Modification to Waste Disposal (O.C.) per IEB 79-14                     3 32-31   Modification to CCW System (O.C.) per IEB 79-14                         3 32-32   Modification to SI and RHR (O.C.) per IEB 79-14                         3 32-91   Modification to CCW System (O.C.) per IEB 79-14                      3 and 4 32 92   Modification to CCW (O.C.) per IEB 79-14                                3 32 93   Modification to CCW (O.C.) per IEB 79-14                                3 32-94   Modification to CCW (I.C.) per IEB 79-14                                3 32-99   Auxiliary Power Vograde, Add 125V - 120 V Equioment                  3 and a 32-102  Lube Oil Storage Tank Relocate                                       3 and 4 32-104  Modify Main Steam System (O.C.) cer IEB 79-14                           3 32-105  Modification to CCW (O.C.) oer IEB 79-14                                3 32-106. RWST Addition Subsurface Site                                        3 and 4 32-109  Modification to CCW (O.C.) per IEB 79-14                                3 32-110  Modification to CCW (O.C.) per IEB 79-14                                3 32-111  Modification to SI and RHR per IEB 79-14                                3
  ~ 32-112 Modification to CCW System (O.C.) per IEB 79-14                         3 32-113  Modification to CCT System (O.C.) per IEB 79-14          .              3 32-115  Modificanon to CCW (O.C.) per IEB 79-14                                 3 32-116  Modification to CCT System (O.C.) per IEB 79-14                         3 32-119  Modification to CVCS (O.C.) oer IEB 79-14                               3 4.
T4:2

TITLE 10, SECTION 50,59 CFR REPORT COMPLETED PCM LIST JULY 1,1983 THROUGH JUNE 30,1984 UNITS COMPLETED PCM NO.                       PCM TITLE DESCRIPTION                     THIS PERIOD 32-120   Modification to Chemical and Volume Control per IES 79-14           3 32-125   Modification t, Main Feedwater oer IEB 79-14                        4 32-123   Battery O.C. Bus Breaker Alarm                                      3 32-129   Battery 0.C. Bus Breaker Alarm                                      4 32-130   Modification to CVCS (O.C.) per IEB 79-14                           3 32-131   Modification to SI and RHR per IEB 79-14                            4 32-132   Modification to CCW (O.C.) oer IEB 79-14                            4 32-133   Modification to CVCS (O.C.) per IEB 79-14                           3 32-134   Modification to CVCS (O.C.) per IEB 79-14                           4 32-135   Modification to SI and RHR (O.C.) per IEB 79-14                     4 32-136   Modification to Main Steam System (O.C.) per IEB 79-14              4 32-137   Modification to Auxiliary Coolant System (O.C.) per IEB 79-14       4 32-141   Replace Unit Auxiliary Transformer                                  3 32-143   Modification to CVCS (O.C.) per IEB 79-14                           3 32-146   Modification to Auxiliary Coolant System (O.C.)                  3 and 4 32-150   Modification to CVCS (O.C.) per IES 79-14                           3 32-154   Modification to CVCS (O.C.) per IEB 79-14                           4 32-156   Modification to CVCS (O.C.) per IEB 79-14                           3 32-l57   Modification to CVCS (O.C.) per IEB 79-14                           4 32-153   Modification to CCW (O.C.) cer IES 79-14                            4 32-164   Modification to CVCS (O.C.) per IES 79-14                           4 32-165   Modification to CCW (O.C.) per IEB 79-14                            4 32-167   Modification to SI (O.C.) per IEB 79-14                             4 32-163   Replace RCP Temperature Recorder                                    3 32-169   Reolace RCP Temperature Recorder                                    4 32-171   Modification to SI and RHR oer IEB 79-14                            4 32 172,. Modification to CVCS (O.C.) cer IEB 79-14                           4 32-173   Modification to CVCS (O.C.) per IES 79-14                           4 32-174   Modification to CCW (O.C.) cer IEB 79-14                            4 32-136   Fisher and Porter Transmitter Replacement                           4 5-T4:2

TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PCM LIST 3ULY 1,1983 THROUGH 3UNE 30,1984 UNITS COMPLETED PCM NO.                      PCM TITLE DESCRIPTION                       THIS PERIOD 32 195  Modification to CCW (I.C.) per IEB 79-14                              4 32-199  Modification to Auxiliary Feedwater System (O.C.) per IEB 79-14       3 32-200  Modification to Main Steam System per IEB 79-14                       4   ,
32-201  Modification to PZR Surge Line (I.C.)                                 4 32-202  Modification to CCW (I.C.) per IEB 79-14                              4 32-203  Modification to CCW per IEB 79-14                                     4 32-206  Modification to CVCS (I.C.) per IEB 79-14                             4 32-207  Modification to CVCS (I.C.) per IEB 79-14                             4 32-208  Modification to CVCS (I.C.) per IEB 79-14                             4 32-209  Containment Purge Valve Leak Test                                     3 32-210  Containment Purge Valve Leak Test Conn.                               4 32-214  Modification to SI and RHR per IEB 79-14                              4 32-215  Modification to CVCS (I.C.) per IES 79-14                             4 32 220 Modification to Waste Discosal System (O.C.) per IEB 79-14            4 32 221 Modification to Main Feedwater (I.C.) per IEB 79-14                   4 32-222 Modification to SI and RHR (I.C.) oer IEB 79-14                       4 32-223 Modification to Main Steam System (I.C.) per IEB 79-14                4 32-224 Modification to CCW System (O.C.) per IEB 79-14                    3 and 4 32-225  Modification to Si and RHR (O.C.) cer IEB 79-14                       3 32-226 Modification to ICS (O.C.) per IEB 79-14                              3 32 223 Power Sucoly to Access and Dress Facility                          3 and 4 32-229 Access and Dress Facility Septic System                            3 and 4 32-230 Modification to Cond, and FW Aux. System (O.C.) per IEB 79-14         4 Modification to RCS (I.C.) per IEB 79-14                              4 32-231 Modification to Containment Soray (I.C.) oer IES 79-14                4 32 232 32-233 Modification to SI and RHR (I.C.) per IEB 79-14                       4 32-238 Modification to CCT per IES 79-14                                     4 32 239 Modification to CCW oer IEB 79-14                                     4 4
32-241 Modification to CVCS (I.C.) cer IEB 79-14 Modification to CVCS (I.C.) per IES 79-14                             4 32-242 Th:2

TITLE 10, SECTION 50,59 CFR REPORT COMPLETED PCM LIST JULY 1,1983 THROUGH JUNE 30,1984 UNITS COMPLETED PCM NO.                       PCM TITLE DESCRIPTION              THIS PERIOD 32-242  Modification to CVCS (I.C.) per IEB 79-14                    4 32-249  Modification to Waste Disposal System oer IES 79-14          4 32-250  Modification to CCW (I.C.) per IEB 79-14                     4 32-25l  Modification to CCW (I.C.) per IEB 79-14                     4 32 252  Modification to RCS (I.C.) per IES 79-14                     4 32-253  Modification to CVCS (I.C.) per IEB 79-14                    4 32-260  Modification to Boric Acid System oer IEB 79-14           3 and 4 32-261  (CPWO) Decontamination Room Exhaust Duct Installation     3 and 4 32-262  Modification to CCW per IEB 79-14                            4 32-263  Modification to CCW oer IEB 79-14                            4 32-266  Modification to SI and RHR (O.C.) per IES 79-14              3 32-267  Modification to CCW (I.C.) per IEB 79-14                     4 32-263  Modification to RCS (I.C.) per IEB 79-14                     4 32-269  Modification to CCW (I.C.) per IEB 79-14                     4 32-270  Modification to CCW (I.C.) per IEB 79-14                     4 32-274  Emergency Lighting Mounting Modification                  3 and 4 32-275  Modification to CCT (O.C.) per IEB 79-14                     4 32.276  Modification to CVCS (O.C.) per IEB 79-14                    3 32-277  Modification to SI and RHR (I.C.) per IEB 79-14              4 32-273  Modification to Waste Olsposal System oer IEB 79-14          4 32-231  Modification to SI and RHR (O.C.) per IEB 79-14              4 32-234  Modification to RCS (I.C.) per IEB 79-14                     2 32 235  Modification to RCS (I.C.) cer IEB 79-l4                     4 32-290  Modification to SI and RHR (O.C.) per IEB 79-14              3 32-297  Replace Solenoid Vaives and Limit Switch                     3 32-301  Remove Containment Pressure Wide Range Instrumentation       3 32-364  Install Thermoweils on LP Turbine                            3 32-313  Turbine Supervisory Instruments                              4 32-323  (CPTO) Locked High Radiation Area Access Alarm            3 and 4 32-07 A Modification to CVCS (I.C.) oer IEB 79-14                    3 7
T4:2                               ,

TITLE 10, SECTION 50,59 CFR REPORT COMPLETED PCM LIST JULY 1,1983 THROUGH JUNE 30,1984 UNITS COMPLETED PCM NO.                       PCM TITLE DESCRIPTION                  THIS PERIOD 32-09A   Modification to CVCS (I.C.) per IEB 79-14                        3 32- 10 A Modification to Si and RHR (I.C.) per IEB 79-14                  3 32- 14 A Modification to SI and RHR per JEB 79-14                         3 32- 16 A Modification to RCS (I.C.) oer'IEB 79-14                         3 32-17 A  Modification to CCW (I.C.) per IEB 79-14                         3 32-23 A  Crossover Pioing Modification to RCS (I.C.) per IEB 79-14        3 32-23B   Modification to Manifold System (I.C.) per IEB 79-14             3 32-23C   Modification to RCS (I.C.) cer IEB 79-14                         3 32- 24 A Modification to CCW (l.C.) per IEB 79-14                         3 32-25 A  Modification to CCW (I.C.) per IEB 79-14                         3 32- 27 A Modification to CVCS (I.C.) per IEB 79-14                        3 32-23A   Modification to CCW (O.C.) per IEB 79-14                         3 32-29 A  Modification to CVCS (I.C.) per IEB 79-14                        3 32-29B   Modification to CVCS (I.C.) per IEB 79-14                        3 32 40 A  Modification to CCW (I.C.) per IEB 79-14                         3 32 20B   Modification to CCW (I.C.) per IEB 79-14                         3 32 41A   Modification to Waste Oisposal System oer IES 79-14              3 32 41B   Modification to Waste Disposal System (I.C.) per IEB 79-14       3 32 42A   \1odification to CVCS (I.C.) per IEB 79-14                       3 32 43 A  Modification to Si and RHR (I.C.) per IEB 79-14                  3 32 45 A  Modification to SI and RHR ~per IEB 79-14                        3 32-50 A  Modification to CCW (I.C.) per IEB 79-14                         3 32-51 A  Modification to CCW (l.C.) per IEB 79-14                         3 32 51B   Modification to CCW (I.C.) per IEB 79-14                         3 32- 54 A Modification to CCW (l.C.) per IEB 79-14                         3 32- 55 A Modification to RCS (l.C.) per IEB 79-14                         4 32-61 A  Modification to P"R Soray and 51 oer IEB 79-14                   3 32-62A   Modification to CVCS oer IEB 79-14                               3 33-07    Lighting Protection                                           3 and 4 33-14    Fire Water Isolation                                          3 and 4 T4:2

TITLE 10, SECTION 50,59 CFR REPORT COMPLETED PCM LIST 3ULY 1,1983 THROUGH JUNE 30,1984 UNITS COMPLETED PCM NO.                      PCM TITLE DESCRIPTION                     THIS PERIOD 33-15  (CPWO) Replace Meteorological Recorder with Tracor Westronics      3 and 4 33-17   ILRT Containment Penetration Flange Replacement                      3 33-19   Spent Fuel Pit Guard Shack                                           3 33-20   Soent Fuel Pit Guard Shack                           -
4 33-21   Modification to Containment Spray System (I.C.) per IEB 79-14        4 33-27   (CPWO) MSR Steam Valve Inlet Timing Valve                            4 33-23   Alternate Gas Supply for Flux Mapper                                 3 33-29   (CPWO) Emergency Diesel Generator A and B Relay Reolacement    , 3 and 4 33-32   Install Plant Vent Flow Monitor                                   3 and 4 33-37   Replace RCP Vibration Sensor Bracket                                 3 33-39   MSRH Modifications                                                   3 33 44,  (CPWO) Replacement 40629 Breaker                                     4 33 46   Raise Level Alarm on SA and 5B Feedwater Heater                      3 33 47   (CPWO)ICW Check Valve Replacement                                    4 33 43   MSR Impingement Plate Liner                                          3 33-51   Fire Sprinkler System CP Guard House                              3 and 4 33-53   Equipment Hatch Platform                                             3 33-56   Condenser Hotwell Ploe Modification                                  3 33-57   Condenser Hotwell Pipe Modification                                  4 33-60   (CPWO) 4 A MSRH OPI Installation                                     4 33-61   MCC 'O' Breaker 06363 Replace                                    3 and 4 33-70   Reactor He'ad Shielding                                              4 33 74   'VOS Condensate Recovery Pump ' A' Breaker                           3 33-32   (CPWO) Gen. Cond. Monitor Oif/ Moisture Trao Bowl Reolacement        3 33-33   Gen. Condition Monitor Oll/ Moisture Trao Bowl                       4 33-34   MSR Timing Valve Relocation                                          3 33-37  '(CPWO) Mvar Telemetering                                             4 33-90   (CPWO) WTP Strainer for Mixed Bed Demineralizer                  3 and 4 33-91   (CPWO) Service Air ' Check Valve Replacement                         4 33-94   4160 Volt Switchgear Additional Bracing                              3 T4:2

TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PCM LIST JULY 1,1983 THROUGH JUNE 30,1984 UNITS COMPLETED FCM NO.                            PCM TITLE DESCRIPTION                  THIS PERIOD 33 95         4160 Volt Switchgear Additional Bracing                          4 33-110        Cevers for Cherry Picker Anchor Bolts                            3 33-111        'CPWO) Condensate Polishing System 24 Volt DC Power Supply       3 33-120        Mechanical Stops for Containment Purge Valves                    3 33-122        (CPWO) Emergency Feeder to MCC RB (Temp)                     Common 33-125     ' Pressurizer Relief Valve Cable Relocation                         3 33-130        240 KV Digital Meter                                             3 33-131        240 KV Digital Meter                                             4 33-132        Replace FCV 113 B and 114B                                       3 3 3- 13 t.    (CPWO) Thrust Ring Replacement for Check Valve 4-312A            4 33-135        Security Lighting Hand Hole #514                              3 and 4 33-160        (CPWO) Turbine Deck Lights                                    3 and 4 33-165        RCP Lower Oil Reservoir CCW Hoses                                3 33-166        RCP Lower Oil Reservoir CCW Hoses                                4 33-131         Normal A/C Air Side Seal Oil Motor Reolacement                  4 4
33-136        (CPWO) RHR Pumo Motor Mounts 33-133        (CPWO) RHR Pump Motor Mounts                                     3 33-194         Portable Dealkalizing Demineralizer System                  '3 and 4   ,
33-196         MSIV Closing Solenoid Check Valves                              3 MSIV Closing Solenoid Check Valve Addition                      4 33 .l.97 (CPWO) Add Hinge Pin Cover Spacer on MSCV and MSIV               4 33-203 33-205         Fuel Transfer System - Cear Limit                               3 4
33-206        (CPWO) Blowdown FCV Actuator Modification FC-3500 33-210        (CPWO) Cable Reolacement for CV3-522A and CV-3-389               3 33-211         Install Temperature Ex-vessel Dosimetry                         3 33-215         Solenoid Mounting Bracket for Purge Supoly Valve #2601          3 Fuel Transfer System Gear Limit Switch                          4 34-06 34-13         (CPWO) Telemetering Cond. for 'C' Bus                            3 34-23          Modification to CVCS (I.C.) per IEB 79-14                       4 Modification to CVCS (I.C.) per IEB 79-14                       4 34-29
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TITLE 10, SECTION 50,59 CFR REPORT
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COMPLETED PCM LIST JULY 1,1983 THROUGH 3UNE 30,1984 UNITS COMPLETED PCM NO.                     PCM TITLE DESCRIPTION                    THIS PERIOD 34-33  Modification to Intake and Chlorination System                     4 34-36  Relocate over Current Trip Relays on 4 AC01,4 AC03,4 AC16,         3 3 ACO1, 4 ACO3, 4 AC06 34-37  Relocate over Current Trip Relays on 4 AC01,4AC03,4AC16,           4 3 AC01, 4 AC03, 4 AC06 34 40  Modification to CCW (I.C.) per IES 79-14                           4 34 41  Modification to CCW (I.C.) per IEB 79-14                           4 34 44  (CPWO) Temporary Substitution of Stud and Bolt Material            4 34-56  Blowdown FCV Actuator                                              4 34-62  SFP Bridge Crane Hatchway Limit Switch Bracket                     4 34 72  Uoender Proximity Switch Sensing                                   4 34 76  CCW Pump Casing Stud and Nuts Replacement                          4 34-32  (CPWO) Intake Lights Upgrade to High Pressure Sodium Vapor      3 and 4 34 71  CCW and TPCW Heat Exchanger Cathodic Protection                    4 Th:2

  . PLANT CHANGE / MODIFICATION 77-45B             PC/M CLASSIFICATION:                NNS UNIT:        3&4
  ,                                                          IMPLEMENTED:          11-15-83 TURNED OVER DATE:             11-29-83

==SUMMARY==
DATE:           12-01-83 REVISION:           2 DEMINERALIZED WATER STORAGE TANK FOUNDATIONS AND RETAINING WALL Summary:
This PC/M provided a demkneralized water storage and deaeration system.to supply the steam generator with deaerated water during start-up, shutdown, and hot standby operations. This included a water storage tank with a N2 blanket to prevent reabsorption.
Safety Evaluation:
This modification did not involve an unreviewed safety question because it did not affect any safety related features.       No margin of safety as defined in the Technical Specifications was decreased nor were any possibilities of accident created or increased.
I

                                          ,,~m       c w ,, o s  .m _ . . . m .,  ..u.      ,a
-   s,                   . c - w .e . . w UNIT:      4
                                                              ? IMPt.EM ENTED:          06-02-83 TURNED OVER DATE:-              09 23-83

==SUMMARY==
OATE:             09-I9-33 R E*.'ISI.O N:     1 CONTAINMENT MODIFICATIONS FOR STEAM GENERATOR REPAIR FOR UNIT 4 Summary:
Tais modifica: ion removed electrical cables, raceways, mechanical equipment, piping and ins:rumenta:!cn, walls, slabs and structural- steel and prepared laydown areas and a transfer platform inside containment building in order to have passage and work areas for
:he steam generator lower assemblies.
Safety Evaluation:
      .ne unit was at cold shutdown with fuel removed from the core during this modification.
Since :he containment building was returned to its original condition, no unreviewed safety ques !cn was created.
L

PLANT CHANGE / MODIFICATION 77-54H                PC/M CLASSIFICATION:       NS UNIT:         4 IMPLEMENTED:     06-02-83 TURNED OVER DATE:     09-21-83

==SUMMARY==
DATE:      09-26-83 REVISION:         1 CONTAINMENT MODIFICATION POR S.G. REPAIR - UNIT 4 Summary:
In order to accomplish the steam generator repair the following systems were cut or removed:
: 1. Main Steam Piping
: 2. Main Feedwater Piping
: 3. Steam Generator Blowdown Piping                                           '
: 4. Cooling Water Return Piping from Emergency Coolers
: 5. Cooling Water Pipes to and from RCP "A"
: 6. Service Air Piping
: 7. Primary Service Water Piping
: 3. Miscellaneous Instrumentation Lines All piping will be reinstalled to their original geometry. -
Safety Evaluation:
The unit was at cold shutdown with fuel removed from the core during this modification.
Since the piping and systems were returned to their original condition and tested, no unreviewed safety question was created.

M       6:                             NS 4
UNIT:         a IMPLEMENTED:         03-21-30 TURNED OVER DATE:          06-12.3h SUMM ARY D ATE:        06-26-3h R EVISION:         1 CONTAINMENT MODIFICATION FOR STEAM GENERATOR REPAIR (ELECTRICAL)
Summary:
This modification removed and reinstalled or replaced cables and raceways to allow access for S.C. repair. ' Reinstallation was made to meet original design requirements.
Safety Evaluation:
The removal and reinstallation /reolacement of cables and raceways did not involve an unreviewed safety question as the changes did not affect any pressure boundary or degrade t9e reliability of any other safety related system or equioment.
e

PC/M CLASSIFICATION:                                                                                            NS PLANT CHANGE '''TDIFICATION 77-50 UNIT:       a IMPLEMENTED:                                                  06-02-83 TURNED OVER DATE:                                                                                     09-21-83

==SUMMARY==
DATE:                                                     09-26-83 REVISION:                       1 CONTAINMENT MODIFICATION FOR STEAM GENERATOR                                                                                                                                       REPAIR (CONTROL SYs a r.MS) UNu 4                   .
Summarvt Tnis PC/M consisu of the removal and replacement of instruments, sensing lines and assoc:atec suoports in the vicinity of each generator within the containment during its repair and removal. Tne existing sensing line tubing will be replaced with new stainless steei tuoing.
Safety EYaju& tion!
Tnis PC/M is nuclear safety related. The removai and replacement of instrumentation for
:ne steam generator repair does not cause a change to any system characteristics and :ne procacility of an accident would be no greater. Therefore, this PC/M does not present an unreviewed safety question since it does not affect any accident addressed in :ne FSAR.
present any new accident not previously analyzed in the FSAR, nor affect the margin of safe:v discussed in :he Tech Spec as :he changes do not affec any pressure boundary or any otner safety system.
l 4
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            . , . ,         .     . . - .         - - _ , - _ _ . . - _ . - - - -  - - . . - - , - , . _ . - _ _ - - , , - - - - - - . . - _ , . - - - - , . _ , - , . - - - - - - - .                   -s

PLANT CHANGE / MODIFICATION 73-31                   PC/M CLASSIFICATIONI        NNS UNIT:      3&4 IMPLEMENTED:      09-29-83 TURNED OVER DATE:       10-12-83

==SUMMARY==
DATE:       10-13-83 REVISION:         1 NUCLEAR MAINTENANCE BUILDING Su mmary:
This PC/M provides a new facility to be used for construction operations during the steam generator repair activities. It will be used for construction personnel access control, for offices and for light storage.                    .
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been Increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.

PLANT CHANGE / MODIFICATION 73-76              PC/M CLASSIFICATION             NS
  .                                                                   UNIT:         4 IMPLEMENTED:         0t /24/33 TURNED OVER DATE:          09-21-83

==SUMMARY==
DATE:          09-26-83 REVISION:           0 BREATHING AR SYSTEM Summary:
This modification consisted in adding the breathing air system to supply clean air to persons working on the steam generator repair effort inside containment, but can be expanded to include other contaminated areas. The system consists of two breathing air compressor packages, two refrigerating dryers, one air receiver one absorber / filter, and outlet manifolds.
Safety Evahation:
This change is nuclear safety related with no unreviewed safety question. No probability or consequence of an accident occurring was increased as previously evaluated in the FSAR nor was any malfunction probability increased to any existing equipment. No margin of safety was decreased as defined in the Technical Specifications.
t

  . PLANT , CHANGE / MODIFICATION 73-34            PC/M CLASSIFICATION:                NS UNIT:            a
  .                                                         IMPLEMENTED:            08-16-33 TURNED OVER DATE:            02-17-34

==SUMMARY==
DATE:           02-2a-3a REVISION:              .
PwwnWATER RECRCULATION SYSTEM Summary:
Tnis PC/M provides a recirculation system for :he feedwater :o be used at cold snutcown.
Safety Evajustion:
The probability of occurrence or the consequences of an accident or malfunc   :
:en of equipment imoortant to the safety of the plant, previously evaluated in the . SAR. .as ,o:
been increased. There is no possibility of an accident or malfunction different*: nan : nose previously evaluated. Therefore, it can be concluded that :his PC/M does not mose anv unreviewed safety questions.
O e

r PLANT CHANGE / MODIFICATION 78-104                 P  !'.t ;L ASSITIC ATION:         NS UNIT:   3 and a l'.iPLE\iENTED:   ' ;-13-3 3 TURNED OVER D ATE:         03-31-30 SUNi\i ARY D ATE:   0:--3 3 8 '.
REVISION:
AUXILIARY FEEDWATER PUMP LUBE OIL COOLER Summary:
This PC/\1 provided a permanent fix to supply cooling water to the safety related auxiliary feed pump lube oil coolers from the second stage of the auxiliary feed pump and route the lube oil cooler discharge flow to the. condensate storage tanks.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunct:en of equipment important to the safety of the plant, previously evaluated in the FS AR. 5as not been inc eased. Tnere is no possibility of an accident or malfunction different than tnose previously evaluated. Tnerefore, it can be concluded that this PC/\i does not oose anv unreviewed safety questions.
e 9
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PLANT CHANGE / MODIFICATION 78107                                       PC/M CLASSIFICATION:                                       NNS
  ,                                                                                                      UNIT:                             a IMPLEMENTED:                                      03-28-83

==SUMMARY==
DATE:                                      07-22-83 REVISION:                               0 STEAM LINE WARM-UP t
^
Summary:
This change added a steam line warm-up line to provide a means of interconnecting the existing tie line to the main steampiping of Unit 3. The purpose of this modificaiton is to                                                         t decrease the start-up time of Units 3 and 4.
Safety Evakastion:
This change is non-nuclear safety related as it does not have any affect on the accicen:s analyzed in the FSAR. No safety related equipment was involved or affected 5v :nis change. The addition of the steam line warm-up did not involve an unreviewed safetv question.              .
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                                                                                                                          -,_.-,_,_,y-          - - , .
                       , _ _   ~ ._ _ _ - . _ , . . - . __           _,.,_,m,     _    - _ - _ - _     -

      ?LANT CHANGE!MCDIFICATION 73-040 A                                                PC/M CLASSIFICATION:     NNi UNIT:      a
                                                                                                !MPLEMENTED:  ^ 6 3 -

==SUMMARY==
DATE:   09-26-33 REVISION:       1 STEAM GENERATOR TET LAYUP SYSTEM (CIVIL)
Summc w:
7.e :urpose _of :his ?C/M was to provide a foundation for the Steam Generator Tet Layup pumos.and a foundation for one chemical feed pot. The pumps and feed pot are part of the Steam Generator Tet Layup System which was installed to maintain water chemistry and prevent stra !!! cation inside the steam generators during extended shutdown per!ods.
Safe:v Evaluationt
: 7. Or:: ability :f oc:urrence or the consequences of an accident or malfunction                                   f    -
ecu.p .ect ! por: ant to the safe:y of the plant, previously eva!uated in :he FSAR, has not
:een inc essed. inere .s no possibility of an accident or malfunction different :han those p ev::us;y evalua:ed. 79erefore, it can be concluded : hat this ?C/M does not pose any
      . .reviewe safety :.ues-lons.                                                           .
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PLANT CHANGE.' MODIFICATION 73-32B             PC!M CLASSIFICATION:            NNSR
  -                                                                     UNIT:
I'.t ?LEM ENTED:      :9-29-53 TURNED OVER DATE:           .-  :: -i?

==SUMMARY==
DATE:           : -::-33 REVISION:          !
CONDENSATE POL!SHING DEMINERALIZER SYSTEM UNIT 4 Summary:
l   This modification provided a condensate polishing deminerati:er sys:em :: pur.f:. : .e c:ndensate by filtration and deminerall:ation, thus providing hign quali:y :: .:e rate water :o :he steam generator.
Safety Evaluat!on:
The probability of occurrence or the consequences of an ac:::e-: Or 1;f. ::.:-
equipment !mportant to the safety of the plant. prev!: s!y eva;;a:ec ~- : e Fi-?.. u l
been inc.-eased. Tnere is no possibility of an accicent :r -a:f ec . :.f f ee : .- -
prev!ously evaluated. Tnerefore, it can be c:nc:ucee : .a: :-is PC '.'. ::es ::          ..
;   anrev!ewed safety questions.
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________.u

PC/M CLASSIFICATION:              NS
  '.
* NT CHANGE / MODIFICATION 79-14 UNIT:            4
'                                                            IMPLEMENTED:          05-26-83

==SUMMARY==
DATE:         05-10-83 REVISION:            .
STEAM GENERATOR VENT VALVE REPLACEMENT                                        '
SummerYt This modification consisted of replacing the steam generator vent valves (11-i,3, 243, 343) witn valves from a rnanufacturer on the QA approved vendor list. The original valves v.. a were beyond repair and needed replacement. The original valve supplier is no longer Q A approved vendor list.
Safety Evaluation:
This modification does not involve an unreviewed safety question as this modi.fication coes not increase the possibility of a " Rupture of a Steam Pipe" accident whien is describec :n"e Section 14-5.2 of the FSAR.          Furthermore, this mocification will et increase probability of malfunction of equipment previously evaluated in the FSAR.

r l
PLANT CHANGE / MODIFICATION 79-27                         PC/M CLASSIFICATION:          NNS l
1 UNU:         3&4 i                                                                    IMPLEMENTED:        06-03-33

==SUMMARY==
DATE:         07-22-83 REVISION:          0 t
l
                                                                         ~
l   Flow TRANSMTTTER (PT-1007) REPLACEMENT Summary:                                  <
l The work performed.under this PC/M replaced the existing Foxboro model 18 target flow transmitter (FI-1007) by one that uses the ultrasonic flow measurement technique. The reason for tnis change was due to the unreliability and high maintenance of the previous target flow transmitter.
Safety Evaluation:
This PC/M is not nuclear safety (NNS) related.                  No increase in the probability of occurrence or consequences of an accident or the creation of a possibility for an accident or malfunction of a different type than those previously evaluated in the FSAR results, the margin of safety as defined in the basis for any Technical Spec'fication is not reduced.
Therefore, this PC/M does not pose an unreviewed safety question.
s G
a 4
                                                                   /

PLANT CHANGE / MODIFICATION 79-34              PC/M CLASSIFICATION:             NNS UNIT:          4 IMPLEMENTED:       05-26-83 TURNED OVER DATE:         09-21-83

==SUMMARY==
DATE:       09-26-83 REVISION:          1 ADDITION OF S/G ALTERNATE FEEDWATER LEVEL CONTROL Summary:                                   ,
This PC/M consists of connecting the alternate level transmitter to existing sensing lines of the narrow range transmitters, to provide redundant narrow range steam generator level transmitters for feedwater control.
Safety Evaluntlan:
This steam generator feedwater alternate level control channel provides the operator with an additional level measurement choice and does not perform any safety related function nor are they connected into any other safety related system. On this basis, this PC/M is considered to be non-nuclear safety related.
e 4
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PC/M CLASSIFICATION:            NS PLANT CHANGE / MODIFICATION 79 46_
UNIT:         3 IMPLEMENTED:        04-03-83 TURNED OVER DATE:         03-05-84

==SUMMARY==
DATE:         03-08-84 REVISION:         0 THERMAL INSULATION FOR UNIT 3 BORIC ACID SYSTEM Summary:
This PC/M provides instructions for replacing present thermal insulation on Boric Acid System with new removable refractory insulation. This insulation will provide ease in working on the system in the future.
Safety Evaluation:
This PC/M does not have a detrimental effect on any plant system or component important to safety and, therefore, does not involve any unreviewed safety question.
e k

PC/M CLASSIFICATION:            NS PLANT CHANGE / MODIFICATION 79-47 UNIT:         4 IMPLEMENTED:        04-03-83 TURNED OVER DATE:         03-05-84

==SUMMARY==
DATE:         O LO8-34 REVISION:         0 THERMAL INSULATION FOR UNIT 4 BORIC ACID SYSTEM Summary:   ,
This PC/M provides instructions for replacing present thermal insulation on Boric Acid System with new removable refractory insulation. This insulation will provide ease in working on the system'in the future.
Safety Evaluation:
This PC/M does not have a detrimental effect on any plant system or component important to safety and, therefore, does not involve any unreviewed safety question.

PLANT CHANGE /MODIFICAT:0N 79-52                                    PC/M CLASS 1F1 CATION:                                NS UNIT:                                     3 IMPLEMENTED:                    07-28-83

==SUMMARY==
DATE:                    08-15-83 REVISION:                                     0 AREA RADITION MONITORING SYSTEM (ARMS) ENHANCEMENT Summary                                       .
This modification replaced buzzer alarm unit (DS 900) with an electronic alarm unit (Mallory SC 110P). Purpose being buzzer could not be heard in high ambient noise areas and maintenance was very high due to ageing of contacts in unit. Also performed was the relocation of the red alarm light from the front of the remote alarm unit to the top of the enciosure (outside containment only).
Safety Evaluation:
The probability of occurrence or the consequences of a design basis accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of accident or malfunction different
;              than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
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                                                                                            ,      - - - - - . ~ . , , , , , . - . - - - - . - .

PLANT CHANGE / MODIFICATION 79-38_               PC/M CLAS3Iri: ATION:              NS UNIT:          o IMPLEMENTED:        02-29-84 TURNED OVER DATE:             03-05-84

==SUMMARY==
DATE:         03-08 84 REVISION:           1 CONTAINMENT RAMP MODIFICATIONS AND S.G. HAUL ROUTE FOR S.G. REPAIR Summary:
This PC/M provided for relocating the three-unit security light fixture to another security light pole nearby. The light fixtures were oriented to provide lighting to the same area as before. This modification also provided for raising the fire hydrant just south of Unit 4 and modifying the ramp slope to clear and provide access to the fire hydrant and nearby post indicator valves.
Safety Evaluation:
The probability of occurrence or the consequences of .sn accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
j P

  ?tAPJT CHANGE / MODIFICATION 79-112             PC/M CLA55IFICA'TidN:              NS UNIT:            3
.                                                          IMPLEMENTED:          03-06-83 TURNED OVER DATE:          02-17-84

==SUMMARY==
DATE:          02-24-84 REVISION:             0 ADDITION OF REACTOR COOLANT SYSTEM VENTING Summary:
This PC/M provided for the instaliation code change for the RCS vent system from ASME III to ANSI B 31.1. This is in accordance with the requirements of ASME XI which allows
:na use of the original code when modifications are performed to an existing system.
Safety Evaluation:
The addition of a reactor coolant venting system consists entirely of seismically supoor ed piping, valves and controis. 'Ihis system also does not decrease :ne design margins of the system nor changes the operating function or affects the other safety related eculpment.
Therefore. :his addition does not create the possibilty of an accident nor does it involve an unreviewed safety question.

PC/M CLASSIFICATION:           NS
    ' PLANT CHANGE / MODIFICATION 79-127 UNIT:         4 IMPLEMENTED:         06-22-83

==SUMMARY==
DATE:          07-22-83 REVISION:          0 REACTOR COOLANT PUMP SEAL RETURN LINE SUPPORT MODIFICATION Summary:
This modification consisted in adding redesigned, new support for the reactor coolant-pump seal return lines which was determined to be inadequate per NRC LE. Bulletin 79-14 stress analysis.
Safety Evaluation:
This change does not present an unreviewed safety question since it does not affect any accident addressed in. the FSAR, present any new accident not previously analvred in the FSAR, nor affect the margin of safety for any Technical Specification.
                                                                                  =
l

1 PLANT CHANGE / MODIFICATION 79-133C              PC/M CLASSIFICATION:             NS       1 UNIT:           4 IMPLEMENTED:         12-01-83 TURNEO OVER DATE:          06 05-84 SUMM ARY DATE:         06-26 84 REVISION:           1 ADDITION OF CONTAINMENT HYDROGEN MONITORS UNIT 4 Summary:     .
This PC/M consists of the addition of redundant containment hydrogen monitors with readout indication located in the main control room. The purpose of this implementation is to provide post LOCA sampling and analysis of the containment atmosphere to monitor free gaseous hydrogen below the lower explosive level in accordance with USNRC R.G.
1.97.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.

PLANT CHANGE / MODIFICATION           80-23       PC/M CLASSIFICATION:                  NS UNIT:         3 and 4 IMPLEMENTED:         09-27-33 TURNED DVER DATE:                05-12-34

==SUMMARY==
DATE:         05-16-84 REVISION:            0 ADDITION OF POST ACCIDENT SAMPLING SYSTEM Summary:                                                                           .
This modification consisted of adding a Post Accident Sampling System that is common to both Units 3 and 4.       This also required the replacement of existing sample line, containment isolation valves with fully qualified solenoid valves along with the addition of reach rods to other existing valves as shown on the P and ids. New stainless steel tubing will be added with all necessary radiological :hielding. This modification met the requirements of NUREG 0573 to provide post accident sampling capability for the parameters and ranges specified by Reg Guide i.97, Revision 2.
Safety Evaluation:
The addition of the Post Accident Sampling System does not involve an unreviewed safety question because it will not affect the function of any other safety system.                  No character'istics have been changed and the probability of occurrence of an accident would be no greater. The consequences of an accident previously evaluated in Chapter i4.0 would not be altered. The addition of the Post Accident Sampling System will have no potential to jeopardize the operation of other safety related systems. The consequences of the equipment malfunction are no more severe than previously analyzed in Chapter l 4.0 of the FS AR. This addition does not decrease the design margins of any system, change the operating function or conditions, or affect the other safety related equioment.
Therefore, this change would not create the possibility of an accident not considered in Chaoter 14.0 of the FSAR. The addition would create the possibility of malfunction of equipment not considered in Chapter 14.0 of the FSAR. This addition will not decrease any margin of safety discussed in the Technical Specifications.

                                        ^                               -             '
PLANT CHANGE / MODIFICATION 80-25                PC/M CLASSIFICATION:             NS UNIT:         3 IMPLEMENTED:       11-09-83 TURNED OVER DATE:           11-16-83

==SUMMARY==
DATE:       11-13-33 REVISION:         0 ADDITION OF CONTAINMENT HIGH RANGE RADIATION MONITORS Summary:
This change consists of adding redundant containment radiation monitors with read-out indication located in the control room to cover the radiation range of 100 _ 103 R/hr.
Safety Evaluation:
This PC/M provided redundant containment radiation monitoring. No system c7.aracteris-tics have been changed and the probability of occurrence of an accident would not be
   - greater. .also, the consequences of an accident previously analyzed in Chapter 14 would not be altered.
e

PC/M CLASSIFICATION:               NS PLANT CHANGE / MODIFICATION 80-26_
UNIT:               3 IMPLEMENTED:             12-28-82

==SUMMARY==
DATE:              09-01-83 REVISION:               O CONTAINMENT HIGH RANGE RADIATION MONITORING SYSTEM Summary:
This modification provided the addition of redundant containment radiation monitors with3 read out indication located in the Control Room to cover the radiation range 100 - 10 R/HR. This is to comply with requirement of USNRC NUREG 0578 and USNRC Reg. l.97 Rev. 2 (Draft 2).
Safety Evaluation:
This PC/M is nuclear safety related with no unreviewed safety question. No probability or
- consequences of an accident or malfunction has been increased. Furthermore, the margin has not decreased as defined in the Technical Specifications.
e

i PLANT CHANGE / MODIFICATION S0-35              PC/M CLASSIFICATION:               NS            l UNIT:          3            !
IMPLEMENTED:          10-30-80          j TURNED OVER DATE:           11-03-S3          1

==SUMMARY==
DATE:           11-10-83 REVISION:           1 AUXILLARY FEEDWATER LINE SOPPORT MODIFICATIONS - UNIT 3 l
Summary:
Pipe supports were modified for greater seismic load and thermal stress load capacity.
This was done in response to USNRC IE Bulletin 79-14.
   - Safety Evaluation:
This modification was nuclear safety related because the Auxiliary Feedwater System needs to remain operational during seismic events and thermal transients.              i nts modification does not involve an unreviewed safety question since it does not increase the possibility of any accident addressed in the FSAR, or present any new accident not previously analyzed in the FSAR, nor decrease the margin of safety for any Technical Specification.
5 e

PC/M CLASSIFICATION:
PLANT CHANGE / MODIFICATION 80-38_
UNIT:        3 IMPLEMENTED:     Oh-29-33 TURNED OVER DATE:        11-29-83

==SUMMARY==
DATE:      12-02-83 REVISION:        1 REACTOR COOLANT SYSTEM VENT SYSTEM summary:
The subject PC/M installed a permanent venting system for the Reactor Coolant System.
This syste'm will reduce amount of process water and operator time required to complete the filling and vent procedure. It will reduce leakage from tygon hose connections and bends in the vent lines occurring prior to this modification (NUREG 0737 work).
Safety Evaluation:
                            ~
The subject PC/M satisfies applicable code requirements regarding RCS pressure boundary double isolation valves, welding, materials, fabrication, and testing. No increase in the probability for an accident as analyzed in' the FSAR resulted. No possibility for an accident of a different type resulted. No reduction in the margin of safety as defined in the basis for any Technical Specifications results.
          /
v       - -..                    -- -

F                                          -
          ?LANT CHANGE''.10DIFICATION S0-39                PC/.\1 CLASSIFIC ATION:                   N5-UNIT:           i I\1PLEi1ENTED:               :5-26-53 S i.u.,. .\1.a. R v, n. a. :_ .
                                                                                                      ,e
                                                                                                      .- n.
REVISIO N:             1 RCS VENTING SYSTEM
  ~
Summarv:
11:s modifica: ion added isolation valves, sight glasses and cicinz, inc!uding flexible          e:2;
         - noses :o direct any possible licuid flow :o the containmen; sumo for crocessi .g in - .e licuid waste discosa! system. 'Affected were the No. ! sea! 'eakoff ven:s fro- P.e RC?s anc Pr: safe:y line drain that includes valve Sh6. The RCS venting sys:em crovides a means for venting :he RCS during draining and filling opera: ions.
Saferv Evaluation:
The RCS ven:ing system was designed and buil:. :o :he original codes. T,e sys:e- as been tes:ed a: full sys:em pressure without leakage. It is, therefore, concluded :na: : mis modification will not increase :he probability of the loss of coolan: accident or oose anv unreviewed safety cuestion. ine marg:n of safety was no: decreased nor the orobaci.1 v for eculpment malfunc-ion increased.
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F L .
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PC/M CLASSIFICATION:                     NNS PLANT CHANGE / MODIFICATION 80 40_
UNIT:                3&4 IMPLEMENTED:                04-29-83

==SUMMARY==
DATE:                08-26-83 REVISION:                  1 STEAM GENERATOR STORAGE COMPOUND Summary:
of the This PC/M added the steam generator storage compound located southeast Radwaste Building to be used for Units 3 & 4.
Safety Evaluation:
This PC/M is not safety related and does not perform a safety function; therefore, :ne probability of occurrence or the consequences of an accident or malfunction of equipmen:
important to the safety of the plant, previously evaluated in the FSAR, has not been increased. It can be concluded that this PC/M does not involve an unreviewed safety question.
O e
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PC/M CLASSIFICATION:              NNS PLANT CHANGE / MODIFICATION 80 43_
UNIT:           4 IMPLEMENTED:          05-10-83

==SUMMARY==
DATE:         07-22-83 REVISION:            1 ADDITION OF STEAM GENERATOR ACCESS PLATFORM Summary:
This modification provided access to the steam generator manway cover and to support a manway cover handling deviciand~a manway cover storage compound.
Safety Evaksation:
The probability of occurrence or the consequences of an accident or malfunction of equipment.important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.

PC/M CLASSIFICATION:                                                    NS PLANT CHANGE / MODIFICATION SC-"
UNIT:                                       3 IMPLEMENTED:                                                07-13-83
                  -                                     TURNED OVER DATE:                                                 02-17-84

==SUMMARY==
DAT :                                                 02-2c-8h REVISION:                                                  0 MODIFICATION OF CONTAINMFNT PEN. ISOLATION SYSTEMS Summerr                                  .                        .
This PC/M added 1) a soienoid valve downstream of valve #552, 2) a check valve for Pen 6, 3) at P25 a. motor operated isolation valve, 4) P30 a check valve, 5) P-42 a check valve and 6) switches. Purpose of this modification was to fulfill commitments made to the NRC NUREG 0573 audit team.
Safety Evahastion:
This PC/M added containment isolation valves and mod. redundant valve hand switches which will not have any effect on any accident evaluated in Chapter la of the FSAR. The consequences of an accident previously analyzed in the FSAR would be reduced.
I

PLANT CHANGE / MODIFICATION 80-52               PC/M CLASSIFICATION:            NS UNIT:         4
                  ..                                   ' IldPLEMENTED:       08-26-83 TURNED OVER DATE:          09-23-83

==SUMMARY==
DATE:         09-23-83 REVISION:         1 MODIFICATION OF CONTAINMENT PENETRATION ISOLATION SYSTEM - UNIT 4 Summary:
The following containment penetrations were modified:
: 1) . Check valves were added to P6, P29, and P42.
: 2)   Solenoid valves were added to P5                                                    '
: 3)   Motor operated valve was added to P25 Also, five control switches were added so that each of the following redundant containment isolation valve groups has its own switch: 2819 and 2826, Instrument Air Bleed; 2821 and 2822, Containment Sump Discharge; 2600 and 2601, Containment Purge; 2602 and 2603, Containment Purge; 2911,2912, and 2913, Containment Air Sample.
~!he purpose of this modification was to fulfill commitments made to the NRC NUREG 0578 audit team.
Safety Evaluation:
This modification is nuclear safety related. All safety related areas have been reviewed and complied with in respect to any accidents, malfunctions, and margins of safety.

PLANT CHANGE / MODIFICATION 80-56               PC/M CLASSIFICATION:              NS UNIT:          4 IMPLEMENTED:           03-23-83

==SUMMARY==
DATE:            10-17-83 REVISION:            2 UPGRADE OF AUXILIARY FEEDWATER SYSTEM FLOW CONTROL AND INITIATION -
UNIT 4 Summary:
Electrical portion of aux. feedwater initiation upgrade. Install new harid indicating controllers in control room, new indicators on the valve platform instrument nests and power supplies in cable spreading room.
Safety Evaluation:
The installation of the auxiliary feedwater flow indication, initiation and control system
  -does not involve an unreviewed safety question because it does not affect any pressure boundary or any other safety system.

PLANT CHANGE / MODIFICATION 80-57               PC/M CLASSIFICATION:                       NS    1 UNIT:       3&4 IMPLEMENTED:                 01-25-82 TURNED OVER DATE:                     12-20-83

==SUMMARY==
DATE:                    12-20-83 REVISION:           1 MAIN STEAM LINE SUPPORT MODIFICATIONS - UNITS 3 AND 4 Summary:
This modification involves two additional supports and modification of four existing supports. This modification allows the system to remain operational following a seismic event.
Safety Evaluation:
This change did not present an unreviewed safety question since it did not affec: any accident addressed in the FSAR, or present any new accident not addressed in the FSAR.
nor affect the margin of safety for any Technial Specification.

PLANT CHANGE / MODIFICATION 80-.62 -            PC/M CLASSIFICATION:             NNS UNIT -      3&4 IMPLEMENTED          11-07-83      .
TURNED OVER DATE:           11-29-83

==SUMMARY==
DATE:           12-01-83 REVISION:           0 CAS STRIPPER BOTTOMS PUMP REPLACEMENT Summary:
         . This modification consisted in replacing the gas stripper bottoms pumps (canned type) with frame mounted centrifugal pumps, single stage, end suction and horizontal shaft since existing pumps were unsuitable for the application and failed repeatedly, Safety Evaluation:
This change is non-nuclear safety related with no unreviewed safety question.' The gas strippers are not associated with and cannot interfere with nuclear safety related i: ems.
Thus, consequences of any accident / malfunction as previously evah:sted in the FSAR is not created.
O t
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PLANT CHANGE / MODIFICATION 80-064_                           PC/M CLASSIFICATION:        NSR UNIT:     4 IMPLEMENTED:   09-30-83 TURNED OVER DATE:        12-07-83

==SUMMARY==
DATE:    12-12-83 REVISION:     1 POST ACCIDENT SHIELDING MODIFICATION UNIT 4 Summary:
This PC/M involved addition of lead shielding to reduce radiation exposure in, areas which will require access during a post accident condition. In addition, reach rods were added to seven valves on the CCW system which will be in high post accident radiation areas. The i
Waste Disposal System was also modified such that under post accident conditions, collected liquid can be pumped back to containment.
Safety Evaluation:                      -
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not
: v. been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
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PLANT CHANGE / MODIFICATION 80-72               PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTED:           12-01-83 TURNED OVER DATE:              02-27-84

==SUMMARY==
DATE:             03-01-84 REVISION:            0 MODIFICATION TO LOW HEAD SAFETY IN3ECTION SYSTEM PER LE. 79-14 Summary:
This PC/M consisted in modifying the pipe supports on the Low Head Safety injection System to comply with NRC !.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION          80-80      PC/M CLASSIFICATION:             NS UNIT:         3 IMPLEMENTED:        01-20-82 TURNED OVER DATE:          11-16-83

==SUMMARY==
DATE:          11-17-33 REV'!SION:         1 REACTOR COOLANT SYSTEM ISOLATION CHECK VALVE TESTING Summary:                  .
Pressure gauges and connections were added to provide a means of testing reactor coolant system isolation valves. This modification was needed for inservice inspection for leaks.
Safety Evaluation:
This modification did not involve an unreviewed safety question because the additional connections and gauges did not increase the possibility of any accident addressed in the FSAR, present the possibility of any accident not addressed in the FSAR, nor decrease the margin of safety for any Technical Specification.

i PC/M CLASSIFICATION:               NS PLANT CHANGE / MODIFICATION S0-96 UNIT:           e IMPLEMENTED:          03-26-83 5.UMM ARY D ATE:         10 17-S3 REVISION:            2 EMERGENCY CONTAINMENT FILTER MODIFICATION Summary:
This PC/M upgrades several Emergency Containment Filter Dousing valves to Post LOCA qualified valves. Piping from the Containment Spray to the filters will be changed from carbon steel to stainless steel.' Isolation valves and test connections are also supplied.
Safety Evaluation:
The probability of occurrence. or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR,5as not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Tlierefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.

PLANT CHANGE / MODIFICATION 80-115               PC/M CLASSIFICATION:           NS UNIT:        3 IMPLEMENTED:        03-04-82 TURNED OVER DATE:         L1-02-83*

==SUMMARY==
DATE:        11-07-S3 REVISION:         1 REPLACEMENT OF FEEDWATER LINE SNUBBERS - UNIT 3 Summary:
Five PSA-10 snubbers on the feedwater piping inside containment were replaced with PSA-35 snubbers. The higher capacity PSA-35 snubber will withstand higher transient loads than the damaged PSA-10 snubbers they replaced.
Safety Evaluation:
This modification is nuclear safety related because the main feedwater system is required to remain intact during a seismic event. It did not present an unreviewed safety question because it did not increase the possibility of any accident addressed in the FSAR, or present any new accident not addressed in the FSAR, nor decrease the margin of safety for any Technical Specification.
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PLANT CHANGE / Mon!FICATIO?, 20-122                  PC/M CLASSIFICATION:                                               NS UNIT:     4 IMPLEMENTED:                                         05-26-83

==SUMMARY==
DATE:                                             09-09-83 REVISION:     1 CONp"! SATE STORAGE TANK PIPING AND STRUCTURAL MODIFICATION-Sammary:
This PC/M con"-rts the CST to a covered gas tight tank. To minimize aeration, the CST will utiliz- a N2 blanket.
Safety Evaluation:
The prob:bility of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been incre sed. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it .can be concluded that this PC/M does not pose any unreviewed safety questions.
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I   PLANT CHANGE /MODIFIC.i-'ON 30-124_                       PC/M CLASSIFICATION:       NS UNIT:     3 p
IMPLEMENTED:     12-01-83 TURNED OVER DATE:    12-06-83

==SUMMARY==
DATE:     12-08-83 l                                                                         REVISION:       1 HHSI REFUELING ISOLATION VALVE Summary:
This PC/M added an isolation valve to the line from the Unit 3 RWST to the 3 A and 3D HHSI pumps' suction. This will enable isolation of the Unit 3 MHSI pumps from the RWST without taking them out of service.
                                     <                :/
Safety Evaluation:
I This valve will be closed on,1y during outages and otherwise locked open. Flow restriction through the valve is negligible.' In light of this, no probability or consequences of any acciderit or equipment me.lfunction, previously evaluated in the FSAR are created or increased by the adding of this valve to the Safety Injection System.
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PLANT CHANGE / MODIFICATION 80-126               PC/M CLASSIFICATION:          NS UNIT:     3 IMPLEMENTED:       03-04-82 TURNED OVER DATE:         11-02-83
                                             ~

==SUMMARY==
DATE:       11-07-33 REVISION:         1 STEAM FLOW TRANSMITTER MODIFICATION - UNIT 3 Summary:
The supports and location of the main steam flow transmitters, FT-4-474, 475, and 495, and their corresponding pressure tubing were modified. The purpose of this modification was to increase the load carrying capacity to minimize damage during a seismic event.
Safety Evaluation:
This modification is nuclear safety related because the main steam lines are safety related systems. It did not present an unreviewed safety question because it did not increase the possibility of any accident addressed in the FSAR, or present any new accident not addressed in the FSAR, nor decrease the margin of safety for any Technical Specification.

PLANT CHANGE / MODIFICATION 80-t36            PC/M CLASSIFICATION:              NS UNIT:          4 IMPLEMENTED:         05/26/83 TURNED OVER DATE:          09-23-83

==SUMMARY==
DATE:          09-26-83 REVISION:            O CONTAINMENT SPRAY SYSTEM MODFICATION Summary:
This modification consisted in replacing all 3-bolts and most U-bolts with structural shapes and special U-straps and welded to existing structural steel supports. This is to comply with NRC LE. Bulletin 79-14.
Saft.tv Evaluation:
This change does not present an unreviewed safety question since it does not affect any accident addressed in the FSAR, present any new accident not previously analyzed in the FSAR; nor affect the margin of safety for any Technical Specification.
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PLANT CHANGE / MODIFICATION 80-143 -             PC/M CLASSIFICATION:                        NNS UNIT:            3&4 IMPLEMENTED:                    Il-19-83 TURNED OVER DATE:                      11-29-83

==SUMMARY==
DATE:                     12-01-83 REVISION:                     1
       - WASTE EVAPORATOR PACKAGE REMOVAL
       ' Summary:
This PC/M removes the Waste Evaporator package ~ from the Aux. Building and reroutes the process lines to the radwaste holdup tank. This will make room for the containment hydrogen system and the addition of the PASS.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be conclu'd ed that this PC/M does not pose any unreviewed safety questions.
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PLANT CHANG 5/ MODIFICATION 30-144              PC/M CLASSIFICATION:             NS UNIT:        3 IMPLEMENTED:        03-04-82 TURNED OVER DATE:           11-02-83

==SUMMARY==
DATE:         11-07-33 REVISION:         1 MODIFY FEEDWATER LINE AT S/G "C" Summary:
This PC/M rerouted the feedwater piping at steam generator "C" in order to shorten the horizontal run into the steam generator. 'Ihe reroute of this pipe will help minimize the magnitude of the hydraulic transient loads which will help prevent snubber damage.
Safety Evaluation:
This change does not present an unreviewed safety question since it does not affect any accident addressed in the FSAR, present any new accident not previously analyzed in the   '
FSAR; nor affect the margin of safety for any Technical Specification.
The modifications described in the PC/M will minimize the magnitude of the hydraulic transient loads.
The supports described in the PC/M are not structurally attached to block walls.
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PLANT CHANGE / MODIFICATION 80-149            PC/M CLASSIFICATION:             NS UNIT:          3
      .                                                 IMPLEMENTED:       11-16-83 TURNED OVER DATE:         02-17-83

==SUMMARY==
DATE:       02-24-84 REVISION:          O CONTAINMENT AIR SAMPLE SYSTEM (UNIT 3)
Summary:
The function of the containment air sample system was to monitor containment air particulates and gases. The purpose for the system modifications was to reduce or eliminate the high repair rate problems being experienced with the existing ASCO solenoid valves.
Safety Evaluation:
These changes do not involve an unreviewed safety question because no accident involving the containment air sample system is discussed in the FSAR. This modification results in a containment air sample system designed, constructed nad tested to the same or upgraded codes and standards as the original system. Therefore, no accident discussed in the FSAR would be made more severe.

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                                                                                                    .   .s REVISION:                     0 FEEDWhTER WARM-UP LINE MODIFTCATION Summar :                                          .
Tnis modifica. tion involves. the replaceme.nt of Unir'I feedwater warm-uc line =icint removed by PC/M 30-ISL and. changes to the pipe succor:s. Scecifically, the cice su=cor-modifications require a new anchor, the addition of nu:r to arr existing 'L" bel; and ne-rcelacement of :hree supoorts with a. higher cacacity design. Addi:ionally, rvo existinr succor:s are :o be removed as direc:ed by 3'.11195.
Safcw Evaluation:
nts enanze :td not oresent an unreviewed safe:v cuestion since it does not affec any ac:! dent accressed in :he 25AR, cresen: any new accident not previously analyzed in ne 25AR. nor affec :he margin of safety for any Technical Scecification. Tne mocifica-i:ns
:escribed allowed :ne system :o be coera-lonal during :hermal :ransients anc following a design basis earthquake. The supports described were not structurally at acnec :o block walls.
he feedwa:er warm _2m 'ine Sicir.s between ?.e feed' vater and -he !!.s valve is
::nsicerec hizr enerzy anc as sucr ecuires a Oi:e racture evalua-ion. Since - e r:u in is si-dar :: :. .e :revi:us r:u-ing, - .ere a e : new adverse effects.
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PLANT CHANGE / MODIFICATION 80-155             PC/M CLASSIFICATION:              NS UNIT:           4 IMPLEMENTED:         07-08-83

==SUMMARY==
DATE:           08-15-83 REVISION:           0 FEEDWATER WARM-UP LINE MODIFICATION Summary:
A new anchor and a restraint are required. Three existing hangers are to be replaced by Bechtel supports. 5177-156-H420-01, 5177-156-H420-02, and 5177-156-H420-03. Two existing supports are *o be removed as directed by SMI 196.
Safety Evaluation:
This change does not rcesent an unreviewed safety question since it does not " affect any accident addressed in the FSAR, present any new accident not previously analyzed in the FSAR; nor affect the margin of safety for any Technical Specification.
The modificaiotn described will allow the system to be operational during thermal transients and following a design basis earthquake.
The supports described are not structurally attached to block walls. The feedwater warm-up line piping between the feedwater and the first valve is considered high energy and as such requires a pipe rupture evaluation. Since the routing has not changed, there are no new adverse effects.
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PLANT CHANGE / MODIFICATION 80-170                             PC/M CLASSIFICATION:                                                 NS UNIT:            4 IMPLEMENTED:                                     05-02-83

==SUMMARY==
DATE:                                       08-18-83 REVISION:                            1 NIS CABLE REPLACEMENT Summary:
This PC/M replaced the following NIS excore instrumentation system cables: 1) Source Range, 2) Intermediate Range and 3) Power Range. Cable connectors were replaced also by new amphenol connectors.
Safety Evaluation:
The replacement of the triaxial NIS excore mstrumentation system cable as desc-ibed in the PC/M does not increase the probability of an accident, equipment malfunction or consequence thereof. This change does not affect or change the original operational intent of the system. No margin of safety previously evaluated is reduced. Tne triaxial cable is merely being replaced by cable better qualified for the environmental condition.
This change does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 81-07              PC/M CLASSIFICATION:              NS UNIT:          4        ,.
                                               ..        IMPLEMENTED:         06-07-83

==SUMMARY==
DATE:          07-22-83 REVISION:          1 ADDITION OF MECHANICAL STOPS FOR PURGE VALVES Summary:
This PC/M adds mechanicai stops in the actuators of the containment purge valves. These stops limit the purge supply valves to an opening of 33       and the exhaust valves to an opening of 30 . This is the result of an NRC directive.-
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.

                                                                                                 ^
PC/M CLASSIFICATION                 NS PLANT CHANGE /MODUrICATION 8148__            '
UNIT:            3 IMPLEMENTED:
83 TURNED OVER DATE:            02-01-84

==SUMMARY==
DATE:           02 01-84 REVISION:              1 Ff5L.Acousxy op ppewym'R LEVEL TRANSMITTER Summary:
This PC/M allowed existing pressurizer level transmitters to be placed with units qualified per IEEE-3231974 and IEEE-3441975. The reason for this change was FPL's com to NRC Bulletin 79-01B.
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Efaty Evaksation:
This PC/M does not involve an unreviewed safety question because the replacement of the pressurizer level transmitters does not affect any other safety related equipment.
These leve1 transmitters will not be installed on or adjacent to any " block" walls.
This replacement will have no effect on the containment heat sinks and, therefore, no effect on Appendix K ECCS analysis.
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PC/M CLASSIFICATIONI                            NS PLANT CHANGE / MODIFICATION 81-10 UNIT:                         4 IMi>LEMENTED:                       05-09-83

==SUMMARY==
DATE:                        07-22-83 REVISION:                          1 MODIFY PEEDWATER LINE AT S/G C Summary:
                                              ~
This PC/M involves the rerouting of the feedwater piping which will shorten the horizontal piping run so as to minimize the magnitude of hydraulic transient loads. These transient loads have presumably damaged the feedwater snubbers on line C.
Safety Evaluation:
This PC/M is nuclear safety related and will minimize the magnitude of the hydraulic transient loads. This change does not present an unreviewed safety question since it does not affect any accident addressed in the FSAR, present any new accident not previously
   -analyzed in the .FSAR, ner affect the margin of safety for any Tech. Spec. for supports and piping installed inside containment. There is no appreciable effect on the heat sink calculations. The re-analysis has provided new stress levels upon which to base the location of postulated pipe breaks. There are no whip restraints on this line but the effects of pipe whip or Jet impingement are considered insufficient to jeopirdize safe shutdown.

PLANT CHANGE / MODIFICATION 31-11               PC/M CLASSIFICATION:              NS UNIT:          3 IMPLEMENTED:          12-30-83 TURNED OVER DATE:            02-27-84

==SUMMARY==
DATE:          03-01-84 REVISION:           0 PRESSURIZER RELIEF TANK DRAIN MODIFICATIONS Summary:
The function.of the pressurizer relief tank drain modification shall be to prolong RCDT pump life and eliminate or reduce excess wastes of good reactor coolant.
Safety Evaluation:
These changes do not involve an unreviewed safety question because no accident involving tne liquid waste disposal system is discussed in the FSAR. This modification results in a
' liquid waste disposal system designed, constructed, and tested to the same or upgraded codes and standards as the original system. Therefore, no accident discussed in the FSAR would be made more severe, and the possibility of a breakdown or malfunction of equipment important to safety has not been increased, and the consequences of malfunction of equipment important to safety are no more severe than previous!y evaluated in the FSAR.

F PLANT. CHANGE /\10DIFICATION 81-17               PC/M CLASSTFICATTO-         ___ NNS V
UNIT:       3&4 IMPLEMENTED:         03-26-33 TURNED OVER DATE:           10-07-83

==SUMMARY==
DATE:          10-12-83 REVISION:          1 4160V SWITCHGEAR CONCRETE REPAIR
    . Summary:
This PC/M modified expansion joints between concrete slabs in the 4160 Switchgear Room. This modification will preclude further expansion ~-related damage to area concrete. In addition, repairs were made to already damaged concrete in the .U4 Switchgear Room.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of e.luipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those
      . previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
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PLANT CHANGE / MODIFICATION 81-20               PC/M CLASSIFICATION:             NNS UNIT:       3&4 IMPLEMENTED:          07-21-83

==SUMMARY==
DATE:           08-04-33 REVISION:           0 ACCESS AND DRESS FACILITY POTABLE WATER SUPPLY Summary:
This modification provided adequate flow of potable water to supply the plumbing fixtures in the access and dress facility from an existing 3" service water line located by the east wall of the Auxiliary Building.
Safety Evaluation:
The potable water supply line to the access and dress facility does not perform a safety function and it is either away or separated from safety related systems and equipment.
The probability of occurrence or the consequences of a design basis accident or malfunction of equipment important to the safety of the plant, previously evaluated in :he FSAR, has not been increased. There is no possibility of accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questiens.
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PLANT CHANGE / MODIFICATION 81-24                PC/M CLASSIFICATION:         NNS-OAOC UNIT:       3&4 IMPLEMENTED:          10-21-83 TURNED OVER DATE:            11-02-83

==SUMMARY==
DATE:           11-08-83 REVISION:           0 ADD FIRE DETECTORS: 3B AND 4B 4160 VOLT SWITCHGEAR ROOM Summary:
This modification consisted in the installation of additionalionization fire detectors in the 3B and 4B 4160V switchgear rooms mounted on the ceiling. The installation of detectors was done in accordance with the original design requirements.
The locations of existing detectors did not effectively detect fires involving 3B and 2B ai60V switchgcar. Additional detectors were installed to provide expanded automatic detection of fire in the 4160V switchgear rooms.
Safety Evaluation:
This modification is non-nuclear safety related with no unreviewed safety question. The probability of malfunction / accident previously addressed in the FSAR was not increased nor was the margin of safety as defined in the basis for any Technical Specification affected.

PLANT CHANGE / MODIFICATION 81-29                 PC/Ni CLASSIFICATION:             NS UNIT:           3 IMPLEMENTED:         Il-02-83 TURNED OVER DATE:           11-23-33

==SUMMARY==
DATE:          11-30-83 REVISION:           0 PRESSURIZER HEATER KEYLOCK SWITCH - UNIT //3 Summary:
A keylock switch will be installed on the' pressurizer heaters feeder breaker control circuit in order to return pressurizer back-up group "B" heaters to service following loss of off-site power. This PC/M will prevent the lifting of the control circuit leads which is hazardous to personnel and time consuming.
Safety Evaluation:
The installation of the keylock switch is not considered an unreviewed safety question because the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR has not been increased, the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR has not been created, the margin of safety as defined in the basis for Technical Specification has not been decreased. This modification will simplify operating procedures and increase the margin of safety by adding reliability to the breaker control circuit. The keylock switch will be qualified as Class IE equipment.

PLANT CHANGE / MODIFICATION 8130                     PC/M CLASSIFICATION:                            NS UNIT:                  4 IMPLEMENTED:     04-20-84 TURNED OVER DATE:             05-23-84 SUMM ARY D ATE:   05-30 84 REVISION:                 O PRESSURIZER HEATER KEYLOCK SWITCH - UNIT M Summary:
A keylock switch will be installed on the pressurizer heaters feeder breaker control circuit in order to return pressurizer back-up group "B" heaters to service following loss of off-site power. This PC/M will prevent the lifting of the control circuit leads which is hazardous to personnel and time consuming.
Safety Evaluation:
The installation of the keylock switch is not considered an.unreviewed safety question because the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR has not been increased.
the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR has not been created, the margin of safety as defined in the basis for Technical Specification has not been decreased. This modification will simplify operating procedures and increase the margin of safety by adding reliability to the breaker control circuit. The keylock switch will be qualified as Class IE equipment.
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PLANT CHANGE / MODIFICATION 81-45                PC/M CLASSIFICATION:            NNS UNIT:      3&4 IMPLEMENTED:        11-14-83 TURNED OVER DATE:          11-29-33

==SUMMARY==
DATE:        12-01-83 REVISION:        0 DRY STORAGE WAREHOUSE FIREWATER AND SERVICE AIR SUPPLY Summary:
This PC/M is extending the existing plant 10" fire main to supply the new dry storage warehouse. This will supply a sprinkler system and two fire hydrants. The PC/M also extends the service air supply from the auxiliary building to the warehouse.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
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PLANT CHANGE / MODIFICATION 81-56               PC/M CLASSIFICATION:             NS            i UNIT:          3 IMPLEMENTED:         Generic TURNED OVER DATE:           05-19-83

==SUMMARY==
DATE:          09-23-83 REVISION:           0 Fm Power %_-ly Test Point Summary:
The modification performed at this time consisted in installing a spare power supply serial
#A0359 to the Hagan power supplies. Since this is a generic plant change modification subsequent reports will follow detailing the work perforrned.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety questions. Tne probability of occurrence or consequence of an accident or malfunction of eculpment important to safety previously evaluated in the FSAR has not increased.

PC/M CLASSIFICATION:            NS PLANT CHANGE / MODIFICATION 81-71 UNIT:       3&4 IMPLEMENTED:       12-30-83 TURNED OVER DATE:          02-01 84

==SUMMARY==
DATE:        02-01 84 REVISION:         1 REACTOR CAVTTY AND TRANSFER CANAL LINER REPAIRS Summary:
The purpose of this design package was for the application of a weld seam sealant on all seam welds, plug welds, and any other linear interruptions which from inspection are in need of repair.
Safety Evahastion:
No accident previously evaluated in the FSAR involves rupture or leakage through the reactor cavity and transfer canal liner; therefore, the possibility of occurrence of an accident previously evaluated in the FSAR does not increase.

CPWO PLANT CHANGE / MODIFICATION          81-73      PC/M CLASSIFICATION:            NS UNIT:     3 and 4 IMPLEMENTED:        12-08-83 TURNED OVER DATE:          03-13-34

==SUMMARY==
DATE:         03-I6-84 REVISION:          O SERVICE AIR CHECK VALVE #205 REPLACEMENT Summary:
The modification involved the replacing of an existing service air check valve #205 which was leaking. However, the valve manufacturer was not on the Florida Power and Light QA approval list, therefore, it was replaced with one from an approved vendor (Rockwell Edward).
Safety Evaluation:
This change does not involve an unreviewed safety question because it does not affect or increase the probability nor the consequences of any accident or equipment malfunction previously evaluated in the FSAR and, it does not create the possibility of malfunction of equipment not considered in Chapter 14 of the FSAR. Also, this change does not decrease any margin of safety discussed in the Technical Specification basis.

CPWO PLANT CHANGE / MODIFICATION 81-77               PC/M CLASSIFICATION:               NSS UNIT:            3 IMPLEMENTED:          03-01-82

==SUMMARY==
DATE:           05-24-83 REVISION:            0.     )
1 ADDITIONAL 480 V POWER FOR TEMPORARY TRAILERS Summary:                                   ,
This modification disconnected the screen wash pump motor supply leads for the #3 pump so the breaker could be utilized as a temporary supply for support trailers. MCC "3E" breaker 30913 will be utilized to supply a distribution tranformer which will power the HP trailer and other temporary trailers.
Safety Evaluation:
This change is non-safety related because the work performed did not affect any safety related component or equipment as described in the FSAR. No additional hazards or potential mailunctions have been created. Therefore, it can be concluded that it has no unreviewed safety question.

PUNT CHANGE / MODIFICATION 81-31                 PC/M CLASSIFICATION                                NS UNIT:            3 IMPLEMENTED:           12-17-83 TURNED OVER DATE:                          01-Oc-84

==SUMMARY==
DATE:                   01-09-84 REVISION:            I W-2 SWITCH REPLACEMENT Summary:
This PC/M replaced W-2 switches for new electroswitches which.were qualified to IEEE 323-1974 and IEEE-344-1975 and required no functional circuit changes and their contact operation is similar to the old W-2 switches.
Safety Evakaatlan The switch replacement will require no functional circuit alterations and the new switch operation is similar to the existin6 switch. Therefore, this replacement does not increase the possibility of an accident or equipment malfunction important to the safety of the plant previously evaluated in the FSAR. There is no possibility of accident or malfunction different than those evaluated; therefore, this PC/M does not generate an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 31-32                           PC/M CLASSIFICATION:           NS UNIT:         a IMPLEMENTED:         06-21                                                                               

==SUMMARY==
DATE:        08-23-83 REVISION:          2 W-2 SWTTCH REPLACEMENT Summarvt                                                                                              1 The new switches are to be seismic vibration tested in order to insure that the switch
          ' remains functional and does not become detached from the control panels during the maximum seismic event described in Appendix 5A of Turkey Point Units 3 & 4 FSAR.
Since the test mounting conditions will not exactly match actual conditions, the test response spectrum should envelope the spectrum curves specified in the FSAR ampilfied by a factor of 1.5. These switches are considered nuclear safety related Class IE and, therefore, require environmental qualification to IEEE 323-1974 and seismic qualification to IEEE 344-1975.
Safety Evaluation:
The new electroswiten switches are classified Class 1E nuclear safety related and are to meet IEEE 323-1974 and IEEE 344-1975. The switch replacement will require no 1
functional circuit alterations and the new switen operation is similar to the existing -
switches.                     Therefore, the replacement of the W-2 switches with the electroswiten switches does not increase the possibility of an accident or equioment malfunction important to the safety of the plant, previously evaluated in the FSAR. There is no possibility of accident or malfunction different than those previously evaluatec: no margin of safety as defined in the Bases for any Tecnnical Specification is recuced. Tnerefore.
this PC/M does not generate ar. unreviewec safety question.
I

PLANT CHANGE / MODIFICATION 81-87               PC/M CLASSIFICATION:              NNS UNIT:        3&a IMPLEMENTED:          06-23-83

==SUMMARY==
DATE:           07-22-83 REVISION:            0 RAB SCAFFOLDING RACKS Summary:
This modification consisted in installing scaffolding racks for proper storage of temporary work scaffolding and guards for hydrogen and nitrogen pipelines adjacent to the rack locations. The racks were installed on the roof of the auxillary building.
Safety Evahastion:
The RAB scaffolding racks do not perform a safety function and they are either away or separated from. safety related systems and equipment.
The probability of occurrence or the consequences of a design basis accicent or malfunction of equipment important to the safety of the plant, previously evaluated in :ne FSAR, has not been increased. There is no possibility of accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does no:
pose any unreviewed safety questions.
l

FC ''.' CLASSIFICATION:          NS PLANT CHANGE / MODIFICATION SI 92 UNIT:        3&4 IMPLEMENTED:       09-22-83 TURNED OVER DATE:           10-07-83

==SUMMARY==
DATE:         !0-12-33 REVISION:          1 EMERGENCY DIESEL GENERATOR ENCLOSURE LOUVERS Summar :                                 -
This modification consisted of installing additional fixed louvers behind existing intake louvers of diesel generator enclosures including flashing anchors and fasteners, etc. to
   . reduce penetration of wind driven rain water. These additional touvers did not add enough
:o the static pressure for the exhaust fan to change the specified cooling air flow and hence did not effect the safety related equipment. The new louvers were attached in existing diesei generator enclosure openings. However, the louvers were to reinforce concrete and not to affect the structuralintegrity of the block walls.
Safety Evaluation:
The addi:lonal louvers will not have any effect on Chapter 14 of the FSAR. The icuvers and louver supports have been designed for 120 MPH winds in accordaneg uith South Florida Building Code. In addition, louver supports have been designed for maximum For the above reason, :he earthquake in accordance with Turkey Point FSAR.
consequences of an accident previously analyzed in the FSAR would not be altered. As these are fixed louve-s, therefore no equipment is involved and does not effect the FSAR.
In addition, :his change cannot increase consequences of a malfunction previously evaluated in the FSAR. Now this modification does not change the operating func:!cn or condition, or effec; the safety related equipment. Therefore, this change would no:
create the possibility of an accident not considered in the FSAR. For :he above reasons.
the modification would not decrease any margin of safety. Tnerefore. the modifica::en does not pose an unreviewed safety question.

 '                                                         FC/M CLASSIFICATION:          NS FLANT CHANGE / MODIFICATION S1-93 UNIT:       3&4 IMPLEMENTED:      09-27-83
                                                            . TURNED OVER DATE:       10-07-S3

==SUMMARY==
DATE:        10-20-33 REVISION:         0 ADDITION OF NEW TRAYS AND WIREWAYS IN THE CABLE SPREADING ROOM Summary:
This PC/M provided additional raceway systems to accommodate new cabling associated with TMI lessons learned and safety assessment systems as well as ongoing miscellaneous p! ant modifications.
Safety Evaluation:
T.!s - odification is nuclear safety related with no unreviewed safety question. With no
         ; ::asility or consequences of an accident or malfunction increasing as ' previously eva;usted in the FSAR. No margin of safety as defined in the basis for any Technical 5:ecificati:n is affected.
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PLANT CHANGE / MODIFICATION i .              -_         PC/M CLASSIFICATION:      NNS-CA/OC UNIT:       3 IMPLEMENTED:        10-24-83 TURNEITOVER DATE:         10-22-S3

==SUMMARY==
DATE:         10-26-33 REVISION:       0 NEW FUEL STORAGE RACKS HANDRAILS Summary:                                                                       .,
The. operating level of both the Units 3 and 4 new fuel storage areas had no safety railings at the outside edge of the fuel element support racks. This was a potential safety hazard during the loading, inspection, or any other time pers6nnel required to be on these new assemblies near the outer edges of the fuel storag'e racks. This change covers the installation of safety rails at the above mentioned areas.
m Safety Evaluation:                                                                        '
Tne new fuel st r' age rack handrails do not perform a safeiy function. However, in order to preclude impact on the new fuel storage racks, all components have been checked to withstand the maximum seismic loading (E') as specified in the Design Basis.                T .e probability of occurrence or the consequence of a design basis accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than these previously evaluated. Therefore, it can be concluded that this PC/M does not pese any
                                                  ~
unreviewed safety question.
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?LANT CHANGE / MODIFICATION St-95                 PC/M CLASSIFICATION:            NNS-C A /OC UNIT:           4 IMPLEMENTED:             10-24-83 TURNED OVER DATE:               10-2c-83

==SUMMARY==
DATE:               10-26-83 REVISION:           0 NEW FUEL STORAGE RACKS HANDRAILS Summary:
Tne operating level of both the Units 3 and 4 new fuel storage areas had no safety railings at the outside edge of the fuel element support racks. This was a potential safety hazard during the loading, inspection, or any other time personnel required to be on these new assemblies near the outer edges of the fuel storage racks. This change covers the installation of safety rails at the above mentioned areas.
Safety Evaluation:
3e new fuel storage rack handrails do not perform a safety function. However, in order to preclude impact on the new fuel storage racks, all components have been checked to withstand the maximum seismic loading (E') as specified in the Design Basis.                 Tne probability of occurrence or the consequence of a design basis accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not.
been increased. There is no possibility of an accident or malfunction different than these previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety question.

PLANT CHANGE / MODIFICATION           81-98     PC/M CLASSIFICATION:           NS UNIT:        3 IMPLEMENTED:       0I-t2-84     i TURNED OVER DATE:         03-21-84

==SUMMARY==
DATE:         03-26-84 REVISION:         O' l
CHARCOAL PILTER THERMOCOUPLE REPLACEMENT Summary:                                  .                        .
This PC/M replaced the charcoal filter thermocouples with qualified resistance temperature detectors. It also replaced the recorder on VP 'B' with one suitable for RTD input.
Safety Evaluation:
This change is nuclear safety related but does not involve an unreviewed safety question because these RTDs will monitor Emergency Containment Filter Temperature during the
      \tHA. They are fully qualified to IEEE-323 and 344 b
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PLANT CHANGE / MODIFICATION 81-99              PC/M CLASSIFICATION:            NS UNIT:        4 IMPLEMENTED:       05-26-83 TURNED OVER DATE:         11-23-83

==SUMMARY==
DATE:        11-29-83 REVISION:         2 CHARCOAL FILTER THERMOCOUPLE REPLACEMENT - UNIT 4 Summary:
This PC/M consists of the replacement of the existing thermocouples for the emergency containment charcoal filters and coolers by qualified resistance temperature detectors.
These RTDs will be located in protection tubes installed in the new charcoal filter traps by the charcoal tray manufacturer.
Safety Evaluation:
This PC/M does not involve an unreviewed safety question because it will not affect :: e functions of any other safety system. 'the replacement of the existing charcoal filter trays and the replacement of the filter and cooler thermocouples with the qualified resistance temperature detectors will have no effect on the containment heat sink anc '
therefore, no effect on the Appendix K, ECCS analysis.
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PC: M CLASSIFICATION:            NNS PLANT CHANGE / MODIFICATION 81-108 UNIT:          3 IMPLEMENTED:          12-04-83 TURNED OVER DATE:           12-15-83

==SUMMARY==
DATE:           12-16-83 REVISION:           O CONTAINMENT EVACUATION ALARM MODIFICATION Summary:
This change installed a 2 second time delay relay on the containment evacuation alarm automatic initiation feature. The time delay will prevent spurious. electrical noise on the SR Nuclear Instruments from actuating the alarm.
Safety Evaluation:
   'ihis PC/M is not nuclear safety related and does not involve an unreviewed safety question because the containment evacuation alarm is not required for safe shutdown of
   -he reactor or to mitigate the consequences of an accident.

i PLANT CHANGE / MODIFICATION 81-140                 PC/M CLA55fFICATION:         NNS UNIT:        4 IMPLEM ENTED:      04-20-84 TURNED OVER DATE:        05-21-84

==SUMMARY==
DATE:        06-04-34 REVISION:         0 INSTALLATION OF NEW REACTOR HEAD O-RING CLIPS Summary:
This PC/M installed the new reactor head 0-ring clips.         Two 0-ring gaskets form a positive seal between the reactor head and shell, thus ensuring that no leakage of primary coolant occurs. Twelve wire clips hold each 0-ring to the reactor head while the latter is being lowered into the reactor vessel, and while it is being lifted off. Once the head is seated on the shell, the clips serve no function.
Safety Evaluation:
Since these clips are needed only when the reactor is in a shutdown condition and the closure head removed, the 0-ring spring clips have no role in maintaining the reactor coolant pressure boundary. They do not contribute to the prevention or mitigation of the consequences comparable to those cited in 10 CFR 100.11. For these reasons, installation of the clips is classi'fied as non-nuclear safety related and does not pose an unreviewed s safety question.

PLANT CHANGE / MODIFICATION 81-147                  PC/M CLASSIFICATION:       NS UNIT:-     3 IMPLEMENTED:     01-04-84 TURNED OVER DATE:      02-27-84

==SUMMARY==
DATE:      03-01-84 REVISION:      0 INSTALL OUALIFIED CONNECTORS FOR SOLENOID VALVES AND INSTRUMENTS Summary:
This change installed CONAX seal assemblies on the penetration to all safety related solenoid valves and instruments located in environmentally hazardous areas.
Safety Evaluation:
This change is nuclear safety related but does not involve an unreviewed safety question because these connectors are used on instruments which input to the protection anc safeguards systems. These connectors ensure that the instrument qualification to harsn environments is maintained and, therefore, improves the margin of safety affectec by equipment failure.
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PLANT CHANGE / MODIFICATION 81-150                 PC/M CLASSIFICATION:              NS UNIT:          3 IMPLEMENTED:         12-05-83 TURNED OVER DATE:           12-15-S3

==SUMMARY==
DATE:           12-16-83
                                                                                                      ^
REVISION:           0 PERSONNEL DOOR INTERLOCK ANNUNCIATION Summary:                                                 -
This change added limit switches to the personnel air lock doors to actuate the " Personnel Door Interlock Violated" annunciator if both air lock doors are opened.
  - Safety Evaluation:       .
Tnis change is nuclear safety related because an additional electrical penetration was added to the personnel air lock. It does not involve an unreviewed safety question because the additional penetration is fully class 1E qualified and the air lock structural strength is unaffected.
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PLANT CHANGE / MODIFICATION 81-152                PC/M CLASSTFICATTON:                      NS UNIT:                     3 IMPLEMENTED:               12-lh-33
   ,                                                  TURNED OVER D ATE:               03-13-SL

==SUMMARY==
D AT .:            03-16-30 REVISION:                     !
HIGH MEAD SAFETY IN3ECTION PUMP RECIRCULATION LINES Summary:
Tnis PC/M provided a new test recirculation line for each High head safety injection pump. These new test lines were needed to allow each pump to be tested at its design flow and pressure. Previously the pump was tested at close to shutoff head through a mini recirculation line.
Safety Evaluation:
This modification does not involve an unreviewed safety question because the system is fully redundant, not normally pressurized, no active components have been added to the SI System, and the new recire lines are normally isolated.
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PC/M CLASSIFICATION:       NS PLANT CHANGE / MODIFICATION 81-153 UNIT:       4 IMPLEMENTED:     12-14-83 TURNED OVER DATE:      02-01-84

==SUMMARY==
DATE:      02-01-84 REVISION:       0 MIGH HEAD SAFETY IN3ECTION PUMP RECIRCULATION LINES Summary:
This PC/M provided a new test recirculation line for each high head safety injection pump. These new test lines were needed to allow each pump to be tested at its design flow and pressure. Previously the pump was tested at close to shutoff h'ead through a mini recirculation line.
Safety Evaluation:
This modification does not involve an unreviewed safety question because the system is fully redundant, not normally pressurized, no active components have been added to the SI System, and the new recire lines are normally isolated.
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PC/M CLASSTFICATf0N:             NS PLANT CHANGE / MODIFICATION _ S1-169 UNTT:         3 ISPLEMENTED:         01-OL-Su TURNED OVER DATE:           03-13-S:.

==SUMMARY==
DATE:          03-!6-83.
REVISION:          S REMOVAL OF PZR INSTR. HEATER CUBICLES AND RELOCATION OF EQUIPMENT Summary:
The plant is switching to a type of pressure transmitter not requiring a heated cubicle for proper operation.      Another PC/M (31-09) governs the installation of these new transmitters while this PC/M removes the old ones.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
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PLANT CHANGE / MODIFICATION 82-02               PC/M CLASSIFICATION:           NNS OA/OC UNIT:            4 IMPLEMENTED:            10-15-83 TURNED OVER DATE:            01-09-84

==SUMMARY==
DATE:             01-09-84 REVISION:             1 NITROGEN BACK-UP FOR MAIN STEAM DUMP TO ATMOSPHERE VALVES Summary:
A nitrogen back-up was provided to the steam dump to atmosphere valves and the associated hand controllers located in the Control Room. .This provided an alternate source of air supply to the valves ard controller in the event of loss of all A.C. power.
Safety Evaluation:
The probability of occurrence or the consequences of a design basis accident or malfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. This PC/M does not reduce the margin of safety previously defined in the FSAR or Technical Specifications. Based on the above, it can be concluded that this PC/M is non-safety related and does not pose an unreviewed safety question.

PC/M CLASSI:ICATION:                NS PLANT CHANGE / MODIFICATION 82-05A UNIT:           3 IMPLEMENTED:           12-07-53 TURNED OVER DA~E:             :2-:5-!3
                          ~

==SUMMARY==
DATE:             '2-19-53 REVISION:            :
MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER LE.
79-14, PROBLEM CCW-02 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Con- :.
System outside containmer.t to comply witn NRC LE. Bulletin 79-14 Safety Evaluation:
Tnis modification is nuclear safety related witn no unreviewed safetv cues-ion.
                                                                                            'e nodification and analysis has ensured that the design :-iteria of tne origina. :!:.ng sys e-design documents have been me and no acciden or malfunc; ion cro:a:!!!- ; .:reasec.
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PLANT CHANGE / MODIFICATION 82.47A                     PC/M CLASSIFICATION:              NS UNIT:             3 IMPLEMENTED:            12-20-83 TURNED OVER DATE:             01-06-84

==SUMMARY==
DATE:             01-09-84 REVISION:              0 MODIFICATION TO CVCS SYSTEM (LC.) PER LE. 79-14 (PROBLEM 0-24)
Summary:
PC/M consisted in modifying the pipe supports for the Chemical and Volume Control System inside containment to comply with NRC !.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety cuestion.                The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-08               PC/M CLA5i ": ATION:                NS UNIT:           3 IMPLEMENTED:            11-29-83 TURNED OVER DATE:              12-08-83

==SUMMARY==
DATE:              12-08-83 REVISION:            0 MODIFICATION TO SAFETY IN3ECTI6N AND RESIDUAL HEAT REMOVAL SYSTEM (O.C.) PER LE. 79-14, PROBLEM CCW-10 Summary:                        -
This PC/M consisted in modifying the pipe supports on the Safety Injection and Residual Heat Removal System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PC/M CLASSIFICATION:                 NS PLANT CHANGE / MODIFICATION 82-09A UNIT:             3 IMPLEMENTED:            12-20-83 T.Q)tNED OVER DATE:           Oh-16-83
                                            ~

==SUMMARY==
DATE:            04-17-8u REVISION:              0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER LE_.
BULLETIN 79-14 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System (inside containment) to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-10A              PC/M CLASSI?ICATION:                  NS UNIT:            3 IMPLEMENTED:             11-16-33 TURNED OVER DATE:               11-23-83

==SUMMARY==
DATE:              !!-29-S3 REVISION:              0 MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.) FER 79-14 Summary:                                   .
This. change involve modification of the pipe supports to the Safety Injection and Residual Heat Removal System (inside containment) to meet the NRC I.E. Bulletin 79-14.
Safety Evaluation:
riteria of the original piping This modification system               andhave design documents   analysis    hasThis been met. ensured    that the design 'gs safety related b modification,_
involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 82-14A             PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTED:            12-30-83 TURNED OVER DATE:              02-01-84

==SUMMARY==
DATE:             02-02-84
                                      .                              REVISION:            0 MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.) PER LE. 79-14, PROBLEM 010
    . Summary:
This modification consisted in modifying the pipe supports in the Safety Injection and Residual Heat Removal System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82 5A               PC/M CLASSIFICATION:                          NS UNIT:               3 IMPLEMENTED:                    12-30-83 TURNED OVER DATE:                       03-13-84

==SUMMARY==
DATE:                    ,
03-15-84 REVISION:                  0 MODIFICATION TO THE REACTOR COOLANT SYSTEM (LC.) PER LE. 79-14, PROBLEM
. RTD1
                                               ~
Summary:
This PC/M consisted in modifying the pipe supports on the Reactor Coolant System Inside Containment to comply with NRC LE. Bulletin 79 14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                      The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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  - PLANT CHANGE / MODIFICATION 82-17A              PC/M CLASSIFICATION:                NS UNIT:          3 IMPLEMENTED:            12-07-83 TURNED OVER DATE:              12-20-83

==SUMMARY==
DATE:             12-20-83 REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. 79-14 Summary:
This PC/M consisted in modifying the pipe supports for the Component Cooling Tater System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
Tnis' modification is nuclear safety related with no unreviewed safety quest:en.           .,e moilification and analysis has ensured that the design criteria of the original piping sys e n design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-22                                     PC/M CLASSIFICATION:                               NS
 ,                                                                                                                UNIT:          3 IMPLEMENTED:                            01-30-84 TURNED OVER DATE:                             02-27-30       l

==SUMMARY==
DATE:                             03-01-Su REVISION:                    0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. 79-14 Summary:
                                                                                                                        ~
This PC/M consisted in modifying the pipe supp' orts on the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:                                                                                                     .
This modification is nuclear safety related with no unreviewed safety question.                                               Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-23A              PCi        SSIFICATION:             NS UNIT:           3 IMPLEMENTED:            11-17-83 TURNED OVER DATE:             !!-29-33

==SUMMARY==
DATE:             !!-3C-S3 REVISION:            0 MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER 79-14. PROBLEM RTD-2 Summary:
Tnis PC/M modified the pipe supports on the Reactor Coolant System inside con ainmen:
to comply with NRC LE. Bulletin 79-14 Safety Evaluation:
Tnis modification is nuclear safety related with no unreviewed safe:y cues-ion.            .e modification and analysis has ensured that :he design criteria of -he original piping sys e-design documents have been met and no accident or malfunction procabill:y increase .
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PLANT CHANGE / MODIFICATION 82-23B              PC/M CLASSIFICATION:                 NS UNIT:           3 IMPLEMENTED:            12-08-83 TURNED OVER DATE:              01-09-84

==SUMMARY==
DATE:             01-10-84 REVISION:             0 MODIP1 CATION TO MANIFOLD SYSTEM (LC.) PER LE. 79-14 Summary:
PC/M consisted in modifying the pipe supports f6r the Manifold System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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1 PLANT CHANGE / MODIFICATION' 82-23C                PC/M CLASSIFICATION:             NS UNIT:     3 IMPLEMENTED:    12-30-83 TURNED OVER DATE:            Oa-16-Su

==SUMMARY==
DATE:      04-!7-83 REVISION:      0
,  MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER LE. BULLETIN 79-14 Summary:
This PC/M consisted in modifying the pipe supports on the Reactor Coolant System (inside containment) to comely with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification.is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-24A              PC/M CLASSIFICATION:                                                          NS
                                             .                                                    UNIT:                             3 IMPLEMENTED:                                          12-03-83 TURNED OVER DATE:                                           01-09-84

==SUMMARY==
DATE:                                         01-10-34 REVISION:                             0 MODIFICATION TO C.C.W. SYSTEM (LC.) PER LE. 79-14                                                                                                           ,
Summary:
PC/M consisted in modifying the pipe supports for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                                                 The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-25A              PC/M CLASSIFICATION:                NS UNIT:            3 IMPLEMENTED:             12-03-83 TURNED OVER DATE:             01-09-84

==SUMMARY==
DATE:             01-10-84 REVISION:              0 MODIFICATION TO C.C.W. SYSTEM (LC.) PER LE 79-14 (PROBLEM CCW-018)
Summary:
PC/M consisted in modifying the pipe supports for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                 The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE ODIFICATION 82-26                                      PC/M CLASSIFICATION:              NS-UNIT:       3 IMPLEMENTED:            12-30-83 TURNED OVER DATE:             01-16-84

==SUMMARY==
DATE:             01-27-84 REVISION:       0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER LE. 79-14 Summary:
This modification consisted of modifying the pipe supports in the Chemical and Volume Control System inside containment to comply with NRC LE. Bulle' tin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-27A _            PC/M CLASSIFICATION:                                NS UNIT:                   3 IMPLEMENTED:                             11-17-83 TURNED OVER DATE:                               11-29-83

==SUMMARY==
DATE:                              11 30-83 REVISION:                   0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER 79-14 Summary:
This PC/M consisted'in modifying the pipe supports on the Chemical and Volume Control System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-28A                                                                                                     PC/M CLASSIFICATION:                                                                 NS UNIT:     3 IMPLEMENTED:                         12-14-83 TURNED OVER DATE:                                                      01-06-84

==SUMMARY==
DATE:                                  01-09-84 REVISION:     0 MODIFICATION TO C.C.W. SYSTEM (O.C.) PER LE. 79-14 Summary:
PC/M consisted in modifying the pipe supports for the Component Cooling Water System outside containmen; to comply with ,x-                                        NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related swith no unreviewed safety question.                                                                                                                                                  The modification and analysis has ensured that the :'esign criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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* PLANT CHANGE / MODIFICATION 82-29A              PC/M CLASSIFICATION:                NS UNIT:          3            ;
s            IMPLEMENTED:            12-03-83 TURNED OVER DATE:              12-20-33

==SUMMARY==
DATE:            12-20-33 REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER LE. 79-14 Summary:                                              ,
This PC/M consisted in modifying the pipe supports for the Chemical and Volume Control System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evalua' tion:
This modification is nuclear safety related with no unreviewed safety question.           Tr.e modification and analysis has ensured that the design criteria of the original piping system
-     design documents have been met and no accident or malfunction probability increased.

PC/M CLASSIFICATION:               NS PLANT CHANGE / MODIFICATION 82-37 UNIT:           3 IMPLEMENTED:             12-14-83 TURNED OVER DATE:              01-06-84

==SUMMARY==
DATE:              01-09-84 REVISION:           0 MODIFICATION TO MAIN STEAM TO RRURF VALVE SILENCER (O.C.) PER LE. 79-14 Summary:
PC/M consisted in modifying the pipe supports for the Main Steam to Relief Valve Silencer outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-38               PC '.i CLASSIFICATION:                               NS UNIT:                     3 IMPLEMENTED:                            12-20-83 TURNED OVER DATE:                               01-06-84

==SUMMARY==
DATE:                             01-09-84 REVISION:                     0 MODIFICATION TO MAIN FEEDWATER SYSTEM (LC.) PER LE. 79-14 Summary:
PC/M consisted in modifying the pipe supports for the Main Feedwater System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                   The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfuncti~on probability increased.
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PLANT CHANGE / MODIFICATION 82-39              PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTED:            11-16-83
                                                 . TURNED OVER DATE:            11-29-33

==SUMMARY==
DATE:             11-30-83 REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER 79-14 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control Systern outside containment to comply with NRC LE. Bulletin 79-14.         -
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-40A              PC/M CLASSIFICATION:               NS UNIT:          3 IMPLEMENTED:          12-03-83 TURNED OVER DATE:            12-20-83

==SUMMARY==
DATE:          12-20-83 REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. 79-14, PROBLEM CCW-32 Summary:
This PC/M consisted in modifying the pipe supports for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
l

' PLANT CHANGE / MODIFICATION 82-40B             PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTED:            12-07-83 TURNED OVER DATE:              12-20-83 l

==SUMMARY==
DATE:             12-20-83 REVISION:         -0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. 79-14 Summary:
This PC/M consisted in modifying the pipe supports for the Component Cooling Ta:er System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:_
Tnis modification is nuclear safety related with no unreviewed safety question.          T,e modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
e

PC/M CLASSIFICATION:                                               NS PLANT CHANGE / MODIFICATION 82-41 A UNIT:                                               3 IMPLEMENTED:                              01-19-84 TURNED OVER DATE:                                02-01-84

==SUMMARY==
DATE:                               02-02-84 REVISION:                                               0 h
MODFICATION TO WASTE DISPOSAL SYSTEM (LC.) PER LE. 79-14 Summary:
     -  This modification consisted irr modifying the pipe supports in the Waste Disposal System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:                                                                                              ,
This modification is nuclear safety related with no unreviewed safety question.                                                                                       The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
1 e
             .-.e. -
                     --n -

I PLANT CHANGE / MODIFICATION 82-41B              PC/M CLASSIFICATION:                NS UNIT:          3 IMPLEMENTED:            12-07-83 TURNED OVER DATE:              12-20-83

==SUMMARY==
DATE:             12-20-S3 REVISIDN:            0 MODIFICATION TO WASTE DISPOSAL SYSTEM (LC.) PER LE. 79-14
- Summary:
This PC/M consisted in modifying the pipe supports for the Waste Disposal System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety. related with no unreviewed safety question.          Tte modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased, O

l PLANT CHANGE /MODFICATION 82-42A                     PC/M CLASSIFICATION:                                                         NS          ,
UNIT:                       3 IMPLEMENTED:              12-20-83             l TURNED OVER DATE:                                   01-06-84

==SUMMARY==
DATE:              01-09-84 REVISION:                       0 MODFICATION TO CVCS SYSTEM (LC.) PER LE. 79-14 Summary:
PC/M consisted in modifying the pipe supports for the Chemical and Volume Control System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                                      The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
  ,--   -..--,n-              - ,,   . . n- ,       -- - - - -. - - , , - - - - - - - - - , - - - ,           -------n-.-.,-    . - - -        , ,-

PLANT CHANGE /MODIFIC.ccN 82-43A                PC/M CLASSIFICATION:                         NS UNIT:        3 IMPLEMENTED:               12-30-83 TURNED OVER DATE:                        01-16-84

==SUMMARY==
DATE:                      01-27-84 REVISION:                 0 MODIFICATION TO SAFETY IN3CTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.)
PER LE. 79-14 Summary:
This modification consisted of modifying the pipe supports in the Safety Injection and Residual Heat Removal System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This. modification is nuclear safety related with no unreviewed safety question.                              The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
I i
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1 I
PLANT CHANGE / MODIFICATION 82 44               PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTED:            01-04-84      !
TURNED OVER DATE:             01-16-84

==SUMMARY==
DATE:              01-27-84 REVISION:            0 A40DIFICATION TO SAFETY IN3CTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.)
PER LE. 79-14 Summary:
This modification consisted of modifying the pipe supports in the Safety Injection and Residual Heat Removal System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PC/M CLASSIFICATION:                        NS PLANT CHANGE / MODIFICATION 82-45A UNIT:                  3 IMPLEMENTED:               01-04-84 TURNED OVER DATE:                  02-27-84

==SUMMARY==
DATE:                03-01-84 REVISION:                    0           .
MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.) PER LE. 79-14, PROBLEM 015 Summary:
This PC/M consisted in _ modifying the pipe supports on the Safety Injection and Residual Heat Removal System inside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.               Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-50A              PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTEO:           02-06-34 TURNEO OVER DATE:              05-30-8a SUMM ARY DATE:            06-11-8a REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (I.C.) PER 79-14,                                l PROBLEM CCW   Summary:                                                                          ,
This PC/M consisted in modifying the pioe supoorts for the Component Cooling Water System inside containment to comoly with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related 'with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the origina! oiping system design documents have been met and no accident or malfunction orobability increased.
e a

PLANT CHANGE / MODIFICATION 82-51 A            PC/M CLASSIFICATION:                                              NS UNIT:     3 IMPLEMENTED:                                          12-08-83 TURNED OVER DATE:                                            01-09-84

==SUMMARY==
DATE:                                           01-10-84 REVISION:                      0 MODIFICATION TO C.C.W. SYSTEM (LC.) PER LE. 79-14 (PROBLEM CCW-31)
Summary:
PC/M consisted in modifying the pipe supporis for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                                      The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
'I k
1 -
                                                               - , - . _ - . _ _ _ , - - . - - - - - - - , ,            -.--.-----,m----,

I
   , PLANT CHANGE / MODIFICATION 82-51B                      PC/M CLASSIFICATION:        NS UNIT:      3 IMPLEMENTED:    12-30-83 TURNED OVER DATE:      02-01-84

==SUMMARY==
DATE:      02-10-84 REVISION:       0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. 79-14 Summary:
This modification consisted in modifying the pipe supports for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
1
                     .,...m.. . . - ,., _    , - . _.. _ - .        ,. .     ,                     , - . ,

PLANT CHANGE / MODIFICATION 52              PC/M CLASSIFICATION:          NS UNIT:        3 IMPLEMENTED:        10-18-83 TURNED OVER DATE:        11-28-83

==SUMMARY==
DATE:        11-30-83 REVISION:         0 MANIPULATOR CRANE MODIFICATION Summary:
This PC/M upgraded the manipulator crane for more reliable, safer, and efficient crane operation.
Safety Evaluation:
This PC/M will not increase the possibility or consequences of the accidents analyzed in the FSAR, nor does it create the possibility of a different accident or equipment malfunction. No margin of safety as defined in the bases for any Technical Specification is reduced.
                                                    ~

PLANT CHANGE / MODIFICATION 82-54A               PC/M CLASSIFICATION:               NS UNIT:           3 IMPLEMENTEO:            01-10-84 TURNED dVER OATE:             05 30 84 SUMM ARY DATE:           06-11-84 REVISION:             0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (I.C.) PER 79-14, PROBLEM CCW-29 Summary:
This PC/M consisted in modifying the pipe supports for the Component Cooling Water System inside containment to comply with NRC !.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original pioing system design documents have been met and no accident or malfunction probability increased.
e

PLANT CHANGE / MODIFICATION 32-55 A             PC/M CL A.SSIFTCATION:              NS UNIT:           4 IMPLEMENTED:            12-30-83 TURNED OVER DATE:              03-30-34

==SUMMARY==
DATE:             04-02-84 REVISION:            0 MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER LE. BULLETIN 79-14, PROBLEM (WD-3)
Summary:
This change consisted in modifying the pipe supports on the Reactor Coolant System (inside containment) to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-56              PC/M CLASSIFICATION:                 NS UNIT:           3 IMPLEMENTED:            12-03-83 TURNED OVER DATE:               12-20-83

==SUMMARY==
DATE:              12-20-83 REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. 79-14, P_nOBLEM CCW-033 Summary:-                       ,
This PC/M consisted in modifying the pipe supports for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. Be modification and analysis has ensured that the design criteria of the original piping system design documents have beeA met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-61 \             PC/M CLASSIFICATION:                 NS UNIT:            3 IMPLEMENTED:            01-04-84 TURNED OVER DATE:              03-13-84

==SUMMARY==
DATE:             03-15-84 REVISION:            0 MODIFICATION TO THE PRESSURIZER SPRAY AND SAFETY IN3ECTION SYSTEM (LC.) PER LE. 79-14. PROBLEM PSI-23 Summary:                                                                           -
This PC/M consisted in modifying the pipe supports on the Pressurizer Spray and Safety Injection System (inside containment) to comply with NRC I.E. Bulletin 79-14 Safety Evaluation:
This modifice. tion is nuclear safety related with no unreviewed safety question.         The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
e

l PLANT CHANGE / MODIFICATION 82-62A              PC/M CLASSIFICATION:                  NS UNIT:      3 IMPLEMENTED:    01-04-34 TURNED OVER DATE:               02-27-84

==SUMMARY==
DATE:         03-01-84 REVISION:       0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER LE. 79-14, PROBLEM 19/12 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System inside containment to comply with NRC !.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.            Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met'and no accident or malfunction probability increased.
            - , . -                     --              -...--_c--,
                                                                                                 -.-n.

PC/M CLASSIFICATION:                     NS PLANT CHANGE / MODIFICATION 82-71 UNIT:                       3 IMPLEMENTED:      12-08-83 TURNED OVER DATE:    01-06-84

==SUMMARY==
DATE:     01-09-84                                         l REVISION:                        0 MODIFICATION TO CVCS SYSTEM (LC.) PER LE. 79-14 Summary:
PC/M consisted in modifying the pipe supports for the Chemical and Volume Control System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                 The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
i i
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PLANT CHANGE / MODIFICATION 82-7:              PC/M CLASSIFICATION:                 NS UNIT:           3 IMPLEMENTED:           12-03-S3 TURNED OVER DATE:              12-20-83

==SUMMARY==
DATE:             12-20-83 REVISION:             0 MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER LE. 79-14, PROBLEM PW-2 Summary:
This PC/M consisted in modifying the pipe supports for the Reactor Coolant System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

F^
   - PLANT CHANGE / MODIFICATION 82-073             PC/M CLASSIFICATION:                NS UNIT:          3 IMPLEMENTED:            09-30-83 TURNED OVER DATE:              10-13-33

==SUMMARY==
DATE:             10-13                                                                     REVISION:            0 MODIFICATION TO AUXILIARY COOLANT SYSTEM (O.C.) PER 79-14, PROBLEM CCW-04 Summary:
This change consisted in modifying the pipe supports in the Auxiliary Coolant System outside containment to comply with NRC I.E. Bulletin 79-14.
    ' Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
e

PLANT CHANGE / MODIFICATION 74'              PC/M CLASSIFICATION:                NS UNIT:            3 IMPLEMENTED:            11-09-83 TURNED OVER DATE:             11-16-33

==SUMMARY==
DATE:              ! !-1 S-33 REVISION:              0 MODIFICATION TO DIESEL OIL AND CONDENSATE RECOVERY SYSTEM (O.C.) PER 79-14, PROBLEM DOCR-1 Summary:
This PC/M consisted in modifying the pipe supports in the Dies'el Oil and Condensate Recovery System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety ouest:en.             ine modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
t I
L.

PLANT CHANGE / MODIFICATION          82-75       PC/M CLASSIFICATION:                NS UNIT:           4 IMPLEMENTED:           02-10 84 TURNEO OVER DATE:              06-05-34 STJMMARY D ATE:           06-25-82 REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (O.C.) PER 79-14 Summary:
This PC/M consisted in modifying the pipe supports for the Comoonent Cooling Water System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.            The nodification and analysis has ensured that the design criteria of the original pioing system design documents have been met and no accident or malfunction probability increased.

82-78       PC/M CLASSIFICATION:                  NS PLANT CHANGE / MODIFICATION UNIT:          3 and 4 IMPLEMENTED:              01-19-84 TURNED OVER DATE:                03-13-84

==SUMMARY==
DATE:               03-15-8a REVISION:             0 MODIFICATION TO THE PRIMARY WATER SYSTEM (O.C.) PER LE. 79-14. PROBLEM PW-3 Summary:
This PC/M consisted in modifying the pipe supports on the Primary Water System (outside containment) to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                 ine modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
1

4 s
PLANT CHANGE /MODl'ICATION 82-79                                         PC/M CLASSIFICATION:         NS UNIT:      3 IMoLEMENTED:       12-09-83' TURNED OVER DATE:        01-06-84 a                                                                           

==SUMMARY==
DATE:        01-09-84 REVISION':     0 MODFICATION TO WASTE DISPOSAL SYSTEM (LC.) PER LE. 79-14 (PROBLEM WD-4)
Summary:                                                      .
PC/M consisted in modifying the pipe supports for the Waste Disposal System inside containment to comply with NRC I.E. Bulletin 79-14.
            ~
     - Safety Evaluation:                                                                  .
This modification is nuclear safety related with no unreviewed safety question.                             The modification and analysis has ensured that the design criteria of the original piping system design documents have been (net and no accident or malfunction probability increased.
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l                                                                           .

PLANT CHANGE / MODIFICATION 82-80                   PC/M CLASSIFICATION;             NS UNIT-      3 IMPLEMENTED:           12-20-83 TURNED OVER DATE:            01-06-84

==SUMMARY==
DATE:           01-09-84 REVISION:      0 MODIFICATION TO WASTE DISPOSAL SYSTEM (O.C.) PER LE. 79-14 (PROBLEM WD-1)
Summary:
PC/M consisted in modifying the pipe supports for the Waste Disposal System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 32-115             PC/M CLASSIFICATION '                  NS UNIT:             3 IMPLEMENTED:            !0-% .s3
_ TURNED OVER DATE:             11      !.s3

==SUMMARY==
DATE:             i : -! ". -5 3 REVISION:               0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (O.C.) PER 79-14, Summary:
This PC/M consisted in modifying the pipe supports on the Component Cooling Ta er System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unce viewed safety question.               ime modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

r PLANT CHANGE / MODIFICATION 82-116             PC/M CLASSIFICATION:                NS UNIT:           3 IMPLEMENTED:            11-18-83 TURNED OVER DATE:              12-06-83

==SUMMARY==
DATE:             12-08-83 REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (O.C.) PER LE. 79-14, PROBLEM CCW-28 Summary:
This PC/M consisted in modifying the pipe supports on the Component Cooling Water System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-119             PC/M CLASSIFICATION:                    NS UNIT:     3                      ,
IMPLEMENTED:                i1-19-S3 TURNED OVER DATE:                  11-29-33

==SUMMARY==
DATE:                 12-01-83 REVISION:              0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER 79-14, PROBLEM CVCS-10 Summary:                         ,
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System outside containment to comply with NRC 1.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                    The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
_                                       __s-  _ . _ _ . _              _ _ . .   - - - . .

PLANT CHANGE / MODIFICATION 82-120                  PC/M CLASSIFICATION:             NS UNIT:           3 IMPLEMENTED:          10-06-33 TURNED OVER DATE:           10-12-S3

==SUMMARY==
DATE:           10-25-33 REVISION:             0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER 79-14,
. PROBLEM 007 Summary:
This PC/M modified the pipe _ supports for the Chemical and Volume Control System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
Tnis modification is nuclear safety related with no unreviewed safety question.           . .e modification and analysis has ensured that the design criteria of the original piping system design documents have been me.t and no accident or malfunction probability increased.
e

PL AN~ CHANGE '\!ODIFICATTON 32-125                                                                 PC/M CLA551FfCAT10N:                                               NS UNIT:                        :.
Pr **
1 \ (. .D t .C. %. t. 2. %' "."2 R. .     .         ...t.'.
3 ;. ,.1 \i. .u. ., s.mn.. . :_.       .       .     .: -:
D. 2.i.rL<:Iua.N*..
  \iODIFICATION TO MAIN FEEDWATER SYSTEM (LC.) PER LE. BULLETIN 79-lu PROBLEM (FW7)
- Su m marv: -
       .is enange consisted in modifying :he main feedwater sys:em o!ce sucoc- s i .si:e
: ,:ainmen: :c como!y with NRC !.E. Eu!1e:in 79-12 Safetv Evaluation:
~ a :.. . ..- s.    . :u.,.. - ._ . : ,             . c .i. .. ,. , s.a . . .s. ..      : . . . s .,1. : ..- . .o . .. m.                        s=.....    ,....s.:,              -,
                                 ...         -.s  .                       ..         . . . - . .                         . . ... .y .1. w. s.           ...   .. . . - .              .
       . ; a. : . . . ; ,
: m. . . c. .i s ' . = s . . e. . s " - a d . ". = . . ' . a. " a. s .+ ..- .... . : .=. .' '. . b. -..- '.3 .= .t . ' ; ~r- . -,.3 =. .=. ~
                  ** ***                                                                                                                      ab =h,.i.I'*. ; m.ea .. s. s o. s. .
C .' "s ". ww"."*...***t
                                     .. b. 2 %c .. a. e.n **. . e *. a m..s e90. .3.C .* ; r.d o m. . *. m .e
                                                         .                                       .              . .c .8.# s.ie m C *. 4 0*.rw
                                                                                                                                          . m. .     . ...          . . .
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PLANT CHANGE / MODIFICATION 82 128                PC/M CLASSIFICATION:           NSR UNIT:         3 IMPLEMENTED:        05-19-84 TURNED OVER DATE:         05-21-84

==SUMMARY==
DATE:         05-30-Su REVISION:          0 BATTERY D.C. BUS BREAKER ALARM Summary:
This PC/M added an auxiliary switch for remote position monitoring of battery D.C.
breakers 3A-41 and 3B-23.
Safety Evaluation:
he added auxiliary switch and its subsequent alarm functirn is non-safety related and
  , does not affect any safety related equipment. Therefore, the addition of the auxiliary switch does not increase the possibility of an accident or equipment malfunc-io-important to the safety of the plant previously evaluated in the FSAR. There is no possibility of an accident or malfunction different than those previously evaluated.

PLANT CHANGE / MODIFICATION 82-1 ;                                 PC/M CLASSIFICATION:                              NSR UNIT:     4 IMPLEMENTED:                     05-19-84 TURN'ED OVER DATE:                    05-21-84 SUMM ARY DATE:                     05-30-84 REVISION:               0 BATTERY D.C. BUS BREAKER ALARM Summary:
This PC/M added an auxiliary switch for remote position monitoring of battery D.C.
breakers 3 A 41 and 3B-23.
Safety Evaluation:
The added auxiliary switch and its subsequent alar n function is non-safety related and does not affect any safety related equioment. Bere. fore, the addition of the auxiliary switch does not increase the possibility of an accident or equipment malfunction important to the safety of the plant previously evaluated in the FSAR.                                              There is no possibility of an accident or malfunction different than those previously evaluated.
4 w        vw---- ---v.---- - - . ,ww -e, - - -
                                                            -.m .- - - - . -         - - - - - - - - - - . .               -   e- -

PLANT CHANGE / MODIFICATION 82-131               PC/M CLASSIFICATION:                NS UNIT:           a IMPLEMENTED:            12-06-33 TURNED OVER DATE:               02-27-84

==SUMMARY==
DATE:              03-01-34 REVISION:            0 MODIFICATION TO SAFETY INJECTION AND RESIDUAL HEAT REMOVAL SYSTEM (O.C.) PER LE. 79-14, PROBLEM SI-2 Summary:
This PC/M consisted in modifying the pipe supports on the Safety Injection and Residual Heat Removal System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.            Tne modification and analysis has ensured that the design criteria of the original pipin.g system design documents have been met and no accident or malfunction probability increased.
l l
l L __

PLANT CHANGE / MODIFICATION 82-132             PC/M CLASSIFICATION:                 NS UNIT:           4 IMPLEMENTED:             06-06-83

==SUMMARY==
DATE:               08-15-83 REVISION:             0 MODIFICATION TO COMPONENT COOLING WATER (O.C.) PER 79-14 Summary:
This PC/M modified the pipe supports of the Component Cooling Water outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                 The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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                         - - - ,                                     _.,            ~       ,- - , , -

PLANT CHANGE / MODIFICATION 82-133             PC/M CLASSIFICATION:                 NS UNIT:          3 IMPLEMENTED:            11-13-83 TURNED OVER DATE:              12-06-33

==SUMMARY==
DATE:            12-OS-33 REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER LE.
79-14, PROBLEM CVCS-6 Summary:                                                      ,
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System outside containment to comply wit' NRC LE. Bulletin 79-14.
Safety Evaluation:
Tnis modification is nuclear safety related with no unreviewed safety question.            Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
4:
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PLANT CHANGE / MODIFICATION 82-134            PC/M CLASSIFICATION:          -       NS UNIT:             4 IMPLEMENTED:               07-19-83

==SUMMARY==
DATE:                08-04-83 REVISION:              0 MODIFICATION TO CHEMICAL VOLUME CONTROL SYSTEM (O.C.) PER LE. BULLETIN 79-14 (Problem CVC.%5)                  , ,
Summary:
This PC/M modified the pipe supports outside containment for the Chemical and Volume Control System to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
6

PLANT CHANGE / MODIFICATION 82-135               PC    T ASSIFICATION:               NS UNIT:           4 IMPLEMENTED:           09-27-33
                          .                          TURNED OVER DATE:              10-25-S3

==SUMMARY==
DATE:              10-27-83 REVISION:            0 MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM (O.C.) PER 79-14, PROBLEM CCW-12 Summary:
This PC/M modified the pipe supports in the Safety Injection and Residual Heat Removal System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety cuestion.            The modification and analysis has ensured that the design criteria of the original piping sys em design documents have been met and no accident or malfunction probability increased.

PC/M CLASSTFTCAT10N:             NS PLANT CHANGE / MODIFICATION 82-136 UNIT:     3 IMPLEMENTED:   07-07-83

==SUMMARY==
DATE:   08-23-83 REVISION:     0 MODIFICATION TO MAIN STEAM SYSTEM (O.C-) PER LE. BULLETIN 79-14 PROBLEM MSO-4 Summary:
This PC/M modified the pipe supports to the Main Steam System outside containment to comply with NRC LE. Bulletin 79-14 Safety Evaluation:
-This modification is nuclear safety related with no unreviewed safety question.                  tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increasec.

PC/M CLASSIFICATION:                   NS PLANT CHANGE / MODIFICATION 82-137 UNIT:      e IMPLEMENTED:   05-10-83

==SUMMARY==
DATE:                  08-26-83 REVISION:     0 MODIFICATION TO AUXILIARY COOLANT SYSTEM (O.C.) PER LE. BULLETIN 79-14 PROBLEM O25
  . Summary:
This PC/M consisted in modifying the Auxiliary Cooiant System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
The This modification is nuclear safety related with no unreviewed safety question.
modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
1

PLANT CHANGE / MODIFICATION 82-141                PC/M CLASSIFICATION:             NNS UNIT:         3 IMPLEMENTED:          12-22-83 TURNED OVER DATE:           02-27-8a

==SUMMARY==
DATE:           03-01-30 REVISION:          1 REPLACEMENT OF UNIT AUXILIARY TRANSFORMER Summary:
This PC/M changed the existing unit auxiliary transformer for a new transformer with similar specifications but with better short circuit capability and also better cooling.
Safety Evaluation:
This PC/M does not involve an unreviewed safety question because the probability of occurrence of an accident previously evaluated in the FSAR is not increased since it merely involved the replacement of existing equipment with similar equipment.
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PC/M CLASS 1FlCATICN:               NS PLANT CHANGE / MODIFICATION- 32-143 UNIT:        3 IMPLEMENTED:            12-06-83 TURNED OVER DATE:              12-15-83

==SUMMARY==
DATE:             12-19-83 REVISION:      -0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER LE.
79-14, PROBLEM CCW-016 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PC,          (SIFICATION:          NS PLANT CHANGE / MODIFICATION 82-146 UNIT:        3&4
                                                                '' ' 7 LEMENTED:
                                                                     .                  08-16-83 TURNED OVER DATE:             10-06-S3
                                                 +

==SUMMARY==
DATE:             10-12-S3 REVISION:          0 MODIFICATION TO AUXILIARY COOLANT SYSTEM (O.C.) PER 79-14,
        -PROBLEM CCW-12 Summary:
This - PC/M modified the pipe supports in the Auxiliary Coolant System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
T,e This modification is nuclear safety related with no unreviewed safety question.
modification and analysis has ensured that the design criteria of the original piping syste~
design documents have been met and no accident or malfunction probability increased.
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PL' ANT CHANGE / MODIFICATION 82-150           PC/M CLASSIFICATION:                 NS UNIT:          3 IMPLEMENTED:            02-07-84 TURNED OVER DATE:              03-13-84

==SUMMARY==
DATE:            03-15-84 REVISION:            0 MODIFICATION TO THE CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER LE.
79-14, PROBLEM CPS Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control Sy' stem (outside containment) to comply with NRC I.E. Bulletin 79-14.~
Safaty Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-154              PC/M CLASSIFICATION:                 NS UNIT:            u IMPLEMENTED:            10-06-83 TURSED OVER DATE:              10-13-33 SUMM ARY DATE:             10-1S-S3 REVISION:             0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER 79-14, PROBLEM CVCS-1 Summary:
This PC/M consisted in modifying the pipe supports in the Chemical and Volume Cont.ol System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
Tnis modification is nuclear safety related with no unreviewed safety quest:en.           .me modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability inc. eased.

PLANT CHANGE / MODIFICATION 82-156             PC/M CLASSIFICATION:                                  NS UNIT:                            3 IMPLEMENTED:                              01-19-84 TURNED OVER DATE:                                03-13-82

==SUMMARY==
DATE:                               03-15-84 REVISION:                            0 MODIFICATION TO THE CHEMICAL AND VOLUME CONTROL SYSTEM (C.C.) PER LE.
79-14, PROBLEM CVCS-7 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System (outside containment) to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                            The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-157             PC/M CLASSIFICATION:                 NS UNIT:             4 IMPLEMENTED:            09-22-83 TURNED OVER DATE:             10-21-83

==SUMMARY==
DATE:             10-22-33 REVISION:               0 MODIFICATION TO CONTAINMENT COOLING WATER SYSTEM (O.C.) PER 79-14, PROBLEM CCW-25 Summary:
This PC/M consisted in modifying the pipe supports for the Component Cooling Tater System outside containment to comply with NRC I.E. Bulletin 79-14
' Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety cuest':n.     .      .e modification and analysis has ensured that the design criteria of the origina. ;'.:! .; ate-design documents have been met and no accident or malfunction probabiFty 1 cre25e:.

PC/M CLASSIFICATION:                 NS PLANT CHANGE / MODIFICATION 82-158 UNIT:           4 IMPLEMENTED:            07-19-83 TURNED OVER DATE:              10-06-83

==SUMMARY==
DATE:             10-12-83 REVISION:            O.
MODIFICATION TO COMPONENT COOLING WATER SYSTEM (O.C.) PER 79-14, PROBLEM CCW-16 Summary:
This PC/M consisted of modifying the pipe supports in the Component Cooling Tater Syste'm outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
ine This modification is nuclear safety related with no unreviewed safety cuestion.
modification and analysis has ensured that the design criteria of the original p'iping system design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE /MCDIFICATION 32-164               PC/M CLAS'.IFICATION:               NS UNIT:          a IMPLEMENTED:            10-04-83 TURNED OVER DATE:               10-21-33

==SUMMARY==
DATE:              10-2'-33 4
REVISION:           0 MODIFICAT3N TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER 79-14, PROBLEM CP5,                                                                            ,
Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
Tnis modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

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    ~ ?LANT CHANGE / MODIFICATION 82-165_            PC/M CLASSIFICATION:                NS UNIT:          4 IMPLEMENTED:            10-06-83 TURNED OVER DATE:              10-12-83

==SUMMARY==
DATE:             10-20-S3 REVISION:            0-MODIFICATION TO COMPONENT COOLING WATER SYSTEM (O.C.) PER 79-14, PROBLEM 037 Summary:
    - This change consisted in modifying the Component Cooling Water System pipe supports outside containment to comply w;th NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is . nuclear safety related with no unreviewed safety quest:en.          ine modification and analysis has ensured that the design criteria of the original piping system design. documents he.ve been met and no accident or malfunction probability increased.
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u PLANT CHANGE / MODIFICATION 82-167                                              PC/M CLASSIFICAT*0N:      NS UNIT:     4 IMPLEMENTED:    07-19-83

==SUMMARY==
DATE:     08-04-83 REVISION:      0 MODIFICATION TO SAFETY IN3ECTION SYSTEM (O.C.) PER LE. BULLETIN 79-14 (Problem 51-1)
Summary:
This PC/M modified the pipe supports on the safety injection system outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                 The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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PC/M CLASSIFICATION:         NNS PLANT CHANGE / MODIFICATION 82-168                                                    __
UNIT:        3 IMPLE'MENTED:     12-07-83 TURNED OVER DATE:       12-15-83

==SUMMARY==
DATE:      12-16-83 REVISION:        0 REPLACEMENT OF RCP TEMPERATURE RECORDER Summary:
                                                                      ~
The RCP temperature recorder presently in service is prone to frequent mechanical failures. The modelit is being replaced by is of improved design and more reliable.
Safety Evaluation:          ,
This PC/M does not detract from the safety function of any plant system or componen:
and therefore, does not involve an unreviewed safety question.

PLANT CHANGE / MODIFICATION 82-169             PC/M CLASSIFICATION:         NNS UNIT:         4 IMPLEMENTED:        04-15-S3 TURNED OVER DATE:        11-28-83

==SUMMARY==
DATE:         11-30-S3 REVISION:           1 REPLACEMENT OF RCP TEMPERATURE RECORDER Summary:
This CPWO provides the replacement of the existing L&N Modei W RCP temperature recorder with a Speedomax Model #250 temperature recorder. The existing recorder is in poor mechanical condition and frequently fails. The new recorder is of an improved design and performs more reliably.
Safety Evaluation:
The replacement of the existing RCP temperature recorder is not nuclear safety related because it does not perform any safety function. The probability of occurrence or the consequences of a design basis accident or malfunction of equipment important to tne safety of the plant previously evaluated in the FSAR, has not been increased. For this reason, the replacement of the RCP temperature recorder does not involve an unreviewe:
l     safety question.
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                        ~
4 PLANT CHANGE / MODIFICATION 82-171              PC/M CLASSIFICATION:                NS UNIT:           4 IMPLEMENTED:            11-07-83 TURNED OVER DATE:               11-16-83

==SUMMARY==
DATE:              11-13-83 REVISION:             0 MODIFICATION TO SAFETY INJECTION AND RESIDUAL HEAT REMOVAL SYSTEM (O.C.) PER 79-14, PROBLEM 050 Summary:     -
This PC/M consisted in modifying the pipe supports for the Safety Injection and Residual Heat Removal System outside containment to comply with NRC I.E. Bu!!etin 79-12 Safety Evaluation:
  - This modification is nuclear safety related with no unreviewed safety         uest:c.~. e modification and analysis has ensured that the design criteria of the origina! pip! g    .5:e-design documents have been met and no accident or malfunction probab!!ity increase:.

PC/M CLASSIFICATION:                NS PLANT CHANGE / MODIFICATION 82-172 UNIT:           4 IMPLEMENTED:            08-17 83 TURNED OVER DATE:              10-21-S3

==SUMMARY==
DATE:             10-2h-S3 REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER 79-14, PROBLEM 007 Summary:
This PC/M consisted in modifying the pipe supports on the Chemical and Volume Control System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety -question.          Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION _82-173             PC/M CLASSIFICATION:                                         NS UNIT:                      4 IMPLEMENTED:                                       07-19-83

==SUMMARY==
DATE:                                        08-26-83 REVISION:                      0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (O.C.) PER LE.
BULLETIN 79-14 PROBLEM CVCS-3 Summary:
  . This PC/M consisted in modifying the Chemical and Volume Control System pipe supports outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                    Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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I PC/N1 CLASSIFICATION:
PLANT CHANGE /110DIFICATION 32-174                                                  NS UNIT:           a IMPLEliENTED:          08-16-83 TURNED OVER DATE:               10-21-83 SU\iMARY DATE:             10-22-33 REVISION:            0        i MODIFICATION TO CONTAINMENT COOLING WATER SYSTEM (O.C.) PER 79-14, PROBLEM CCW-15 Summary:
This PC/M consisted in modifying the pipe supports on the Component Cooling Tater System outside containment to comply with NRC I.E. Bulletin 79-14.
  . Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLAN     CHANGE / MODIFICATION 82-186          PC/M CLASSIFICATION:          NS UNIT:         4 IMPLEMENTED:       08-23-83 TURNED OVER DATE:         09-21-83

==SUMMARY==
DATE:        09-26-83 REVISION:         3 FISCHER & PORTER TRANSMITTER REPLACEMENT Summary:
This PC/M replaced existing F&P transmitters with Rosemount Model 1153 units.
Safety Evaluation:
Since this PC/M modification is only for transmitter replacement and the new locations are approximately. the same as the existing, it does not change the previous design.
Therefore, the replacement does not change the design function of the circuitry and a malfunction would cause the same results as a malfunction of the presently installed transmitters. Therefore, the probability or consequences of an accident previously evaluated in the FSAR are not increased. An accident of a different type cannot ce created.                                     .

PLANT CHANGE / MODIFICATION _82-195                PC/M CLASSIFICATION:               NS UNIT:         4 IMPLEMENTED:    16-83

==SUMMARY==
DATE:              08-26-83 REVISION:         0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. BULLETIN 79-14, PROBLEM CCW-45 Summary:
This PC/M consisted in modifying the pipe supports on the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.             The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-199                        PC/M CLASSIFICATION:              NS UNIT:       3 IMPLEMENTED:        11-22-83 TURNED OVER DATE:             12-06-33

==SUMMARY==
DATE:             12-08-83 REVISION:       0 MODIFICATION TO AUXILIARY FEEDWATER SYSTEM (O.C.) PER LE. 79-14 Summary:
This PC/M consisted in modifying the pipe supports on the Auxill'ary Feedwater System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                   Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
1

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?LANT CH 2.SGE ''.10DITICATION S2-200           PC/\1 CLASSIFfCATION:                                         NS UNIT:                        L                 j i
                                                                                                     ; . , u_ ,
                                                                                                   - e          -
Is.1 .o f_ e_ s.t =_ N _. =- .n.
                                                                               -                   ,                            i SUN 1\1ARY DATE:                        :- 19-33 REVISION:                             :
MODIFICATION TO MAIN STEAM SYSTEM (LC.) PER LE. BULLETIN 79-14 PROBLEM (L E.-I I)
Summarv:                                                                  .
Tnis change consisted in modifying the main steam sys em oice su6cer:                                               :
nsMe containmen: :o comoly 'vith NRC I.E. Bulletin 79-12 Safety Evaluation:
T-!s modifica:10n is .uclear safe y related wie no urreviewed safe:. cues:i: .                                          e mcdifica-ion and analysis has ensured da: de design :.-!:eria of :5e crit:nal :!:i                              ses e-desig- documents have beer me and no accident or malfunc-ion crobabill- :ncreased.
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PLANT CHANGE / MODIFICATION 82-201                    PC/M CLASSIFICATION:          NS UNIT:           k IMPLEMENTED:        05-10-83

==SUMMARY==
DATE:         08-15-83 REVISION:           0 MODIFICATION TO PRESSURIZER SURGE LINE (LC.) PER 79-14, PROBLEM 041 Summary:
This PC/M modified the pipe supports for the Pressurizer Surge Line inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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                                                                                                                                                                 .                .     . .                .    .e : .q-REVISIO N:
MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.I PER LE. BULLETIN 79-14 PROBLEM (CCW-39)                                                                                                                                                                    .
Summarv:
This change consisted in nodifying -he comocnent cooling water system cice sucoc- s inside containment to comoly svi:5 NRC I.E. Sulle:in 79-12 Safety Evaluation:
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PLANT CHANGE /MODfFICATION S2-203              PC/M CLASSTFICATION:
UNIT:                   .
I\iPLE\1ENTED:           : 5 . :-33

==SUMMARY==
DATE:                 37-19-33 REVISION:                   0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. BULLETIN 79-14 PROBLEM (CCW-37)
Summarv:
This change consisted in modifying the comoonent cooling water system cipe supoorts inside containment to comply with NRC LE. Bulletin 79-14 Saferv Evaluation:
This modification is nuclear safety related with no unreviewed safety cuestion.                    The-modification and analysis has ensured that the design criteria of the erizina! oiping system design documents have been met and no accident or malfunction orobability increased.
           -          ,    -,.     . - - - - -  ,,     . - - . , , ,         - . , - . = , , - -

PC/M CLASSIFICATION:                  NS PLANT CHANGE / MODIFICATION 82-206 UNIT:             4          ;
IMPLEMENTED:               07-la-83       ,

==SUMMARY==
DATE:                07-22-83       f
~
REVISION:              0 l
MODIP1 CATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER LE.
BUT 1 ETIN (PROBLEM CVCS 4)
Summary:
This change consisted in modifying the pipe supports in the chemical and volume control system outside containment to comply with NRC LE. Bulletin 79-14 Safety Evaluation:                                                             -
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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i PLANT CHANGE /\10DfFTCATION S2-207            PC/M CLASSIFTCATION:                   NS        !
UNIT:             E
                                                                                               )
I\iPLE\1ENTED:            05-10-S3 SUN 1 MARY DATE:            07-19-?3 REVISION:              G MODIFICATION TO ' CHEMICAL VOLUME AND CONTROL' SYSTEM (LC.) PER LE.
BULLETIN PROBLEM (CVCS 23)
Summary:                  -
This change consisted in modifying the chemical volume and control system oipe supoorts inside containment to comply with NRC I.E. Bulletin 79-14.
Saferv Evaluation:
This modification is nuclear safety related with no unreviewed safety cuestion.           ine modification and analysis has ensured that the design criteria of the original picing system design documents have been met and no accident or malfunction orobabill v increased.

PLANT CHANGE / MODIFICATION 82-208                                  PC/M CLASSIFICATION:                   NS UNIT:            4 IMPLEMENTED:             05-16-83

==SUMMARY==
DATE:               08-10-83 REVISION:            0 MODIFICATION TO CHEM: CAL AND VOLUME CONTROL SYSTEM (LC.) PER 79-14, PROBLEM CVCS-29 Summa y:
This PC/M consisted in modifying the pipe supports on the chemical and volume control system inside conteinment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                                  The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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                                                                                   .-_..-v--   -    , . _ , _       _   , - _ . _ _ . _ _

PC/M CLASSIFICATION:                                          NS PLANT CHANGE / MODIFICATION _S2-209 UNIT:               3 IMPLEMENTED:             12-30-83 TURNED OVER DATE:                                 01-16-84

==SUMMARY==
DATE:                01-27-84 REVISION:               O CONTAINMENT PURGE VALVES LEAK TEST CONNECTIONS Summary:                                                                                          -
This PC/M installed leak rate' test connections outside of the containment and removed and sealed the leak test connections inside the containment. This modification permits leak testing of.the purge valves at any time, independent of reactor operation.
Safety Evahaation:
This safety related PC/M does not involve an unreviewed safety question because no active components have been added to the system; the operating functions, or conditions of other safety related equipment has not been affected and the new equipment has been designed to withstand postulated seismic loads.
-----~y.      , - . - , - - - - - -   ,n ,   - , , e-. - .., - ,.- - -, -,,,_---,.-,.-,,,-.,.,-,,,_,,e,--                . . . - ,
e ,, --_,

-PLANT CHANGE / MODIFICATION 82-210             PC/M CLASSIFICATION:              NS UNIT:          4 IMPLEMENTED:         05-09-83 TU'RNED OVER DATE:          10-25-83
                         ~

==SUMMARY==
DATE:         10-27-83 REVISION:           O CONTAINMENT PURGE VALVE LEAK TEST CONNECTION Summar';:
This ' modification consisted -in providing a means for leak testing containment purge valves by adding a test connection outside containment to permit leak testing at any time, independent of reactor operation.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.         No probability of occurrence or consequence of accident / malfunction has increased. Further-more, this modification does not decrease any margin of safety discussed in the Technical Specifications.

PLANT CHANGE /\10DIFICATION S2-214            PC/M CLASSIFICATION:                 NS UNIT:           4 IMPLEMENTED:            05-21-83 SU\lMARY DATE:            07-19-83 REVISION:             0 MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.) PER LE. BULLETIN PROBLEM (053)
Sommary:
                                                                      ~
This change consisted in modifying the safety injection and residual, heat removal system pipe supports inside containment to comply with NRC 1.E. Bulletin 79-14 x
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE. .'0DIFICATION 82-:;5               PC/M CLASSIFICATION:              NS UNIT:            4 IMPLEMENTED:            05-25-83

==SUMMARY==
DATE:             08-15-83 REVISION:             0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER 79-14, PROBLEM CVCS.25C Summary:
This PC/M modified the        .opports for the Chem.ical and Volume Control System inside containment to comply witn .,RC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety questiqn. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-220               PC/M CLASSIFICATION:                NS
                                                                                ~
UNIT:            4 IMPLEMENTED:            08-16-83 TURNED OVER DATE:               10-21-53

==SUMMARY==
DATE:              10-24-83 REVISION:              0 MODIFICATION TO WASTE DISPOSAL SYSTEM (O.C.) PER 79-14, PROBLEM WD-2 Summary:
This PC/M consisted in modifying the pipe supports on the Waste Disposal System outside containment to comply with NRC LE. Bulletin 79-14.
s                              -
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.            The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE''.iCDiFICATION S2-221              PC/\1 CLASSIFICATION:                 NS UNIT:            2 I\tPLEiiENTED:           05-10-33 SU\1'1 ARY D ATE:           06-!9-33 REVISION:              0 MODIFICATION TO -MAIN FEEDWATER SYSTEM (LC.) PER LE. BULLETIN 79-14
  ' PROBLEM (FW7)
Summary:                                                                           .
This change consisted in modifying the main feedwater system cice succorts inside containmen to.comoly with NRC I.E. Bulletin 79-14 Saferv Evaluation:
This modification is nuclear safety related with- no unreviewed safety cues:.on.           ne
:odification and analysis has ensured that the design criteria of the original cicing sys em
:esign documents have been me; and no accident or malfunction crocability increased.

PLANT CHANGE / MODIFICATION 82-222             PC/M CLASSIFICATION:                  NS UNIT:           4 IMPLEMENTED:             05-10-83

==SUMMARY==
DATE:               08-15-83 REVISION:             0 MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM (LC.) PER 79-14. PROBLEM Si-16 Summary:
This PC/M modified the pipe supports for the Safety Injection and Residual Heat Removal System inside containment to comply with NRC LE. Bulletin 79-14.
i    Safety Evaluation:
    ' This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-223            PC/M CLASSIFICATION:                 NS UNIT:            4 IMPLEMENTED:             06-22-83

==SUMMARY==
DATE:               08-26-83 REVISION:             0 MODIFICATION TO MAIN STEAM SYSTEM (LC.) PER LE.                          BULLETIN 79-14, PROBLEM IC-12
~
Summary:                          -
This PC/M consisted in modifying the Main Steam System pipe supports inside containment to compiy with NRC LE. Bulietin 79-14.
Safety Evaluation:
  'This modification is nuclear safety related with no unreviewed safety question.         The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

- PLANT CHANGE / MODIFICATION 82-224              PC/M CLASSIFICATION:                NS      -
UNIT:           3 IMPLEMENTED:           10-31-83 TURNED OVER DATE:              12-06-83

==SUMMARY==
DATE:             12-08-83 REVISION:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (O.C.) PER LE. 79-14, PROBLEM CCW-07 Summary:             .
This PC/M consisted in modifying the pipe supports on the Component Cooling Water System outside containment to cornply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.            The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
9

PLANT CHANGE / MODIFICATION 82-225              PC/M CLASSIFICATION:                NS UNIT:           4 IMPLEMENTED:            07-07-83 TURNED OVER DATE:              10-12-83 SUMM ARY DATE:            10-20-83 REVISION:            0 MODIFICATION TO SAFETY INJECTION AND RESIDUAL HEAT REMOVAL SYSTEM (O.C.) PER 79-14, PROBLEM 047 Summary:                                                                                       .
. This change consisted in modifying' the Safety Injection and Residual Heat Removal System pipe supports outside containment to co'mply witn NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The mcdification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

  . PLANT CHANGE / MODIFICATION 'S2-226            PC/M CLASSIFICATION:                 NS UNIT:           3 IMPLEMENTED:            09-22-83 TURNED OVER DATE:              10-06-83

==SUMMARY==
DATE:             10-!2-83 REVISION:             0 MOOFICATION TO INTAKE COOLING SYSTEM (O.C.) PER 79-14, PROBLEM Summary This PC/M consisted in modifying the pipe supports for the Intake Cooling System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety ques ::n.           ne modification and analysis.has ensured that the design criteria of -he original picing system design documents have been met and no accident or malfunction probab!!!ty increased.
e O
e

PLANT CHANGE / MODIFICATION 82-223              PC/M CLASSIFICATION:              NNS UNIT:          3&4 IMPLEMENTED:            08 /2h /83 TURNED OVER DATE:            09-23-83

==SUMMARY==
DATE:             09-26-83 REVISION:            0
                                            .                                                    1 POWER SUPPLY TO ACCESS AND DRESS FANTTY Summary:                                                     .
This modification provided a power feed to access and dress facility. The power supply         l was obtained from the Florida City feed power line via the dry storage warehouse transformer vault. A new duct bank was run from the existing dry storage warehouse ::
the new facility.
Safety Evaluation:
The access and dress facility power supply and associated duct banks do not perform a safety function and due to their location cannot interact with any safety relatec structures, system, or equipment. The probability of occurrence or the consequences of a design basis accident previously evaluated in the FSAR has not been increased. Tnere is no possibility of accident or malfunction different than those previously evaluated. Ne margin of safety as defined in the bases for any Technical Soecification is reduced.
Therefore, it can be concluded that this PC/M is non-safety related and does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 82-229              PC/M CLASSIFICATION:           NNS UNIT:        3&4 IMPLEMENTED:        Il-10-83 TURNED OVER DATE:          Il-16-83 SU".M ARY DATE:        11-13 83 REVISION:           0 ACCESS AND DRESS FACILITY SEPTIC SYSTEM                                       '
Summary:                                                                            .
This PC/M provided a septic system that services the access and dress facility. Tne septic system is located due east of the access and dress facility. The new layout and design   is in of Department     accordance    with the South Florida Building Code and the 'ade County Polution Control.
Safety Evaluation:
ine septic system does not perform a safety function or provide protection for safety related systems or equipment. Tne system is located away from all safety relatec structures, systems, and components. As such, :he system is c!assified non-safety re'ated.

ANGE/ MODIFICATION 82-230            PC/M CLASSIFICATf0N:                N3 UNIT:           a IMPLEMENTED:            06-24-33 TURNED 0VER DATE:               11-29-33

==SUMMARY==
DATE:              12-01-83 REVISION:             0 MODIFICATION TO CONDENSATE AND FEEDWATER AUXILIARY SYSTEM (O.C.) PER 79-14, PROBLEM 057 Summary:
This PC/M consisted in modifying the pipe supports on the Condensate and Feedwater Auxiliary System outside containment to comply with NRC LE. Bulletin 79-14 Saferv Evaluation:
This modification is nuclear safety related with no unreviewed safety cuestion.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
9

PL/ M LLAsair m.'. uum               m            -
PLANT CHANGE / MODIFICATION 32-43 L UNIT:            4 IMPLEMENTED:              07-08-83

==SUMMARY==
DATE:               07-22-83 REVISION:             0 MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER LE. BULLETIN 79-14 (Problem PR-2)
Summary:
This change consisted in modifying the reactor coolant system pioe supports inside containment to c.omply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original pioing system d; sign documents have been met and no accident or malfunction probability increased.
e

PLANT CHANGE /MODfFfCATION 82-232             PC/M CLASSIFICATION:                 NS UNIT:            c IMPLEMENTED:             05-1C-83

==SUMMARY==
DATE:              07-19 83 REVISION:              C MODIFICATION TO CONTAINMENT SPRAY SYSTEM (LC.) PER L E. BULLETIN PROBLEM (058A)
Summary:
This change consisted in modifying the contalment spray system oice supoorts inside containment to comply with NRC LE. Bulletin 79-14 Safety Evaluation:
i This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original oicing system design documents have been met and no accident or malfunction probability increased.
t t_ .

PC/M CLASSIFICATION:                  NS PLANT CHANGE / MODIFICATION S2-233 U'!!T:           4 IMPLEMENTED:              05-10-83

==SUMMARY==
DATE:               08-10-33 REVISION:             0 MODIFICATION TO SAFETY IN3ECT10N AND RESIDUAL HEAT REMOVAL SYSTEM PER 79-14. PROBLEM S1-17 Summary:                        ,
This PC/M consisted in modifying the pipe supports for the safety injection and residual heat removal system inside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluatior.:
This modification is nuclear safety related with no unreviewed safety question.          Be modification and analysis has ensured that the design criteria of the original piping <yste ..
design documents have been met and no a-:ident or malfunction probability increased.
l 1
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PLANT CHANCE /\tODIFICATION 32-233              PC /\1 CL ASSIFIC ATIO N:          NS UNIT:         2 l'.t PL E\t ENTED:    05-10-33 SU\tMARY DATE:          T 33 REVISION:         0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. BULLETIN 79-14 PROBLEM (CCW 43)
Summarv:
This change consisted in modifying the comoonent cooling water system oice succorts inside con:ain. ment to como!y wi:5 NRC !.E. 'Bu!!e:!n 79-1L.
Safety Evaluatien:
T'-!s   cd;!! cation is nuc! ear safety related w!:5 no unreviewed safe:v cues:!cm. The m:t!!!:2:len. and analysis has ensured :52: :5e desiz, :riteria of :Me cr!&a! o!cinz sys em des!;n d:cuments have been Te: and no accident or ma!!unc:!cn orobability increased.

PLANT CH ANGEN.lODIFIC 2 ~~         ?:-2 39     PC/M CLASSIFTCATTON:                                   NS UNfT:                                    2 IMPLEMENTED:              05-10-33

==SUMMARY==
DATE:               07-!9-33 D EVISIO N:                                  0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. BULLETIN 79-14 PROBLEM (CCW-33)
Summarv:    ,
This change consisted in modifying the component cooling water system cice supoorts inside containmen: to comoly with NRC !.E. Bulletin 79-14 Saferv Evaluation:
T5!s modifica:!cn is nuclear safety related with no unreviewed safety ques:!on.                                                                                n.e modifi:ati:n. and analysis 5as ensured tha: :he design criteria of the Original cioing sys:em desizn dccuments have been met and no accident er malfunc:!cn probability increased.

PC/M CLASSIFICATION:                 NS PLANT CHANGE / MODIFICATION 82-241 UNIT:            6 IMPLEMENTED:             05-23-83

==SUMMARY==
DATE:               08-26-83 REVISION:              0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (LC.) PER LE.
BU1.LETIN 79-14. PROBLEM CVCS-24 Summary:
This PC/M consisted in modifying the Chemical and Volume Control System pipe supports inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
e 9

PC/M CLASSIFICATION:                       NS PLANT CHANGE / MODIFICATION 82-242 UNIT:         4 IMPLEMENTED:                    05-10-83

==SUMMARY==
DATE:                    07-19-83 REVISION:                     0 MODIFICATION TO CHEMICAL VOLUME AND CONTROL SYSTEM (LC.) PER LE.
* BULLETIN PROBLEM (CVCS 27)
Summary:
This change consisted in modifying the chemical volume and control system oipe supoorts inside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related. with no unreviewed safety question.                                    The modification and analysis has ensured that the design criteria of the original pioing system design documents have been met and no accident or malfunction probability increased.
                                     , - - , . _ - , - - - - . - . -            _. _ _ _ _ _ _ _       __   _        ,, .-s

PC/M CLASSIFICATION:                 NS PLANT CHANGE / MODIFICATION 82-249 UNIT:            4 IMPLEMENTED:              05-25-83

==SUMMARY==
DATE:               07-19-31 REVISION:              C MODIFICATION TO WASTE DISPOSAL SYSTEM (LC.) PER LE. SULLETTN PROBLEM (WD-8)
Summarv:
This change consisted in modifying the waste disposal system pipe
* supports insice containment to comply with NRC LE. Bulletin 79-t4.
x Safety Evaluat i ym This modification is nuclear safety related with no unreviewed safety question.           .ne modification and analysis has ensured that the design criteria of the original gioing system desit;n documents have bee met and no accident or malfunctina orobability increased.

PLANT CHANCE /\tODIFTCATION S2-250             PC/\1 CL ASSIFICATTCN:               NS i                                          !                                                UNIT:             a 1.\lPLEt1ENTED:         55-10-33
                                                                             . 51151M ARY DATE:          37-19-33
        .                                                                              REVISION:              0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. BULLETIN                            ~
79-14 PROBLEM (CCW-36)
Summary:
This change consisted in modifying the comporient cooling water system pipe supports inside containment to comply with NRC !.E. Bulletin 79-14 Safety Evaluation:
This modification 'Is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original pioing system design documents have Seen met and no accident or malfunction orobability increased.
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PLANT CHANGE / MODIFICATION 82-251             PC/M CLASSIFICATION:                 NS UNIT:            k IMPLEMENTED:              05/10/33 TURNED OVER DATE:                09-23-33

==SUMMARY==
DATE:               09-26-33 REVISION:              0 MODIFICATION TO THE COMPONENT COOLING WATER SYSTEM (IC) PER LE.
BULLETIN 79-14 PROBLEM CCT-46 Summarvt This PC/M modified the pipe supports in the component cooling water system inside containment to comply with NRC I.E. Bulletin 79-14 Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety ques' tion.         The modification and analysis has ensured that the design criteria of the original pioing system design documents have been met and no accident or malfunction probability increased.

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                                                                                                                                                                    -.se-e. tc.1 ,\..    .                      ,
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MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER LE. BULLETIN PROBLEM
( P'V.A)
  .                                  Summarv:                                                                                                                                               .
This :hange : ens!sted in rod!!ying the resetor coolant system oice suceerts :asi:e
:entain nen: :: :omeiv wi:n NRC !.E. Sulle !n 791L.                                                                                                                                             -
1 Safety Evaluation:
                                       .3 .
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                                                                              .          .                    . . .'s..d v..*                   . . .    .. a. \ :. . .v a. . f a '. a. . . .        a. s . . .- . .          a.
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                                                                                                                                                      .        . . . . .   ..,..a.. . ......    .. .    ...,f,....
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PLANT CHANGE! MODIFICATION 82-253            PC/M CLASSIFICATION:                 NS UNIT:           2 IMPLEMENTED:             07/27/33 __
TURNED OVER DATE:              09-23-33

==SUMMARY==
DATE:              09-26-83
   -                                                          REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (IC) PER LL BLLLs a d 79-14. PROB .EM CVCS 25B Summaryt This change consisted in modifying the pipe supports in the chemical and volume control system inside containment to comply with NRC LE. Bulletin 79-14 Safety Evaluation:
                                                                                        ~
This modification is nuclear safety related with no unreviewec safety cuest:en.           9e modification and analysis has ensured that the design :r!teria of tne original oscing svste-ces:gn documents have been met and no accident or malfunct:en crocamility .nc. esse:.
W     se t as

PLANT CHANGE / MODIFICATION 82-260                PC/M CLASSIFICAYIOB$t               NS UNIT:        3&4 IMPLEMENTED:           10-04-33 TURNED OVER DATE:             !C-21-33

==SUMMARY==
DATE:            10-24-33 REVISION:            0 MODIFICATION TO BORIC ACID SYSTEM (O.C.) PER 79-14, PROBLEM 237 Summary l
This PC/M consisted in modifying the pipe supports on the Boric Acid Sys:em cu: side containment to comply with NRC 1.E. Bulletin 79-14 Safety EvaluatlOnt 7-!s m:dif!:st!:n is auclear safety related with no unreviewed safety question.            7,e
:d!!!:2:!:n s,d ans!yt!s has ensured that the design criteria of the or!g!nal o!;!ng sys:em
::s;gn de:uments 5sse been met and no accident or ms!!unc:!on probsbill:y increase .
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CPTO PLANT CHANGE /\tODfFICATION 32-761                      PC/M CLAS$1FICATION8                           NSR UNIT:                       3&4 IM PLE.',t ENTED:                     09-23-33 TURNED OVER DATE:                           10 05-33

==SUMMARY==
DATE:                          10-.37-33 REVISION:                           0             f i
DECONTAMINATION ROOM EXHAUST DUCT INSTALLATION                                                                        j Summary:                                     -
This CPWO involved the installation of an exhaust duct and register In the decontamin-ation room adjacent to the hot tool room / tool crib. This modification was required :o comply with the five (5) minimum air turnovers per hour per room !n the 1.us;;;sry                                   ;
Building as speelfled by the FSAR.                                                                                  i Safety Evaluationt l
The HVAC system in :ne aux!!!sry building is non-safety related, inerefore. :his CF',' O .s not nuclear safety re!sted as it d:es not affect any safe:y related system or f:2:;re ; . : .e p! ant. F;rthermore, it does not a!!ect, create, or increase any ac:! dea: '?.a!!unc .:-
already addressed, or new, in :he FSAR.
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PL ANT CHANGE /\tCDIFTCATION 32-262           PC'\1 CL ASSIFTCAT!ON:                NS UNIT:            2 l\tPLEitENTEP:          05-10-33 SU\1\1ARY DATE:           0 33 R EVISIO N:            0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (LC.) PER LE. BULLETIN 79-14 PROBLEM (CCT-34)
Summarv This change consisted in modifying the comoonent cooling water system cioe succor:s inside containment to comoly 'vith NRC !.E. Bu!!etin 79-14 S.3fety Evaluation:
This modification is nuclear safety re!ated with no unreviewed safe:v question.           ~5e mcdif!ca: ion and analysis 5as ensured that :he desis, criteria of :he original cioint system design documents have been met and no accident or malfunction orebabill:v increased.

i ANT Cl!ANCE/'.tO"'FICATION 32-263           PC/\1 CLASSIFICATION:                 NS UNIT:            4
                                                           !\tPLE\ TENTED:          05-23-33 SU\1*t ARY DATE:            07-19 33 R EVIS:""':           0 MODIFICATION TO COMPONCltT COOLING WATER SYSTEM (LC.) PER LE. BilLLETIN 79-14 PROBLEM (CCW-35)
Ssmmary:
This change consisted in modifying the inain feedwater system pipe supports inside containment to comply with NRC f.E. Bulletin 79-14.
Safetv Evaluation:
Bis modification is nuclear safety related with no unreviewed safety question.             The modification mid analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or rr.alfunction probability increased.
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r PLANT CHANGE / MODIFICATION 82-266             PC/M CLASSIFICATIONa                 NS UNIT:           3 IMPLEMENTED:            02-01-84 TURNED OVER DATE:              03-13-84

==SUMMARY==
DATE:             03-15 34 REVISION:            0 n'
MODIFICATION TO THE SAFETY IN3ECT10N AND RESIDUAL HEAT REMOVAL SYSTEM (O.C.) PER LL 79-14. PROBLEM 032 SummarYt This PC/M consisted in modifying the pipe supports on the Safety injection and Residual Heat Removal System (outside containment) to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 82-26'           PC/M CLASSIFICATION:                 NS UNIT:           4 IMPLEMENTED:             05-25-83

==SUMMARY==
DATE:              08-15-83 REVISION:             0 MOD FICATION TO COMPONENT COOLING WATER (LC.) PER 79-14 PROL .EM CCT41
  . Summary 1 This PC/M modified the pipe supports for the Component Cooling Water System inside containment to comply with NRC LE. Bulletin 79-14.
Safety EVRAlttlen:
This modification is nuclear safety related with no unreviewed safety question.         Ta.e modification and analysis has ensured that the design criteria of the original pleing syste-design documents have been met and no accident or malfunction probability increases.
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PLANT CHANGE'\tCClF!:; iCN 32 263               PC/\t CLASSIFICATION:                 NS UNIT:             .
                                                           !\t?LEstENTES:          O f.: ".!?
SU\l\tARY DATE:           "" !4.!3 R EVISION:              0 MODIP" CATION TO REACTOR COOLANT SYSTEM (LC.) PER LL BULLETIN PROBLEM (R-  o-fl kmmarvi                                               '
Yhis change consisted in modifying the reactor coolant system pipe succorts inside
  -containment to comely with NRC !.E. Su!!etin 79-14 Safetv Evaluation:
7-is mod!!!:::!cn !s nuclear safe:y re!ated with no unreviewed safety cuestion.            I,e
   ~:c!!!ca:!:n and analysis has ensured tna: the design celteria of the ortg!nal o!cint system
::esq- ::cu .ents -ave been met and 9e accident er malfunc !on erobacilltv increased.
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PLANT CHANGE / MODIFICATION 82-269             PC/M CLA55tFICATION:                  NS UNIT:             4 IMPLEMENTED:               06/62/33 TURNED OVER DATE:                09-23-33

==SUMMARY==
DATE:                09-26-81 REVISION:               0 MM1 PICA"10N TO THE COMPONENT C00' NG WATER SYSTEM (IC) PER LL BL1        u nd M. ,4. room wu Cuw-40 h
This change consisted in modifylng the pipe supports in the component cooling water system inside containment to comply with NRC LE. Bulletin 79-14 Safety Evahastion his modification is nuclear safety related with no unreviewed safety question.            The ;
modification and analysts has ensured that the design criteria of the original plaing ivstem
::esign documents have been met and no accident or malfunction probability increased.         ,
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PLANT CHANGE / MODIFICATION 82-270             PC/M CLA551FICATION:                 N5 UNIT:            4 l
IMPLEMENTED:              05-16-83        ,

==SUMMARY==
DATE:               08-26-83 REVISION:             0
_m3:en AT10N TO CN880NENT COOLING WATF.R SYSTEM (LC.) PER LL SULLETIN 79 ,4. re    ' = Cuwd2 h
This PC/M consisted in modifying the Commment Cooling Water System pipe supports' Inside containment to comply with NRC LL lulletin 79-14.
Safety Evakaatlans                                                                               I This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
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    - m m _                            u         ,-     - - - -    ____
UNIT:             3&h IMPLEMENTED:               10 31-1)
TURNED CVER DATE:                   !! !4 33

==SUMMARY==
DATE:
                                                                                            !!-!! 33 REVISION:                1 EMERGENCY LIGHT 1NG MOUNTING MODIFICATION                                                     ,
Summary:
This PC/M provided the upgrading of mountings for emergency lighting units installed under PC/M 79-95 to an analyzed seismic design.                                                               l Safety Evaluationf This PC/M is classifled nuclear safety related only to the extent of insta!!!nl and verifying the seismic mounting of the emergency lighting units. The emergency lignting anits and their function are non safety related and are not used as an input into any safety related system. Therefore, it can be concluded that this PC/M does not involve an
     'anreviewed safety question.
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8

        . OY L4TMneEN9d ollAlcfMu1L9'1 3 Z -Z 73    ~ Mc2/G M                               N5           ,
UNIT:            6
                                                                !MPLEMENTED:             10 04-43 TURNED OVER DATE:                10 21 33

==SUMMARY==
DAT!:               10 24 33       l REVISION:            0           ;
t MOD MCAT"ON TO SAFETY N3ECT10N AND RESIDUAL HEAT REMOVAL SYSTEM                                   l i
(O.C.? PER 77-14. rmOm WM QM f
hmmacu                                         ,
This PC/M consisted in modifying the pipe supports on the Safety Injection and Residual          .
Heat Removal System outside containment to comply with NRC !.L Sulletin 7914.                    !
hfety Evaluatlans his modification is nuclear safety related with no unreviewed safety question.             Be modification and analysis has ensured that the design criteria of the arti;lnal piping system    !
design documents have been met and no accident or malfunction probability increased.
3
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l'1PLCMENT20:           !! !!.33 l                                                              TURNED OVCR DATE:               !? %33           1 I
SU'tMARY DATE:             10 -$! .1)       !
REV!SION:             0      _
j MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (o.c.) PER t.L 79 14_                                                                           .
            %mmaryt l
Thb PC/M consisted in modifying the pipe supports on the Chemical and Volume Control               ,
System outside containment to comply with NRC !.E. Bulletin 7914                                   l l           hfety Evaluationt l
Bis modification is nuclear safety related with no unreviewed safety quest!cn.                Be
!            9::l!! cat!cn and snalysts has ensured that the design critoria of the original plolng system das;3n documents have been met and no accident or malfunction probability Increased.              j i
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UNIT:            4 IMPLEMENTED:           05-23-43

==SUMMARY==
DATE:             08-26-33 REVISION:             0 MODIFICA710N "O SAFETY INJECTION AND PNUAL HEAT R8MOVAL SYSTEM LLCJ ra tt 3 r     i   ing 79.ig ,,r- - oge hammaryl                                               ,
This PC/M consisted in modifying the Safety inlection and Residual Heat Remova! System ins &de contaAnmerit to comply with NRC LL Bu!)etin 79-14 Sadaty Evahantians This modification is nuclear safety related with no unreviewed safety question.          The modification and analysis has ensured that the design criteria of the original piping system l design documents have been met and no accident or malfunction probability increased.
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PLANT CHANGE / MODIFICATION 82-278              FC/M CLASSIFICATIOPJ:                NS UNIT:           4 IMPLEMENTED:            05-25-83 TURNED OVER DATE:              10-12-83

==SUMMARY==
DATE:             10-20-83 REVISION:             0 MODIFICATION TO WASTE DISPOSAL SYSTEM (LC.) PER 79-14, PROBLEM WD-14 Summary:
This change consisted in modifying the pipe supports on the Waste Disposal System inside containment to comply with NRC LE. Bulletin 7,9-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. Tne modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
m D

am-m                                    .        .-
UNIT:           4 IMPLEMENTED:            11-03-83 TURNED OVER DATE:              11-23-33

==SUMMARY==
DATE:              11-29-83 REVISION:            0 MODIFICATION TO SAFETY IN3ECTION AND RESIDUAL HEAT REMOVAL SYSTEM' (O.C.) PER 79-14, PROBLEM 034 Summary:
This PC/M consisted in modifying the pipe supports on the Safety Injection and Residual Heat Removal System outside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.          Tne modifgcation and analysis has ensured that the design criteria of the original piping system desiggdocuments have been met and no accident or malfunction probability increased.
6

E PLANT CHANGE / MODIFICATION 82-284            PC/M CLASSIFIC.,!;CN:                NS UNIT:            4 IMPLEMENTED:             05-25-83

==SUMMARY==
DATE:               08-15-83 REVISION:             0 MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER 79-14, PROBLEM RTD-4 Summary:
This PC/M modified the pipe supports on the Reactor Coolant System inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
_T

PLA$'T CHANGE /\10DlFTCAT1-]N 32-235           PC/\1 CL ASSIFICATION:               NS UNIT:          a I\1PLEi!ENTED:           05-10-S3 SUM \1ARY DATE:            37-19-S3 REVISION:          0 MODIFICATION TO REACTOR COOLANT SYSTEM (LC.) PER LE. BULLETIN PROBLEM
( RTD-6)
Summary:                                               .
This change consisted in modifying the reactor coolant system ploe succorts inside containment to comply with NRC I.E. Bulletin 79-14 Saferv Evaluation:
This modification is nuclear safety re!:ted with no unreviewed safety question.                The modification and analysis has ensured that the design criteria of the original cloing system design documents have been met and no accident or malfunction orobability increased.
  +
9

PLANT CHANGE / MODIFICATION 82-290              PC/M CLASSIFICATION                 N5      -
UNIT.           3 IMPLEMENTED             12-14-83 TURNED OVER DATE:              01-06-84

==SUMMARY==
DATE:             01-09-84 REVISION:            0 MODIFICATION TO S.L AND RHR SYSTEM (O.C.) PER LE. 79-14 (PROBLEM-033)
Summary:
PC/M consisted in modifying the pipe supports for the Safety Injection and Residual Heat Removal System outside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
l l
l

PLANT CHANGE / MODIFICATION 82-297               PC/" C'_ASSIFICATION:          NS UNIT:      3 IMPLEMENTED:       12-16-83 TURNED OVER DATE:         02-01 84

==SUMMARY==
DATE:         02-01-84 REVISION:        1 REPLACEMENT SOLENOID VALVES AND LIMIT SWITCHES Summary:-
This modification consisted of replacing safety related NAMCO limit switches and ASCO solenoid valves with fully qualified and documented ASCO Catalog NP-1 solenoid valves.
Qualified and documented Conax electric conductor seal assemblies (ECSAs) are utilized to maintain the environmental and electrical integrity of replacement limit switch connections. These changes are a result of NRC IE Bulletin 79-01B, Environmental Qualification of Electrical Equipment Review.
Safety Evaluation:
This PC/M !s safety related as it replaces safety related limit switches, solenoid valves and electric conductor seal assemblies. The changes brought about by the PC/M do not involve an unreviewed safety question as this modification does not affect, create or increase any accident / malfunction already addressed, or new, in the FSAR.

UNIT:       3 IMPLEMENTED              10-29-83 TURNED OVER DATE:                11-23-83

==SUMMARY==
DATE:              11-30-83
                                            .                   REVISION:              0 REMOVAL OF CONTAINMENT PRESSURE WIDE RANGE INSTRUMENTATION Summary:
The purpose of this modification was to provide documentation and drawing changes necessary for the removal of transmitters PT-1622 and PT-1623 and their power supplies, and pressure indicators PI-1622 and PI-1623. In addition, the DDPS inputs for contain-ment pressure monitoring from the 1622 and 1623 loops will also be deleted. New pressure transmitters were added by PC/M. 79-132A and 133 A.
Safety Evaluation:                                                             .
This removal will not involve an unreviewed safety question because no system functions will be affected. PC/M 79-132A and 133A have added redundant containment pressure monitoring; therefore, the probability of occurrence or the consequence of an accident or malfunction important to safety previously evaluated in the FSAR has not been increased.
For the same reasons, no possibility for an accident or malfunction of a different type from any evaluated previously in the FSAR has been created by this modification.
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ar-mo_     egw,gshwaarusannera              e; UNIT:         3 IMPLEMENTED:        11-26-83 TURNED OVER DATE:          11-28-33

==SUMMARY==
DATE:          11-30-33 REVISION:           1 INSTALLATION OF THERMOWELLS ON LP TURBINE CROSSOVER PIPING Summary:
This PC/M installed thermowells on each MSR outlet pipe just above the existing platform to make the gathering of temperature data possible.
Safety Evaluation:
This is a non-nuclear safety related PC/M. The installation of thermowells on this piping does not affect any safety related equipment or function.

UNIT:          4 IMPLEMENTED:          11-08-83 TURNED OVER DATE:           11-2S-83

==SUMMARY==
DATE:           11-30-83 REVISION:           1 TURBINE SUPERVISORY INSTRUMENTATION Summa y     -
Tnis PC/M adds turbine supervisory instrumentation to monitor turbine performance and provide the data required to properly service and maintain the turbine.
Safety Evaluation:
Tne turbine supervisory system is not a safety related system.        The mounting of the recorders, tachometer, and an acceleration meter to RTG boards 4C04 and 4C02 make the package a safety design feature. The new system does not introduce any new safety cuestions or change the evaluation study already done.

                                             .-        m                           -
UNIT:                 3&4 IMPLEMENTED:                  09-26-83 TURNED OVER DATE:                  10-06-83

==SUMMARY==
DATE:                   10-19-83 REVISION:                      O LOCKED HIGH RADIATION AREA ACCESS ALARM Summary:
This modifications required to install an alarm system for the LHRAs are as follows:
: 1. An audible alarm that reminds a person entering / exiting the. area to secure the door / gate.                                ,
: 2. A visual alarm that serves to alert Health Physics (HP) personnel in the area to the fact that a LHRA door / gate is open.
: 3. Five control boxes each provided with 120 VAC power from local distribution or lighting panels and connected to a maximum of six doors / gates that are in the near vicinity of their respective control box.                                           .
I    4    The use of 12 VDC between the control box and system commponents to reduce the hazard if wiring is damaged.
This alarm system has been designed as a commitment to the NRC following recent audits
 ,    by FP&L QC and NRC inspectors. During these inspections, doors / gates at posted LHRAs have been found unlocked.
Safety Evaluation:
Tnis non-nuclear safety related modification adds a system that does not affect the operation of any other system. It is merely to inform or alert personnel to the fact that LHRA door / gate is open and remind them that this door / gate should be locked and secured behind them. If the alarm system malfunctions, there would be no change in operations or procedures from that of the previously existing setup. The control boxes are wall mounted and locked in an area such that their failure would not interfere with safety related equipment / components. This alarm installation does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important i     to safety, previously evaluated in the FSAR. Nor does it create the possibility for an accident or malfunction of a different type than evaluated previously in the FSAR.
l l      Finally, this alarm installation does not reduce the margin of safety as defined in the basis for any Technical Specification. Therefore, no unreviewed safety. question is posed.
i

rum u-naan~         -   "         ---
PLANT CHANGE 7sf0DIFICATION 33-w _
UNIT:      3&4 IMPLEMENTED:         09/06/83        l TURNED OVER DATE:           09-21-83        l

==SUMMARY==
DATE:          09-26-83        l REVISION:          O LIGHTNING PROTECTION
 ' Summary:
Additional lightning protection is being installed on the control room and diesel generator buildings to enhance existing system.
Safety Evaluation:
The lightning protection system does not perform any safety related function and due to its location, no new accident possibility or equipment malfunction can affect any safety related equipment. The probability of occurrence or the consequences of design basis accident or malfunction of safety related equipment previously evaluated in the FSAR has not been increased. There is no possibility of accident or malfunction different from those previously evaluated. Based on the above, this PC/M is non-safety related and does not involve an unreviewed safety quefstion.
e

PLANT CHANGE / MODIFICATION 83-14                PC/M CLASSIFICATION:       NNS OA/OC UNIT:      3&4 IMPLEMENTED:        11-28-83 TURNED OVER DATE:          12-06-83

==SUMMARY==
DATE:          12-08-83
* REVISION:         0 FIRE WATER ISOLATION Summary:
Tnis PC/M added four isolation valves in strategic locations between PIVs (Post Indicator Vaives) 24 and 29. The new isolation valves will enable sections of fire water piping in Unit 3 and Unit 4 turbine building and the auxiliary building to be isolated for maintenance.
Safety Evaluation:
The fire water isolation valve pipe supports do not perform a nuclear safety related function and are located away from safety related structures, equipment, and components. Analysis has shown that no new supports or modifications to existing supports are required. Therefore, the probability of occurrence or the consequences of a design basis accident or malfunction of equipment important to safety of the piant has not been increased. This PC/M does not pose any unreviewed safety questions.

        ?'.' ANT CHANGE / MODIFICATION 83-15           PC/M CLASSIFICATION:               NNS UNIT:        3&4 IMPLEMENTED:          !!-06-83   r TURNED OVER DATE:             11-29-33 .

==SUMMARY==
DATE:           ii-30-83 REVISION:           0
       -REPLACE METEROLOGICAL RECORDER WITH TRACOR WESTRONICS Sum' mary: .                                                                         .
     ' This PC/M consisted in replacing the existing meterological recorder with one of higher quality and reliability.
Safety Evaluation:
Tais modification is non-nuclear safety related with no unreviewed safety question.
Replacement recorder meets all material specifications, performance parameters and design c:sde and determined to be equivalent or better than the original recorder.
f i
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PLARfif CilGRN@Ld/QBODI?lCAW@M }N-IV           1 K C T MI @ L A E Ml0P W M M C   N ~ -- -  R UNIT:        3 IMPLEMENTED          11-01-83 TURNED OVER DATE:            11-23-33 SU.'.tM ARY D ATE:     11-29-33 REVISION:         0 ILRT CONTAINMENT PENETRATION FLANGE REPLACEMENT SummarYt This PC/M increased the flange connection at penetration //65 from 6" to 8" and allows increased flow rates for pressurizing and depressurizing the containment during integrated leakage rate tests.
Safety Evaluation:
This is a safety related PC/M which does not involve an unreviewe) safety question because this modification brought the penetration into agreement wi, :h existing design documents which have been previously evaluated for safety.
n

PLANT CHANGE / MODIFICATION 83-19                 PC/M CLASSIFICATIONa            NN5 UNITS          3 IMPLEMENTED:        12-20-33 TURNED OVER DATE:           02-01-34

==SUMMARY==
DATE:          02-01-34 REVISION:          1 SPENT FUEL POOL GUARD SHACK Summary:
This PC/M provided the addition of a newly constructdd guard shack on the roof of the new fuel storage building on Unit 3. The purpose of this PC/M is to provide adequate shelter for security personnel during inclement weather.
Safety Evaluation:
This PC/M is not nuclear safety related nor poses any unreviewed safety question. There is no possibility of an ac'cident occurring because of the placement of a guard shack on the new fuel storage building. This can be assured as long as all codes and specification requirements are tulfilled.

r v, m v-nasu iv. s , ~. ,       ,. s  ..m PLANT CMAN0n/MODII iLAlivN e>-ev UNIT:        4 IMPLEMENTED             12.20-83 TURNED OVER DATE:                02-01-84

==SUMMARY==
DATE:             02-01-84 REVISION:          1 SPENT FUEL POOL GUARD SHACK Summary:
This PC/M provided the addition of a newly constructed guard shack on the roof of the new fuel storage building on Unit 4. The purpose of this PC/M is to provide adequate shelter for security personnel during inclement weather.
Safety Evaluation:
This PC/M is not nuclear safety related nor poses any unreviewed safety question. There is no possibility of an accident occurring because of the placement of a guard shack on the new fuel storage building. This can be assured as long as all codes and specification requirements are fulfilled.

PLANT CHANGE / MODIFICATION 83-21                      PC/M CLASSIFICATION:               NS UNIT:        4 IMPLEMENTED:           06-10-83

==SUMMARY==
DATE:            08-26-83 REVISION:       0 MODIFICATION TO CONTAINMENT SPRAY SYSTEM (LC.) PER LE. BULLETIN 79-14, PRMLEM 058B Summary:
This PC/M consisted in modifying the Containment Spray System pipe supports inside containment to comply with NRC LE. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.                 The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION 83-27              PC/M CLASSIFICATION:             NNS UNIT:          4 IMPLEMENTED:          03-21-83 TURNED OVER DATE:           10-27-83

==SUMMARY==
DATE:           10-27-83 REVISION:           0 MSR STEAM VALVE INLET TIMING VALVES Summary:
This CPWO modifies CV-4-3710 and CV-4-3713 which controF the flow of steam into the A and D moisture separator reheater. The modification consists in removing the valve internals and placing a bottom cap on both top and bottom of the valve body. this essentially removes the valves, control of steam into the affected moisture separator reheaters will be done by manually opening the corresponding MOVs: MOV-4-1431 and MOV-4-1434 In addition to the above mechanical modification, the control circuits to MOV-4-1431 and MOV-4-1434 is to be modified to prevent remote opening of these valves. The c!osing circuits are not changed and will still be possible to close them remotely. This is a temporary operation. Valves will be returned to normal once new/ rebuilt internals for CV-4-3710 and CV-4-3713 are available.
Safety Evaluation:
This modification is not safety related as it does not affect any safety related system or feature in the plant. Furthermore, it does not involve an unreviewed safety question as this modification does not affect, create, or increase any accident / malfunction already addressed or new in the FSAR.

PLANT CHANGE /M '. i.'ICATION 83-28              PC/M CLASSIFICATION:            NNS UNIT:         3 IMPLEMENTED:         12-12-83 TURNED OVER DATE:           01-09-84

==SUMMARY==
DATE:           01-11-84 REVISION:          0 Alternate Gas Supply for the Flux Manoer System Summary:
This PC/M provided an alternate source (permanently piped) of inert gas supply for the Flux Mapper System on Unit 3. This design calls for the use of N2 gas from the nearby N2
  'supoly to the SI accumulators. This provides a constant source of N 2, more than adequate for the needs of the Flux Mapper System.
Safety Evaluation:
This DC/M is non-nuclear safety related and failure or malfunction of this alternate gas supply will not affect safety related systems, components, and structures. All portions of this design are seismically supported to preclude interaction with safety related equipment during a seismic event.
With respect to the probability of occurrence of accident seriously evaluated in the FSAR:
the probability of occurrence or the consequences of a design basis accident or malfunction of equipment important to the safety of the plant previously evaluated in the FSAR, has not been increased. Therefore, this PC/M does not pose any unreviewed safety questions.

CPWO PLANT CHANGE / MODIFICATION 33-29               PC/M CLASSIFICATION:                 NS UNIT:           3&a IMPLEMENTED:             03-12 83

==SUMMARY==
DATE:              09-01-33 REVISION:              0 EMERGEtiCY DIESEL GENERATOR A & B RELAY REPLACEMENT Summary:
This modification involved the replacement of Agastat Relay //2412PE for an equivalent substitute //7012PE at "A" emergency diesel generator control panel.
Safety Evaluation:
This CPWO is nuclear safety related but does not adversely af fect any sa.fety relatec system or feature in the plant. Furthermore, it does not involve an unreviewed safetv questian as this modification does not affect, create or increase the procacility of occurrence of any accident / malfunction already addressed, or new in the C S A R.

                                                                                                                                                       ~
PLANT CHANGE / MODIFICATION 83-32                                                 PC/M CLASSIFICATION- [                                        NNS UNIT:  ,
3&4
                            ,                                                                   IMPLEMENTED:                                  02-01-84 TURNED OVER DATE:                                        01-17 8u

==SUMMARY==
DATE:                                  02-24-8a REVISION:                          0 INSTALLATION OF PLANT VENT FLOW MONITOR Summary:
This PC/M consists of adding a piant vent stack flow monitor (FE-6584 & FT-65Sk) at the stack (El.174'-6") and a square root extractor (FY-6584) at the Eberline Spring 4 monitor (RAD-6304) elevation 13'-0" in the HVAC Room. The purpose of this PC/M !s to provide a means to monitor stack flow.
Safety Evaluation:
This DC/M is classified as non-nuclear safety related. It has no interconnections with any safety related system nor does it perform any nuclear safety related function. Tnerefore.
:his modification does not affect any equipment described in the FSAR.
                                                                                      -.-an---                  - - , . . - - - - , - . + ,        -,- .

PLANT CHANGE / MODI:1 CATION S3-37             PC/M CLASSIFICATION:        NNS OA-OC UNIT:          3 IMPLEMENTED:        12-09-33 TURNED OVER DATE:           12-15-33

==SUMMARY==
DATE:          12-16-83 REVISION:          0 REPLACEMENT OF RCP VIBRATION SENSORS MOUNTING BRACKET Summary:
This change replaces individual mounting brackets for the RCP vibration pick-ups with a single Westinghouse designed bracket on which all three probes can be attached. The existing brackets and vibration equipment were installed under PC/M 75-50. Tnis PC/M just replaces the mounting bracken.
Safety Evaluation:
The new bracket does not provide any nuclear safety related function nor does b :nange the design of the RCP seal assembly. Therefore, this modification does not avo;ve an unreviewed safety question.

PLANT CHANGE / MODIFICATION S3-39_              PC/\1 CLASSIFICATION:             NNS UNIT:      3 IMPLE\ TENTED:       !!-23-33 TURNED OVER DATE:            12-Es 3 St ".t'.t A R Y D A TE: 12 22 33 REVISION:       3 MOISTURE SEPARATOR REHEATER MODir:ICATIONS So m mar. :                                              -
This PC/\t provided addi:lonal baffling to eliminate steam channe!!ng :".reugh :: s .-c tube bundles to increase outlet steam temperatures. Tnere .vas no NRC c: .mi: est invcived with this PC/M.
Efetv Evaluation:
T5is modification is a non-nuclear safety related PC/\t, 1: dns n:: s!'e:: _.
co penents used to mitigate any accidents analy:ed in the T ;r':ey F'- Ti a R.
C: panents affec:ed are ou: side the pressure boundary.
L_

CPWO                                    l PLANT CHANGE / MODIFICATION 83 44                               PC/M CLASSIFICATIONg    NNS UNIT:
i l
IMPLEMENTED:   0 %i2-83

==SUMMARY==
DATE:   09-t3-33 REVISION:     0 i
L REPLACEMENT OP 40629 BREAKER                                     -
i 1
Sammary:                                                                                           I This CPWO involved the replacement of an existing ITE breaker with a Testinghouse                 {
breaker of the same electrical specifications. The breaker is used in the power feed for           ;
the 40 CRDM cooling fan motor. Breaker contacts were burned out.
Safety Evaluation:
I This change does not perform a nuclear safety question. It does not involve an unreviewec safety question as this modification does not affect, create, or increase any s:::cen.            3 ms!! unction already addressed or new in the FSAR.                                              l i
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PLANT CHANGE / MODIFICATION 83 46               PC/M CLASSIFICAT!ON:              NNS UNIT:            3 IMPLEMENTED:            10-19-33 TURNED OVER DATE:             10-27-33

==SUMMARY==
DATE:             10-27-33 REVISION:            0 RAISE LEVEL ALARM ON 5A AND 5B FEEDWATER HEATERS Summary:
This CPWO elevates the level alsrm tree on SA and 5B feedwater hesters for Unit 3. Tne feedwater hesters high level alarm targets are on continuously, negating the purpose of the alarm. Raising feedwater heater level tree will clear the s!srms and provide a correct status of the level which will enable the operators to take action in the esse of an actual level increase. This is an improvement design and no system characteristics have been changed.
Safety Evaluation:
Raising the feedwater hester S A and 5B level slarm tree !s not nuclear safety re::.ted because it does not perform sny safety function. The probability of oc:urrence or 9e consequences of a design accident or malfunction of equipment impor an to 9e safen of the plant previously evaluated in the FSAR, has not been incressed. For9e esse s discussed above, raising the feedwater hester level tree does not involve an ;nrev.e a ec safety question.
y

CPWa 83.47      PC/M CLASSIFIC ATION:                   NS PLANT CHANGE / MODIFICATION UNIT:                4 IMP!.EMENTED:               04.27.84 TURNED OVER DATE:                 05 14 34 SUMM ARY DATE:                05 29 84 REVISION:                 0 ICW CHECK VALVE REPLACEMENT Summaryr This modift ation consisted of replacin's the 24" check valves on the Intake Cooling Water System with one of greater corrosion resistance (ductile iron to nickel aluminum bronze alloy).                                              ,
Safety Evaluation:
This change does not involve an unreviewed safety question because it does not affect or increase the probability nor the consequences of any accident or equipment malfunction previously evaluated in the FSAR and, it does not create the possibility of malfunction of equipment not considered in Chapter 14 of the FSAR. Also, this change does not decrease any margin of safety discussed in the Technical Specification basis.
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PLANT CHANGE / MODIFICATION 83-48                PC/M CLASSIFICATION:          NNS UNIT:         3 IMPLEMENTED:       12-19-83 TURNED OVER DATE:         01-09 84

==SUMMARY==
DATE:       01-09-84 REVISION:         1 MOISTURE SEPARATOR REHEATER IMPtNGEMENT PLATE LINER Summary:
This modification provided the replacement of an impingement plate within the moisture separator reheater hemi-head beneath the main steam inlet nozzle.
Safety Evaluation:
The moisture separator reheater vessel is non-safety related and the work additional!v does not involve the pressure boundary. The mod;fications do not increase the ::ossibility or extent of any previously analyzed accident nor create new or unanaly:ed accident not provided for in the FSAR and do not affect the Plant's Technical Soecifi:ations.
Therefore, this modification does not involve an unreviewed safety question.
i

83-51      FC/M CL 2.SSIFIC ATION:       NNS PLANT CHANGE / MODIFICATION UNIT:     3 and u IMPLEMENTED:        03_ % 3t TURNEO OVER D 2.TE:      Oc.;6.ss SL'MMARY D ATE:       Ga-t9 Sc REV!SION:         0 FIRE SPRINKLER SYSTEM FOR CONTROL POINT GUARD HOUSE Summary:                                      .
This modification provided a fire protection sprinkler syatem in the recently built radiation control area access point guard house.
Safety Evaluation:
Although this PC/M is non-nuclear safety related, the associated pioing is seis ntes!!v supoorted to insure that affects are imoosed on nearby safety related systems. Tnerefo e.
no orobability or consequences of any accident or equipment malfunct:en, orev;ous!.
addressed in the FSAR, !s increased. Furthermore, no margin of safety :s secrease an:
no unreviewed safety question is posed.

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PLANT CHANGE /MODIFICATIGN7hAN UNIT:                3 IMPLEMENTED:                02-01-se TURNED OVER DATE:                    02-27-84

==SUMMARY==
DATE:                03-01 -Su REVISION:               1 EOUIPMENT HATCH PLATFORM Summary:
The equipment hatch platform was extended so hard to reach bolts are more accessible.
l Safety Evaluation:
The equipment hatch work platform does not perform a nuclear safety-related function.
However, since they are being installed inside a Class I structure and in order to cerc!ude the possibility of impacting safety related equipment or components during a seismic                      Tne event, the platforms have been designed to withstand all aoplicable scismic loads.                             j structural integrity of the equipment hatch was unaffected.
l s.

PLANT CHANGE / MODIFICATION 83-56               ?C/M CLASSIFICATION:                        NNS UNIT:      3 IMPLEMENTED:          08-22-83

==SUMMARY==
DATE:          08-23-83 REVISION:      O CONDENSER HOTWELL PIPE MODIFICATION Summary:
The suoject modification shortens the condenser hotwell drain pipe. This crain line discharges to the cooling canal and is shortened .to prevent possible seawater incuction into the hotwell and resultant chloride contamination of the steam generators.
Safety Evaluation:
This non-nuclear safety related modification does not affect any safety related' systems, structures, or components. No increase in the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR results. No possibility for an accident or malfunction of a different type previously analyzed in the FSAR results. The margin of safety as defined in tne casts for any Technical Specification is not reduced.
       . . - -     , . , . .                   - . , . - - - . . .   .-.,_-.-r      -,.,m

PLANT CHANGE / MODI.CICATION 33-57             PC/M CLASSIFICATION:             NNS UNIT:          4 IMPLEMENTED:         08-22-83

==SUMMARY==
DATE:           08-23-83 REVISION:          O CONDENSER HOTWELL P!PE MODIFICATION Summary:
The subject modification shortens the condenser hotwell drain pipe. This drain line discharges to the cooling canal and is shortened to prevent possible seawater induction into the hotwell and resultant chloride contamination of the steam generators.
Safety Evaluation:
This non-nuclear safety related modification does not affect any safety related systems, structures, or components. No increase in the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR results. No possibility for an accident or malfunction of a different type previously analyzed in the FSAR results. He margin of safety as defined in the basis for any Technical Specification is not reduced.

CPWO
- PLANT CHANGE / MODIFICATION 83-60              PC/M CLASSIFICATION:              NNS UNIT:          s IMPLEMENTED:           03-2L-33

==SUMMARY==
DATE:           09-!5-S3 REVISION:            0 4A MOISTURE SEPARATOR REHEATER DP! INSTALLATION Summary:
This modification installed a differential pressure indicator between PI-l410 and P!-!511 on the moisture separator reheater to measure the shell side pressure drop to verify tne AP is within the design vendor specifications.
Safety Evaluation:
This modification is non-nuclear safety related as it does not alter the performance of a ,y safety related equipment. Therefore, the change does not increase the probability of occurrence of an accident or malfunction of equipment linportant to safety prev:cuse,.
evaluated in the FSAR; thus, posing no unreviewed safety question.
D

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Sa'ety Evaluation:
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PLANT'dHANGE/ MODIFICATION             83-70      PC/M CLASSIFICATION: N NS -O A/OC UNIT:          4 IMPLEME.'tTED:       03-26-84 TURNED OVER DATE:          04-16-84
                                                ~

==SUMMARY==
DATE:         04-17-84 REVISION:           0 REACTOR HEAD SHIELDING Summary:
This PC/M installed a permanent support structure in which, temporary lead blankets will
  'be installed on the Reactor Head during outages to provide gamma dose reduction for individuals working around the reactor vessel head area.
Safety Evaluation:
This PC/M is non-nuclear safety related since the shield system serves no safety related function. Since the only safety related system or component which the permanently attached structure (indirectly) interfaces with is the reactor vessel and its only affect is a slight load on the lift lugs, it can be concluded that the small stress at the lift lug does not pose any unreviewed saftey question.

PC/M CLASSIFICATION:           NNSR PLANT CHANGE / MODIFICATION 83 74 UNIT:         3 IMPLEMENTED:         09-22-83 TURNED OVER DATE:          01-09-84

==SUMMARY==
DATE:          01-09-84 REVISION:         I WDS CONDENSATE RECOVERY PUMP "A" BREAKER REPLACEMENT Summary:
The 3A WDS auxillary steam condensate recovery pump motor was changed from 3 HP to 7.5 HP due to the unavailability of a replacement motor. Therefore, due to the increased motor size, the existing power cable, circuit breaker and overload relay heaters were replaced in order to accommodate the increased electrical load.
Safety Evaluation:
This PC/M involves replacing existing equipment (motor, breaker, cable and overload heaters) with properly sized equipment in order to account for the increase in electrical load. The motor is non-safety related as it does not affect any safety related system or feature in the plant. Furthermore, PC/M 83-74 does not involve an unreviewed safety question as this modification does not affect, create or increase the probability of occurrence of any accident / malfunction _already addressed, or new, in the FSAR.

CPWO                                    -
PLANT CHANGE / MODIFICATION 83-82_               PC/M CLASSIFICATION:           NNS
                      ""                                              UNIT:         3 IMPLEMENTED:      _
10-23-S3 TURNED OVER DATE:          12-r-33

==SUMMARY==
DATE:         12-12-S3 REVISION:         O GENERATOR CONDITION MONITOR OIL / MOISTURE TRAP BOWL REPLACEMENT Summary:
This modification involved the replacement of the existing Environment /One' Corporation P/N A-1012A-114 PL plastic bowl with one that was stainless steel at the Generator Condition Monitor System P/N A-1012A-114 PZ, thus preventing a potential fire hazard due to the plastic bowl breaking.
Safety Evaluation:
This modification is non-nuclear safety related as it does not affect any safety related system or feature in the plant. Furthermore, it does not involve an unreviewed safety questi'on as this modification does not affect, create, or increase the probability of occurrence of any accident / malfunction already addressed or new in the FSAR.

CPWO PLANT CHANGE / MODIFICATION              83-83          PC/M CLASSIFICATION:                         NNS UNIT:     4 IMPLEMENTED:                   03-26-34 TURNED OVER DATE:                      05-23-84

==SUMMARY==
DATE:                    06-06-84
                                                                     .           REVISION:               O GENERATOR CONDITION MONITOR OIL / MOISTURE TRAP BOWL REPLACEMENT Summary:
This modification involved the replacement of the existing Environment /One Corporation P/N A-1012A-114 PL plastic bowl with one that was stainless steel at the Generator Condition Monitor System P/N A-1012A-Il4 PZ, thus preventing a potential fire hazard due to the plastic bowl breaking.
Safety Evaluation:
This modification is non-nuclear safety related as it does not affect any safety related system or feature in the plant. Furthermore, it does not involve an unreviewed saferv question as this modification does not affect, create, or increase the orobability of occurrence of any accident / malfunction already addressed or new in the FSAR.
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PLANT CHANGE / MODIFICATION                    33-84 PC/M CLASSIFICATION: _                        NNs UNIT:                                    3 IMPLEMENTED:    02-02-3:.
TURNED OVER DATE:      03-21-8t.

==SUMMARY==
DATE:      03-26-80 REVIslON:                                   0 1
1 MOISTURE SEPARATOR / REHEATER TIMING VALVE RELOCATION Summary:
Tnis design provided a bypass loop for the Moisture Separator / Reheater Temperature Control valves. These valves are used to control the ramp rate of temperature rise of the reheat steam. Relocation of these valves was provided to divert flow from these valves during operation to reduce wear on the internals. The valves will pass steam only during startup and shutdown of the secondary plant.
Safety Evaluation:
This is a non-nuclear safety related design change. The malfunction of tnis system will not affect safety related systems, components and structures. All portions of connecting piping are non-safety related.

PC/M CLASSIFICATION:              NNS PLANT CHANGE / MODIFICATION 83-87 UNIT:          4 IMPLEMENTED:           08-05-83

==SUMMARY==
DATE:-           08-13-83 REVISION:           O GROSS MVAR TELEMETERING Su.nmary:
This modification involved the installation of a cable to pick up an existing gross megavar signal in the data acquisition package and br.ing this signal to the RTU (Remote Terminal Unit). The RTU will transmit this signal via telephone lines to the System and Division Dispatch for their reference.
Safetv Evaluation:
This modification is non-nuclear safety related as it does not affect any safety relate:
systems or features in the plant. All previous applications of the data acquisition package and the RTU will not be affected. Furthermore, it does not involve an unreviewed safet'.
question as this modification does not affect, create or increase any accident /malfunctier already addressed or new in the FSAR.
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CPWO PLANT CHANGE / MODIFICATION 83-90               PC/M CLASSIFICATION:             NNS UNIT:        3 & 'a IMPLEMENTED:        08-25-83

==SUMMARY==
DATE:         09-01-33 REVISION:           0 WTP STRAINER FOR MIX BED DEMINERALIZER Summary:
This change involved the addition of in-line conical strainers for the discharge of the A and B mix bed demineralizers of the Water Treatment Plant. The new strainer acts as a back-up filter to prevent the ingress of resin from the mixed bed demineralizers to the primary and secondary water systems.
Safety Evaluation:
This change is non-nuclear safety related as it does not affect any safety related svs:e -
or feature in the plant. Furthermore, it does not involve an unreviewed safety quest.: a this modification does not affect, create or increase the probability of occurrence of ~.
accident / malfunction already addressed, or new in the FSAR.

PLANT CHANGE /MOC*EC3. TION                                             33-91                     PC/M CLASSIFICATION:                                               NS UNIT:                            4 IMPLEMENTED:                             04-19-34 TURNED OVER DATE:                                        05-18-84                                  l

==SUMMARY==
DATE:
06-04 84 REVISION:                             0 f
SERVICE AIR CHECK VALVE REPLACEMENT Summary:                                                                         ,
This PC/M replaced the service air check valve //205. The valve previously serving in this capacity had a problem with leakage.
Safety Evaluation:
The PCCE in the CPWO package verifles that the new valve is acceptable as a replacement.               This CPWO does not have a detrimental effect on any plant system or component important to safety and, therefore, does not involve any unreviewed safety                                                                                                                       l question.
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PLANT CHANGE / MODIFICATION 83-94                  PC/51 CLASSIFICATION:           NS L                                                                               UNIT:         3 hiPL2Ni2NT20:       11-01-33 l
i TURNED CVER DATE:          !!-M-S3 l                                                                  SUNtNtARY DATE:       1!-!3-53 REVISION:          0 i
l         4160 VOLT SWITCHGEAR ADDITIONAL BRACING t
l-        Summary!
This PC/m installed additional short circuit bracing in the 4160 volt switchgear to provide the intended short circuit (momentary) capability of 30,000 amps.                            ;
I Safety Evaluation:
This modification is nuclear safety related. It will not adversely affect the opers:;o , of i          the 4160 volt switchgear as it will not change the seismic capability of the switchgear .or l         does it create the possibility of another failure mode. Therefore, it can be cone:vdec :*.s:
i          this PC/St does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 3k95                  PC/'.'. T.ASSIFICATION:         NS UNIT:         4 NPLEMENTED:        05.09.84 TURNED OVER DATE:           05 13 84

==SUMMARY==
D ATE:       06.06.34 REVISION:         0 4160 VOLT STTTCHGEAR ADDITIONAL DR ACING Summary:                                                      -
This PC/M installed additional short circuit bracing in the 4160 volt switchgear to orovide the intended short circuit (momentary) capability of 30,000 amps.
Safety Evaluation This modification is nuclear safety related. It will not adversely affeet the coerstion of the 4160 volt switchgear as it will not change the seismic capability of the switchgest nor does it create the possibility of another failure mode. Therefore,it can be concluded that this PC/M does not involve an unreviewed safety question.

PC/M CLASSIFICATION:       NNS OA OC PLANT CHANGE / MODIFICATION 83-110 UNIT:                       3 IMPLEMENTE.D:        12 05 83 TURNED OVER DATE:         01-09-34

==SUMMARY==
DATE:         01-09-84 REVISION:                        0 COVERS FOR CHERRY PICKER ANCHOR BOLTS hmmerYt The cherry picker anchor bolt covers were installed to protect the cherry picker anchor bolts from damage by rolling equipment or accidental load drops. "Ihese removable covers are located over the three pedestal crane tower anchor bolt groups on the 53 ft. elevation
<    in the Unit 3 containment.
Safety Eva6 tion:
The anchor bolt covers have no affect on the nuclear safety related structures, systems or components. The anchor bolt covers produce an additional equivalent surface area of approx!mately 119 square feet of carbon steel l/8" thick exposed one side in the containment. This will have negilglble effect on the ECCS analysis per FSAR Aopendix C.
8

PC/M CLASSIFICATION:             NS PLANT CHANGE / MODIFICATION 83-120 UNIT:         3 IMPLEMENTED:        01-04-84 TURNED OVER DATE:          02-01-84

==SUMMARY==
DATE:         02-01-84 REVISION:           1 MECHANICAL STOPS FOR CONTAINMENT PURGE VALVES SummarYt This PC/M changes the existing IM inch diameter stops to a 2 inch diameter stop. Also, the PCV which was to be installed in Pc/M 79-128 will be replaced with a manually operated needle valve to control (limit) the purge valve opening to 3 inches per second.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or marfunction of equipment important to the safety of the plant, previously evaluated in the FSAR, has not been increased. There is no possibility of an accident or malfunction different than those prevlously evaluated. Therefore, it can be concluded that this PC/M does not pose any unreviewed safety questions.
L_

CPWO
  ' PLANT CHANGE / MODIFICATION S3-111              PC/M CLASSIFICATION:             NNS UNIT:          3 IMPLEMENTED:         OS-03-83

==SUMMARY==
DATE:          09-06-83 REVISION:           O CONDENSATE POLISHING SYSTEM 24V DC POWER SUPPLY Summary:
This CPWO involved mounting a common bus bar for modules being powered by a 24V DC power supply in the condensate polishing system. It involves mounting two 1" x 1/4" bus bars (99" and 34" in length, connected by approximately twelve feet of #2 AWG wire) pe-unit in order to provide a common bus for the negative 24V DC wire run.             This will compensate for the voltage drops across the modules, thus maintaining the loop tolerance of 1.02V DC drop.
Safety Evaluation _:
This CPWO is not nuclear safety related as it does not affect any safety related system er feature in the plant. Furthermore, it does not invlove an unreviewed safety cuestio . :s this modification does not affect, create. or increase the probability of occurrence of an.
accident / malfunction already addressed, or new, in the FSAR.
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CPWO PLANT CHANGE / MODIFICATION 83-122             PC/M CLASSIFICATION:             NNS UNIT:      Common IMPLEMENTED:          08-03-33

==SUMMARY==
DATE:            08-11-83 REVISION:          0 EMERGENCY FEEDER TO MCC RB (TEMPORARY)
Summary:   ,
This modification involved the temporary change (until 10-83) of the feeder cable to the MCC RB (radwaste) from LC3B to LC4C because existing feeder (D A) was found. to be grounded.
Safety Evaluation:
This CPTO is non-nuclear safety not affecting any safety related system or feature :n : .e piant. Furthermore, it does not in"oive an unreviewed safety question as this moctitca-tion does not affect, create, or increase the prot; ability of occurrence of any acc:c:,:
malfunction already addressed, or new, in the FSAR.

PLANT''CHANGE/ MODIFICATION U-ID              N M " '" " " '                    '-
UNIT:         3 IMPLEMENTEDI          12-30-33 TURNED OVER DATE:          02-17-8h

==SUMMARY==
DATE:          02-24 83 REVISION:         O PRESSURIZER RELIEF VALVE CABLE RELOCATION Summary:
This PC/M replaced the degraded cables for MOV 3-535, 536 and PCV 3 255C anc 256.
Safety Evaluatiom The only change is the replacement of existing cable with an improved type of environmentally qualified cable. Therefore, the probability of occurrence of an ace:cen:
previously evaluated in the FSAR is not changed. The consequences of an accicen:
previously analyced in the FSAR would not be altered. It does not create the possibili y of an accident not considered in the FSAR.
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PLANT CHANGE / MODIFICATION 83-130                PC/M CLASSIFICATIONI           NNS UNIT:         3 IMPLEMENTED:         05-01-84 TURNED OVER DATE:          05-25-84

==SUMMARY==
DATE:         06-04-84 REVISION:          0 240 KV DIGITAL METER Summary:
his PC/M added a digital meter with greater accuracy for 240 KV switchyard voltage installed on control board 3C04.
Safety Evaluations, This PC/M is not safety related and has no effect on safety related systems.            De probability of occurrence or the consequences of an accident or malfunction previous!v evaluated in the FSAR has not been increased.
Affected Drawings:          NOTE: This section may be affected by the drawing verification / update phase of the plant documentation 3PE-C-83130-001                  update. A summary revision will be issued to document 5610-M-301-12 Rev 15             any changes.

PLANT CHANGE / MODIFICATION D-131             PC/M CLASSIFICATIONS           NNS UNIT:         4 IMPLEMENTED 2        05.01 84 TURNEO OVER DATE:          05-25-84

==SUMMARY==
DATE:         06 04 34 REVISION:          0 240 KV DIGITAL METER Summary:
This PC/M added a digital meter with greater accuracy for 240 KV switchyard voltage installed on control board 4C04.
Safety Evaluation:
This PC/M is not safety related and has no effect on safety related systems.        The probability of occurrence or the consequences of an accident or malfunction previousP.
evaluated in the FSAR has not been increased.
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CPWO PLANT CHANGE / MODIFICATION 83-134              PC/M CLASSIFICATION:               NNS UNIT:           4 IMPLEMENTED:          08-13-83

==SUMMARY==
DATE:           08-13-33 REVISION:            0 THRUST RING REPLACEMENT POR CHECK VALVE 4-312A Summary:
This modification consisted in replacing the thrust ring for check valve 4-312A which was leaking externally. Due to time restrictions and lack of available spare parts, it was decided to replace the original thrust ring with one having the same inside and outside diameters and tolerances, but with twice its original length.              This extra length (approximately 1/3") should move the gasket downward enough to clear the two scratches and thus prevent possible leakage between the gasket and the stainless steel inlay surfaces. It is important to note that the scratches observed on the stainless steel inlay surface are aproximately the length of the gasket as located in its original position.
Safety Evaluation:
The probability of occurrance or the consequences of a design basis accident er malfunction of equipment important to the safety of the plant, previously evaluated in tne FSAR, has not been increased. There is no possibility of an accident or malfunction different than those previously evaluated. This CPWO does not reduce the margin of safety previously defined in the FSAR or Technical Specifications. Based on the above, !t can be concluded that this CPWO is non-safety related and does not pose an unreviewee safety question.
~ _ . _ _ _ _ _ . _ _ _ _ _ _ _

                                             .35      PC/M CLASSIFICATION:              NNS         l PL ANT CH ANGE/'.10DIFICAT10'. >
UNIT:         3 s'< k      l l
IMPLEMENTED:          09 13 33 TURNED OVER DATE:             09-14-13

==SUMMARY==
DATE:           09-13 33      f REVISION:            0 I
SECURITY LIGHTING HANDHOLE #514 ELIMINAT10N                                                ,
                                                                                  ,                   t Summarvt This modification provided for the elimination of security lighting handhole //514 which will become inaccessible due to the addition of an access ramp to the new drum storste building.                                                  ,
1 i
r Safetr Evaluatict.:                                                                           !
This PC/M is non. nuclear safety related as the security ll(sting system does not per!or"-    :
a safety related !"nction and is powered from non safety sources. Therefore, this PC ''
;     does not inv alve an unreviewed safety question. The security lighting handhole to se         l modified by this PC/M is located so that it cannot affect any salety related equipmen..
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CPWO PLANT CHANGE /MODIFIC ATION Skl81                PC/M CLAS5IFICATION:              NNS UNIT:        4 IMPLEMENTEO:         03 27 3h TURNEO OVER DATE:          05 25 34
                                                       $UMM ARY D ATE:        04.04.44 REVISION:         0 NORMAL AC AIN 5IDE SEAL QB, MOTOR REPLACEMENT Summary:
Bis modification consisted in replacing the existing normal AC air side seal'oll motor with one with higher RPM rating and flow rate. This will increase the efficiency of the hydrogen seal rings.
Safety Evaluations This modification is non. nuclear safety related. No safety related system, component, or structure will be affected by this change. Therefore, it will not increase the probability of securrence or consequence of accident / malfunction of equipment important to safety previousiv analyzed in the F5AR or reduce the margin of safety as defined in the basis for inv Technical Soecification. Therefore, it does not constitute an unreviewed safety question.
t

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PLANT CHANGE /MODIFICAT10N 8k140                  PC/M CLA551PlcATION:             NN5        ;
UNIT:      3 and 4
                                               .                          IMPl.EMENTED:        03-24-84      ;
TURNED OVER DATE:
05-23 44 SUMM ARY DATE:        03-30-ta REV1510N:           0         :
TUR5tNE DECM IJGHT5                                                                     ,
Summary                                                              .
This CPWO provided for an upgrade of turbine deck !!qhts for Units 3 and 4.
l Safety Evaluatten:         -
i This modification is non-nuclear safety since the turbine deck lights do not affeet any       I safety related system or feature. Furthermore, it does not involve an unreviewed safety       l question as this modification does not affect, create, or increase any accident / malfunction i already addressed in the F5AR.
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9 PLANT CHANGE / MODIFICATION Skl65               PC/M CLASSIFIC ATION:             N5 UNIT:         3 IMPLEMENTED:          05.05 84 TURNED OVER DATE:            05-22 84
                                                                            $UMMARY DATE:           06 04 84 REVISION:          0 UNIT 3 RCP LOWER OIL RESERVOIR COOLING WATER HOSL REPLACEMENT 5 Summary:
Component replacement was essential to improve reliability under excessive radiation exposure. This improvement was due to the absence of teflon Inserted tubing which was found to degrade under high radiation exposure.                                             ,
Spiety Evahastion:
This safety evaluation assures that the replacement of Unit 3 RCP(A. 5, and C) lower oil reservoir cooling water hoses does not pose an unreviewed safety question. This nuclear safety related task provides replacement cooling water hose with materials more quallfled to withstand post accident environments (e.g. radiation) than the original hoses. The replacement equipment installed is similar to that in use in similar aoolications elsewhere in the plant.
w.__._______._-___-__--_

PC/M CLASSIP!2 NON:                   NS PLANT CHANGE / MODIFICATION 83-166
                                                                                                                                  .N!Te     4 IMPLEMENTED:   04.19.34 TURNED OVER DATE:                 05 21 34 SUMM ARY D ATE: 05 22 34 REVISION:     0 UNIT 4 RCP LOWER OIL RUERVOIR COOLING W ATER HOSE REPLACEMENTS Summary                                                        -
Component replacement was essential to improve reflability under excessive radiation exposure. This improvement was due to the absence of teflon inserted tubing whien was found to degrade under high radiation exposure.
     -     Safety Evaluation:
This safety evaluation assures that the replacement of Unit 4 RCP ( A, B, and C) lower si reservoir coolint water hoses does not pose an unreviewed safety question. This nu:!est safety related task provides replacement cooling water hose with materials more -as!:f:e:
to withstand post accident environments (e.g. radiation) than the original 1oses. Be replacement equipment installed ls similar to that in use in similar aoplications elsew9ere in the plant.

PC/M CLASSIFICATION:                        NNS PLANT CHANGE / MODIFICATION S3-186                                                    -
UNIT:             4 IMPLEMENTED:     10-17-83 TURNED OVER DATE:             10-24-83

==SUMMARY==
DATE:            10-25-33 REVISION:             0 RHR PUMP MOTOR MOUNTS Summary:
This CPWO involved the addition of a weep hole 1" diameter at the bottom of the RHR motors 4A and 4B leads connection' boxes. This hole allowed for any water that was accumulated to drain cut.                            -
Safety Evaluation:
This modification does not involve an unreviewed safety question as this item does not affect, create or increase the probability of occurrence of any accident /malf. unction already addressed, or new, in the FSAR.
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PLANT CHANGE / MODIFICATION 83-188            PC/M CLASSIFICATION:            NNS UNIT:            3 IMPLEMENTED:           11-21-83      l TURNED OVER DATE:           12-12-83 SUMM ARY DATE:         12-12-83 REVISION:             0 RHR PUMP MOTOR MOUNTS Summary:
This CPWO involved the addition of a weep hole 1" diameter at the bottom of the RHR motors 3A and 3B leads connection boxes. This hole allowed for any water that was accumulated to drain out.
Safety Evaluation:
Tnis modification does not involve an unreviewed safety question as this item does not affect. create or increase the probability of occurrence of any accident /malfunc-ion already addressed, or new, in the FSAR.
9

erve PC/\1 CLASSIFTCATTON:          NNS PLANT CHANGE / MODIFICATION 83-l'94 UNIT:      3&c IMPLEMENTED:         12-12-33 TURNED OVER DATE:          12-13-33 SU\t\iARY DATE:       12-16-S3 REVISION:         0 PORTABLE DEALKALIZING DEMINERALIZER SYSTEM Summary:
This change consisted of a temporary portable dealkalization (softening) system being added while the coagulator is out of service due to sand blasting and painting taking place in the water treatment plant.
Safety Evaluation:
This change is non-nuclear safety related. Furthermore, this temporary installation and operation of a portable demineralizer system will not increase the probacility of occurrence or the consequences of an accident or malfunctioning of equioment. impor ant to safety, nor does it create the possibility of an accident or malfunction not previously evaluated in the FSAR. Additionally, it does not reduce the margin of safety as defined in the basis for any Technical Specification.
J

PLANT CHANGE / MODIFICATION 83-196               PC/M CLASSIFICATION:             NS UN1T:         3 IMPLEMENTED:        12-18-33 TURNED OVER DATE:           01-09-si

==SUMMARY==
DATE:        01-09-SL REVISION:          1 MSTV CLOSING SOLENOID CHECK VALVE ADDITION Summary:
This modification adds a high capacity check valve downstream of each MSIV 3-way closing solenoid valve. This will prevent backflow of closing air through the vent port of a closing solenoid valve should it fail to open.
Safety Evaluation:
This change is nuclear safety related because it affects the closing ability of the MSIVs which are required to isolate a mainstream break. The change does not involve a-unreviewed safety question because it improves the ability of the MSIVs to close in :ne event of equipment failure.
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  . PLANT. CHANGE / MODIFICATION 183-197 UNIT:         e IMPLEMENTED:        11-25-S3 TURNED OVER DATE:         !!-29-S3

==SUMMARY==
DATE:         12-91-83 REVISION:         0 MSIV CLOSING SOLENOID CHECK VALVE ADDITION _
   . Sammary:
Tnis PC/M consisted in adding a high capacity. check valve down stream of each '.iSIV closing solenoid valve. This check valve prevents reverse flow through to solencid to atmosphere in the event of a failed solenoid, thereby ensuring that the MSIVs close in 5 seconds.
Safety Evaluation:
involve an unre.ie.ved 31fe:y This plant- change is nuclear safety related but does not ques:!cn. Tith respect to the probability of occurrence or -he conseguem es of inv a cident . or - equipment f ailure evaluated in the FSAR, the addi:!cn of :Sese 1:.es hpreves :he operation of the MSIVs in the event of a single c:~.p:nen: f2.. re. 2 5 2. R.
A ::5 respec :o the possibility of an accident of a different type than analyzed :n : .e
:nis PC/M has no effect because it does not change the operation of :5e ''.5!V ::: sing
    - sys:em but only ensures that it will operate in :he required time frame xi:" 15 ; e equipmen: f ailures.

CPWO PLANT CHANGE / MODIFICATION 83-203                PC/M CLASSIFICATION:     NNS OA-OC UNIT:      a IMPLEMENTED:      11-23-S3 TURNED OVER DATE:        !2-07-33

==SUMMARY==
DATE:       12-12-S3 REVISION:      0 ADDITION OF HINGE PIN COVER SPACERS ON MSIV OR MSCV Summary:
This modification consisted in modifying the hinge pin cover on the MSIVs or MSCVs by adding a spacer, thus preventing lateral movement in the rockshaft.
Safety Evaluation:
This modification is non-nuclear safety related with no unreviewed safety que's :on. ine probability of occurrence or consequences of an accident / malfunction of equipment important to safety will not increase as previously analyzed in the FSAR. nor was the possibility for an accident or malfunction increased or created.
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PLANT CHANGE / MODIFICATION 83-205               PC/M CLASSIFICATION:               NNs UNTT:            3 IMPLEMENTED:             11-20-83 TURNED OVER DATE:              03-05-S:.

==SUMMARY==
DATE:             03-0s S:.
REVISION:             0 FUEL TRANSFER SYSTEM - GEAR LIMIT Summary:
Modifications consiste'd of adding a gear limit contact as a back-up to existing proximitv switches to stop frame up drive action. Tnus, preventing motor from overstressing cable and frame up mechanism.
Safety Evaluation:
This modification does not involve an unreviewed safety question or affect nuclear safety as it does not affect any safety related system or feature in the piant and does not affect, create or increase any accident / malfunction already addressed, or new, in the FSAR.
%_    T12:5     ^

                                      ~
PLANT CHANGE / MODIFICATION 83-2 5               PC/M CLASSIFICATION:            NS UNIT:         4 IMPLEMENTED:        12-02-83 TURNED OVER DATE:         01-03-84  j

==SUMMARY==
DATE:        05 24-84 REVISION:          0 BLOWDOWN FCV ACTUATOR MODIFICATION Summary:
his CPWO corrected a design deficiency in the blowdown flow control valve actuator.
De deficiency resulted in a stop in the valve action and, therefore, inaccurate flow control.
Safety Evaluation:
This CPWO does not have a detrimental effect on any plant system or component important to safety and, therefore, does not involve an unreviewed safety question.
T12:5

CPWO PLANT CHANGE / MODIFICATION 83-210             PC/M CLASSIFICATION:            NS UNIT:       3 IMPLEMENTED:       12'-20-83 TURNED OVER DATE:         03-13-84

==SUMMARY==
DATE:        03-16-84 REVISION: -     0 CABLE REPLACEMENT FOR VALVES CV3-522A AND CV-3-389 Summary:
The modification involved the replacement of the cables for control vavles CV-3-522A and CV-3-389 and re-routing of conduit to avoid the high temperature in the area of the existing conduit.
Safety Evaluation:
This modification is safety related but does not involve an unreviewed safety question.
The consequences of an accident previously evaluated is not increased because the replacement cable equals or exceeds the quality of the existing cable. The existing conduit is being re-routed away from harsh environmental conditions, therefore, the probability of malfunction of equipment important to safety is decreased.
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PLANT CHANGE / MODIFICATION 83-215_              PC/M CLASSIFICATION:            NS UNIT:         3 IMPLEMENTED:       12-12-83 TURNED OVER DATE:          12-15-83

==SUMMARY==
DATE:         12-16-83 REVISION:         O SOLENOID MOUNTING BRACKET REPLACEMENT FOR PURGE SUPPLY VALVE #2601 Summary:
This modification consisted of fabricating and installing a misplaced mounting bracket for solenoid purge supply valve #2601.
Safety Evaluation:
This modifiction is nuclear safety'related with no safety related system, component or structure adversely affected and no increase in the probability of occurrence or consequences of an accident / malfunction of equipment important to safety previously analyzed in the FSAR.

PLANT CHANGE / MODIFICATION 83-211                PC/M CLASSIFICATION:          NNS UNIT:       3 IMPLEMENTED:     01-10-84 TURNED OVER DATE:       01-16-84

==SUMMARY==
DATE:       01-27-84 REVISION:       0 INSTALLATION OF TEMPORARY EX-VESSEL DOSIMETRY Summary:
This PC/M governed the installation of foil dosimetry devices in the annulus between the reactor vessel and the primary biological shield. These devices are atte.ched to wires suspended from the seal ring area to the vessel sump. Information from this. dosimetry will be utilized to resolve the pressurized thermal shock issue.
Safety Evaluation:
This PC/M has no detrimental effect on any piant system or component important to safety and does not involve an unreviewed safety question.

O PLANT CHANGE / MODIFICATION          84-06        PC/M CLASSIFICATION:        NNS UNIT:       4 IMPLEMENTED:      04 02 34 TURNED OVER DATE:     05-18-84

==SUMMARY==
D ATE:     05-30-84 REVISION:       0 FUEL TRANSFER SYSTEM GEARED LIMIT SWITCH Summary:
This PC/M added a geared limit switch to the upender wench circ' ult. This switch is a backup to the installed proximity switch and will stop the wench motor when the upender
-frame is up.
Safety Evaluation:
This change is non-nuclear safety related and does not involve an unreviewed safety question. This is because the fuel handling system controls are not required to mitigate any accident described in the FSAR. The addition of the redundant geared limit switch provides additional assurance that the upender wench operates correctly.
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PLANT CHANGE / MODIFICATION E                  PC/M CLASSIFICATION:           NNS UNIT:         3 IMPLEMENTED:        01-26 84 TURNED OVER DATE:         03-07-84

==SUMMARY==
DATE:         05-24-84 REVISION:         0 TELEMETERING CONDUIT FOR "C" BUS Summary:
This PC/M modified the "3C" bus megawatt transducer circuit to provide proper input to data acquisition package for net generation signal by providing two resistors for each c'ircuit mounted on existing terminal blocks.
Safety Evaluation:
This modification is non-nuclear safety related as it does not affect any safety related systems or features in the plant. Furthermore, it does not involve an unreviewed safety question as this modification does not affect, create, or increase any accident /
malfunction already addressed or new in the FSAR.
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PLANT CHANGE / MODIFICATION         84 28       PC/M CLASSIFICATION:                NS UNIT:           4 IMPLEMENTED:            04-27.84 TURNED OVER DATE:             05-18.84 SUMM ARY DATE:            05-31.84 REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (I.C.) PER 79-14, PROBLEM CVCS-25C Summary:
This PC/M consisted in modifying the pipe supports on the chemical and volume control system inside containment to comply with NRC !.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question. The modification and analysis has ensured that the design criteria of the original pising system design documents have been met and no accident or malfunction probability increased.

PLANT CHANGE / MODIFICATION         1W-29       PC T T_ ASSIFICATION:               NS UNIT:           4 IM PLEM ENTED:          04-27.8h TURNED OVER DATE:              05-!S-84 SUMM ARY D ATE:            05-31-30 REVISION:            0 MODIFICATION TO CHEMICAL AND VOLUME CONTROL SYSTEM (l.C.) PER 79-14, PROBLEM CVCS-24 Summary:
This PC/M consisted in modifying the pipe supports on the chemical and volume control system inside containment to comply with NRC !.E. Bulletin 79-14 Safety Evaluation:
This modification is nuclear safety related with no unreviewed safety question.           The modification and analysis has ensured that the design criteria of the original piping system design documents have been met and no accident or malfunction probability increased.
9

PLANT CHANGE / MODIFICATION        84-33       PC/M CLASSIFICATION:               NS UNIT:          4 IMPLEMENTED:            05-14-34 TURNEO OVER DATE:              06-05-34

==SUMMARY==
DATE:             06-25-34 REVISION:            0 MODIPICATION TO INTAKE AND CHLORINATION SYSTEM (O.C.) PER I.E. BULLETIN 79-14, PROBLEM 039 Summary:
This PC/M consisted in modifying the pipe supoorts for the intake and Chlorination System outside containment to comply with NRC 1.E. Bulletin 79-14 Safety Evaluation:
This modification is nuclear safety related with no unreviewed safetv question.          The modification and analysis has ensured that the design criteria of the original cicing s ste-design documents have been met and no accident or malfunction probability increased.
4
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PLANT CHANGE /MODIPlcATION 84-36                PC/M CLASSIFICATION              NNS
                                                                 . UNIT:          3 IMPLEMENTED:        02-23-84 TURNED OVER DATE:           03-05-84

==SUMMARY==
DATE:           03-08-84 REVISION:          0 v
RELOCATES OVER CURRENT TRIP RELAYS ON 3AC01,3AC03, AND 3AC16 Summary:
This change removes the over current relays from the breaker doors on the "C" 4160 volt buses and relocates them to the meter and relay compartment where they are less susceptible to mechanical actuation.
Safety Evaluation:
This change is non-nuclear safety related and does not involve an unreviewed safety question because the "C" bus is not required to mitigate any accident in the FSAR and this change makes no functional change in the circuit.
9 9

PLANT CHANGE / MODIFICATION 84 37               PC/M CLASSIFICATIONI              NNS UNIT:          4 IMPLEMENTED:         02-22-84 TURNED OVER DATE:           03-05-84

==SUMMARY==
DATE:           03-08-84 REVISION:           0 RELOCATES OVER CURRENT TRIP RELAYS ON 4 AC01. 4 ACO3, AND 4 AC16 Summary:
J This change removes the over current relays from the breaker doors on the "C" 4160 volt buses and relocates them to the meter and relay compartment where they are less susceptible to mechanical actuation.
Safety Evaluation:
This change is non-nuclear safety related and does not involve an unreviewed safety question because the "C" bus is not required to mitigate any accident in the FSAR and this change makes no functional change in the circuit.                                ,,

PLANT CHANGE / MODIFICATION         84-40      PC/M CLASSIFICATION:               NS UNIT:          4 IMPLEMENTED: _,')6- 12-8 4 TURNED OVER DATE: _ 05-19-3h

==SUMMARY==
DATE: _ 06-25-80 REVISION:           0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (I.C.) PER 79-14, PROBLEM CCW-43 Summary:                                                                .
This PC/M consisted in modifying the pioe suooorts for the Comoonent Cooling T2:=-
System inside containment to comply with NRC 1.E. Bulletin 79-14 Safety Evaluation:
This modification is nuclear safety related with no unreviewed safe:. : .:e < - .        -
modification and analysis has ensured that the design criteria of the aric,2: a:o:n: s. c '
design documents have been met and no accident or malfunction probacill:v :,:.easa:.
9
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PLANT CHANGE / MODIFICATION          84-41      PC/M CLASSIFICATION:                NS UNIT:           4 IMPLEMENTED:            06-12-84 TURNED OVER OATE:              05-19-84 06-25-84     I SUMM ARY DATE:
REVISION:             0 MODIFICATION TO COMPONENT COOLING WATER SYSTEM (I.C.) PER 79-14, PROBLEM CCW-44 Summary:
This PC/M consisted in modifying the ploe supports for the Component Cooling Water System inside containment to comply with NRC I.E. Bulletin 79-14.
Safety Evaluation:
This modification is nuclear safety related with no unreviewed safetv question. The modification and analysis has ensured that the aesign criteria of the original cicing system design documents have been met and no accident or malfunction probability increased.
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i CPWO                                                    I PLANT CHANGE / MODIFICATION           84-44      PC/M CLASSIFICATION:             NS UNIT:         4 IMPLEMEN"ED:        03-01-84 TURNED OVER DATE:          03-07-84 SUMM ARY D ATE:       05-24-84 REVISION:          0          I TEMPORARY SUBSTITUTION OF STUD AND BOLT MATERIAL ON VALVE FC-850D     __
Summary:
This change consisted of temporarily substituting the material for studs and bolts on valve FC-850D with one of similar specifications. The stud and bolts will be changed to its original material on the next available outage.
Safety Evaluation:
This modification is nuclear safety related with on unreviewed safety questions because there is no reduction in the margin of safety as defined in the Technica! Soe:!!: a:ie,s. na increase in the probability of an accident or increase in the probabilly of safety rela:ed equipment malfunction.

CPWO PLANT CHANGE / MODIFICATION           84-%
PC/M CLASSIFICATION: _         NNS UNIT:         4 IMPLEMENTED:      04-12 34 TURNED OVER DATE:      05-22-84

==SUMMARY==
DATE:       06-21-84 REVISION:         0 BLOWDOWN PLOW CONTROL VALVE ACTUATOR Summary:
s This CPWO modified the blowdown flow. control valves by securing the bearing succort plate more firmly to the valve body. This will alleviate the stop exoerienced in the valve actuation and ensure more accurate blowdown flow control.
Safety Evaluation:
This CPWO does not have a detrimental effect on any clant syste n or co~.co,e--
important to safety and, therefore, does not involve any unreviewed safety question.
I 6

PLANT CHANGE / MODIFICATION           84 62      PC/M CLASSIFICATION:           NS UNIT:       4 IMPLEMENTED:       03-21-84
    ^
TURNED OVER DATE:        05-17-84

==SUMMARY==
DATE:        06-04-84 REVISION:        O SPENT FUEL PIT BRIDGE CRANE HATCHWAY LIMIT SWITCH BRACKET Summary:
This modification provided a bracket for the spent fuel pit bridge crane hatchway limit switch ensuring that a mount aligns the hatchway limit switch with the trip bar. The original bracket was lost and a new one was fabricated and installed.
Safety Evaluation:
his modification is nuclear safety related with no unreviewed safety questions since the consecuen:e or probability of accident / malfunction was not increased nor the margin of safety changed as defined in the basis for any Technical Specifications.
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PLANT CHANGE / MODIFICATION           84J2         PC/M CLASSIFIC ATION7 _NNS O A-OC UNITg                               4 IMPLEMENTED:                                                              04-09 34 TURNED OVER DATE:                                                               05-03-84 4                                                          SUMM ARY D ATE:                                                              05-29.84 REVISION:                                                      0 UPENDER PROXIMITY SWITCH SENSING BAR BR ACKETS Summary:                                    '
The purpose of this change was to modify the upender proximity switch sensing bar brackets to prevent damage to the proximity switch if the upender lift frame bottoms out on the kick spring rod assembly. This was done by redesigning the brackets so sensing bars were outside the proximity switches instead of between the switches.
Safety Evaluation:
This change does not involve an unreviewed safety question because it does not affect or increase the probability nor the consequences of any accident or equipment malfunction previously evaluated in the FSAR and, it does not create the possibility of malfunction of equipment not considered in Chapter 14 of the FSAR. Also, this change does not decrease any margin of safety discussed in the Technical Specification basis.
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CPWO PLANT CHANGE / MODIFICATION          84 76      PC/M CLASSIFICATIONa              NS UNIT:            4 IMPLEMENTED:           04-19 84 TURNED OVER DATE:            05-14.84 SUMM ARY DATE:           05-30.84
   ,                                                               REVISION:            O COMPONENT COOI.!NG WATER PUMP CASING STUD AND NUTS REPLACEMENT Summary:
This modification provided for a compatible substitute for existing component cooling water pump casing studs and nuts with ones of greater ultimate strength, existing studs and nuts talled.
j Se ety Evaluation:
his change is nuclear safety related with no increase in the probability of occurrence o-consequences of an accident / malfunction of equipment important to safety previo.n!.
evaNated in the FSAR. No reduction of margin of safety as defined in the Basis for an, Technical Specification. Derefore, this change does not constitute an unreviewed safen concern.
                                                                                               ._~

CPWO PLANT CHANGE / MODIFICATION                                                         84-82                                                                           PC/M CLA551FICATION:                                   NNS UNIT:                3 and 4 IMPLEMENTED:                                03-23-84 TURNEO OVER DATE:                                   05-18-84 SUMM ARY DATE:                               06-04-84 REVISION:                         0 INTAKE LIGHTS UPGRADE TO HIGH PRESSURE SODIUM VAPOR Summary:                                                                                                                                                                                            -
This modification consisted of upgrading the intake lights on Units 3 and 4 to lights of high pressure sodium vapor.
Safety Evaluation:
1he intake lights do not perform any nuclear safety function, and power will come from existing light circuits. Furthermore,it does not involve any unreviewed safety question as this modification does not affect, create, or increase any accident / malfunction already addressed or new in the FSAR.
e h _ . _ _ . _ . _ _ . _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . . _ _ _ _ _ _ _ _ . _    . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _                                    . _ _ _ _ _ _ _        __ _ _ ____ ____

m PLANT CHANGE /MObiFICATION            84 71    PC/M CLASSIFIC ATION2          NS UNITv        4 IMPLEMENTED:        05-25.84 TURNED OVER DATE:        05-26-84

==SUMMARY==
DATE:        06.04-34 REVISION:         0 CCW AND TPCW HEAT EXCHANGER CATHODIC PROTECTION Summary:
This PC/M added reference electrodes to CCW and TPCW heat exchanger, also reolaced the TPCW heat exchanger button anodes with probe anodes.
Safety Evaluation:
1his PC/M is safety related; the Cathodic Protection System misuse or failure w! : not hinder the functional ability of the heat exchanger to mitigate the consequen:es of 2-accident or to maintain safe shutdown conditions.
l
. T19.4

(11) PROCEDURE CHANGES The following procedures were changed, reviewed, approved and reissued during the reporting period. The procedure changes are as described below and only those procedure changes constituting changes in the procedures as described in the Final Safety Analysis Report (FSAR) are reported. Minor or routine procedure changes not affecting procedures as described in the FSAR are not reported.
: 1. In order to incorporate the requirements of Technical Specification Amendment 93 (Facility Operating License DPR-31 for Unit 3) and Amendment 92 (Facility Operating License DPR-41 for Unit 4) which allowed a longer roi drop time, the following procedure was changed:
Operating Procedure 1604.8: CRDM/RP! Stepping and Drop Time Test Date of Change: 12/17/33
: 7. In order to incorporate the requirements of Technical Specification Amendment 95 (Facility Operating License DPR-31 for Unit 3) and Amendment 89 (Facility Operating License DPR-41 for Unit 4) which allowed incorporation of the Standard Technical Specification methods of determining the acceptable level of radiciodine in the reactor coolant system, changes to the Nuclear Chemistry Procedures !!sted below were made a)    NC-2: Schedule for Periodic Tests Date of Change: 11/09/33 b)    NC-52: Sampling and Analysis, Preparation, and documentation of Gas Decay Tank Releases Date of Change: 11/09/33 c)    NC-60: Reactor Coolant System isotopic Identification Date of Change: 10/31/33 di    NC-44: Determination of E (The Average Beta and Gamma Energy per Disintegration for a Mixture of Radlonuc!! des in the Reactor Coolant)
Date of Change: 11/09/33 e)    NC-65: Determination of Radioactive Dose Equivalent 1-131 in the Reactor Coolant System Date of Change: 11/09/33 f)    NC-66: Determination of Gross Beta-Gamma or Gross Alpha Activity Date of Change: 10/31/33 g)    NC-94: Determination of Percent Gas Concentrations (Chromatography)
Date of Change 11/09/33 h)    NC-95: Determination of Dissolved Hydrogen Date of Change 11/09/33 T20:2

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1 I
(ii) Procedure Changes Page 2                                                                 ,
: 3. In ' order to incorporate the requirements of Technical Specification Amendment 90 (Facility Operating License DPR-31 for Unit 3) and Amendment 34 (Facility Operating License DPR-41 for Unit 4) which modified the required flow rate of the auxiliary feedwater system from 600 gpm to 373 gpm for the new model 44f steam generators, the procedures listed below were changed:
a)   Operating Procedure 1008.7: Reactor Coolant System Natural Circulation Date of Change: 07/21/33 b)    Emergency Operating Procedure 20000 (E-0): Immediate Actions and Diagnostics Date of Change: 07/21/83 c)   Em'ergency Operating Procedure 20001 (E-1): Loss of Reactor Coolant Date of Change: 07/21/33
: 4. Due to revision by Westinghouse of the Reactor Vessel Head Stud Revised Tensioning /Detensioning Procedures, the following procedure was changed:
Maintenance Procedure 1407.12: Reactor Vessel Guide Stud Removal, Closure Stud / Nut Installation and Stud Tensioner Operation Safety Evaluation Summary: The proposed procedural change will not increase the probsbility or consequences of an accident inalyzed in the FSAR nor, will it impact the functioning of any safety related equioment important to safety. No new accident or malfunction of a different type will be created and no margin of safety as defined in the basis for any Technical Specification is decreased.
Date of Change: 05/09/34
: 5. Due to the replacement of a process radiation monitor with a SPING 4 type monitor, the following procedure was changed:
Operating Procedure 11100: Process Radiation              Monitoring   System    Operating Instructions Safety Evaluation Summary: R-13 provided no safety functions. No increase in the probability or consequences of an accident or malfunction previously analyzed in the FSAR is created by this change. The margin of safety as defined in the basis for any Technical Specification is not decreased by this change.
Date of Change: 08/25/33 6,    Instrument air bleed valves frmn containment are left open to relieve containment pressure and are automatically closed if high airborne activity is detected. Due to a discrepancy between actual valve position and the valve positions described in the FSAR, the following procedure was changed:
Operating Procedure 10100: Containment Ventilation and Containinent Purge T20:2

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(ii) Procedure Changes
    ' Page 3 Safety Evaluation Summary: This change affects FSAR Table 6.6-1, item 63. This change does not increase the consequences or probability of an accident or equipment malfunction already analyzed in the FSAR. Furthermore, no unreviewed safety question is posed nor, is any margin of safety decreased by this change.
Date of Change: 03/25/33
: 7. Implementation of Plant Change Modification 53-23 provided a constant nitrogen supply to the Flux Mapper System. Two valves, mentioned in Table 6.6-1 of the FSAR as normally closed, were changed to normally open. The following procedure was changed:
Operating Procedure 4103.1:          High Head Safety Injection and Containment Spray Line-up for Automatic Operation Safety Evaluation Summary: Installation of the new Flux Mapper Purge System on the nitrogen line, necessitates that valves S55 and 846 be kept at normally open position. This change is non-nuclear safety related; operating valve 355 at open position does not involve an unreviewed safety question.
Date of Change: I1/16/S3
: 3. Wide range and narrow range containment pressure indicators were modified to include a strip-chart recorder and relocated in the control room.                  The daily comparison between wide and narrow range pressure indication was deleted from the following procedure:
Operating Procedure 0204.2:          Schedule of Periodic Tests, Checks, Calibrations, and Operating Evolutions Safety Evaluation Summary: The need for comparing these pressure indicators per OP 0204.2 was alleviated by the performed modifications.               -\ discrepancy between wide and narrow range containment pressure indicators is now immediately able to be determined by the operator's visual inspection. The deleting of this procedural comparison does not increase the probability or consequences of an accident or, equipment malfunction, previously evaluated in the FSAR. No unreviewed safety question is posed nor, is any margin of safety as defined in the basis for any Technical Specification decreased Date of Change: Il-10-33 i
  , .T20:2

T (iii) TESTS AND EXPERIMENTS This section contains the results and conclusions for special tests that were completed during the reporting period. Special tests still in progress at the end of the reporting period are also described. .
SPECIAL TEST NUMBER                                      TITLE                           UNIT (S) 33-02               Functional Test of Steam Dump to Condenser                 4 33-03              Auxiliary Building Ventilation Test                    Common 83-04               MSR Tubes Purge Test                                       3 33-05              Sand Filter Backwash with Raw Water Booster Pump        Common 83-06              Undervoltage Modifications                            .
3 33-07              Monitoring of Undervoltage                                  3
;           S4-01              SJAE Condensate Removal for SPING 4                         3 34-02              Voltage Regulators - PSS Test                            3 and 4 34-03              4C Bus Lockout and 3C Transformer Lockout                3 and 4 34-04              Functional Test of Auxiliary Power Breaker Interlocks   3 and 4 34-05              Moisture Separator Performance. Evaluation Test         3 and 4 34-06              480 Load Center Undervoltage Monitoring                     4 34-07              Improvement of Lighting Heater 7 rain Pump Area             3 84-03             Improvement of Lighting Heater Drain Pump Area               4 T20:2

SPECIAL TEST 83-02 Unit 4 Cycle VHI FUNCTIONAL TEST OF STEAM DUMP TO CONDENSER VALVES Background Information:
This soecial test was conducted to determine the operability of the Unit 4 Steam Dump to Condenser Valves in order to determine the need for overhaul and adjustment.
Test Results:
On the initial test, valves 2827, 2828 and 2829 were found to be inoperable under conditions of full inlet steam pressure.       Valves 2827 and 2828 were subsequently overhauled and pilot oressure adjustments were made to 2829. On the retest during unit stsetup, valves 1827,1828 and 2829 operated properly. The fourth valve 2830 initially ooerated correctly but would not operate during retest.
Safety Evaluation:
This test was non-nuclear safety related and did not involve an unreviewed safety question because the steam dump to condenser valves do not perform any safety function as analyzed in the FSAR. Decay heat removal and steam generator overpressure protection is provided for by use of the steam generator code safety valves.
e P2:1

7 SPECIAL TEST 83-03 AUXILIARY BUILDING VENTILATION TEST Background Information:
This test provided data to determine if all rooms and ooen areas of the Auxiliary Building were experiencing a minimum of five air turnovers per hour as stated in Section 9 of the FSAR. Air flow was measured at the exhaust registers throughout the building and the volume.of air moved was calculated in cubic feet per minute.
Test Results:
All rooms and ooen areas were determined to have adequate or better ventilation as based on the FSAR criteria.
Safety Evaluation:
This test is designed to determine the overall performance of the Auxiliary Building Ventilation System. The air flow from each room will be measured and recorded during normal operation of the Auxiliary Building Ventilation System. The device used for the measurements willbe a portable, hand held, battery operated air flow meter.
The HVAC System in the Auxiliary Building is non-safety related; therefore, this soecial test is not nuclear safety related as it does not affect any safety related system or feature in the plant.       Furthermore, it does not affect, create, or increase any accident / malfunction already addressed, or ne'v, in the FS AR.
P2:1

SPECIAL TEST 83-04 MSR TUBES PURGE TEST                                         ,
Baelarround Information:
The moisture separator reheaters utilize steam extracted from the main steam, upstream of the high pressure turbine, to reheat steam from the high pressure turbine to power the two low pressure turbines. Lower than expected temperatures of the reheated steam, lead to the theory that the much of the high energy steam flowing through the reheat tubes was condensing in the tubes and, therefore, not reheating the steam from the MSRs to the low pressure turbines adequately. The steam in the reheat tubes heats the steam from the high pressure turbine as it passes over the reheat tube. This test was to note a significant increase in reheated steam temperature by increasing the flow of steam through the reheat tubes.
Test Results:
The reheated steam temperature was not measured to significantly increase as theorized.
Safety Evaluation:
This test is designed to record the effect on temperature of the steam reheated by the moisture separator reheaters 3A and 3B by increasing the flow of main steam through the MSRs. This will be done by manually allowing the fluid in the A reheater drain tank to drain completely from the tank into 6A feedwater heater or, if needed, directly to the condenser.
The equioment and components subject to this test are not safety related and serve no ourtioses that are important to safety. This test affects only equipment downstream of the main steam isolation valves. This test, therefore, does not affect, create, or increase any accident or malfunction previously evaluated in the FS AR.
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SPECIAL TEST 83-05 Units 3 and 4 SAND FILTER BACKWASH WITH RAW WATER BOOSTER PUMP Background Information:
This special test is designed to determine if the raw water booster cump could suoply enough flow and pressure to backwash the sand filters in the water treatment plant.
Test Results:
The raw water booster pump did not supply sufficient pressure and flow to backwash the sand filters. Therefore, it cannot be used for that purpsoe on a routine basis.
Safety Evaluation:
This special test _does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety, it does not create the possibility of an accident or malfunction not previously evaluated, and the margin for safety as defined in the basis for Technical Specifications is not reduced.
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i I
SPECIAL TEST 83-06 Unit 3 UNDERVOLTAGE MODIFICATIONS Beekground Information:
This special test ensures that the new undervoltage logic and sequence action are operable and functions are designed on PC/M 79-16.
Test Results:
The test was successfully completed.
Safety Evaluation:
The probability of occurrence of an accident or malfunction of equipment important to safety is not increased by testing the undervoltage modifications since the unit is at cold shutdown condition.
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SPECIAL TEST 83-07 Unit 3 MONITORING OF UNDERVOLTAGE Background Information:
This special test monitors the sequence of operation of the undervoltage relays in the case that such an event occurs. It also monitors bus voltage to evaluate whether or not normal load / voltage oscillators bring the 480V level down to the undervoltage relay setpoints.
Test Results:
Test engoing.
Safety Evaluation:
The probability of occurrence of an accident or malfunction of equipment imoortant to safety is not increa >ed by monitoring the operation of the undervoltage auxiliary relays (using their spare dry contacts) or variations of bus voltages.
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SPECIAL TEST 84-01 Unit 3 SJAE CONDENSATE REMOVAL FOR SPING 4 "Arvand Information:
This special test was conducted to provide soevidic data for the development of a permanent system to remove moisture from the exhaust of the SJAE to make the SJAE SPING-4 functional.
Test Results:
Due to equioment failure, the special test was performed for two days instead of six weeks as stated in the special test package. The data obtained during the two days is available through the Technical Deparment.
~ Safety Evaluation:
This special test does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety, it does not create the possibility of an accident or malfunction not previously evaluated, and the margin for safety as defined in the basis for Technical Soecifications is not reduced.
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s SPECIAL TEST 84-02 Units 3 and 4 VOLTAGE REGULATORS - PSS TEST Background Information:
This special test is being performed to properly align and verify proper operation of Units 3 and 4 Power System Stabilizer (PSS) function of the voltage regulators.        ,
Test Results:
This special test is on-going.
Safety Evaluation:
This test is non-safety related as it does not affect any safety related system or feature in the plant. Furthermore, it does not involve an unreviewed safety question as it does not affect, create, or increase the probability of any accident / malfunction already addressed, or ne'v, in the FSAR.
P2:1

SPECIAL TEST 84-03 Units 3 and 4 4C BUS LOCKOUT AND 3C TRANSFORMER LOCKOUT Background Information:
This soecial test is to determine the cause of the nearly simultaneous 4C bus lockout and 3C transformer lockout which occurred n February 16, 1984. The test will remove 3C transformer from service and then check inputs from the Unit 4C bus protective relays which could cause a 3C transformer lockout. The test also checks for proper interlock operation on breakers 4 AC16 and 4AC01.
Test Results:
: 1) The 4C bus lockout was caused by mechanical actuation of the 4C bus overcurrent relay 174/TDDO in breaker 4AC01. These relays in breakers AC01, AC03, and AC16 have been relocated to an adjacent compartment.
: 2) The 3C bus transformer lockout was caused by mechanical actuation of the CHC relay in the 4C bus back-up protection scheme.
: 3) The 4C syne check relay was found to be defective. The relay has been reolaced.
Safety Evaluation:
This test is not nuclear safety related and does not involve an unreviewed safety question for the following reasons:
: 1) The test only involves power distribution systems provided by the C bus auxiliary power. This bus only suoplies non class IE equipment.
: 2) The test will not affect any Class IE safety related power systems.
: 3) The units will be at hot shutdown for the test.
O The oroblem which caused the dual unit trip on February 16, 1994 originated in the C bus auxiliary power and did not have any adverse affect on any safety related equioment. This test is to determine the cause of the non-safety related failure.
For t.he above reasons, this test has no affect on the probability' of occurrence or consequences of any accident or equipment malfunction analyzed in the FSAR. No probability for new accidents is created and the Basis for the Technical Specifications is not changed.
P1:1

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SPECIAL TEST 84-04 Units 3 and 4 FUNCTIONAL TEST GF AUX 11JARY POWER BREAKER INTERLOCKS Beektround Information:
This special test will check for. proper functioning of the breaker interlocks on breakers 3 AC01, 3 AC16, 3 AC03, 3 AC13, 4 AC01, 4 AC16, 4 AC03, and 4 AC13. See detailed test procedure (Enclosure 4). It will also check the breaker Interlocks associated with auxiliary power upgrade C bus breakers. This will provide additional assurance that the interlocks function correctly.
Test Results:
The subject soecial test was performed on February 22 and 23,1984, on both Units 3 and
: 4. During the initial attempt to synchronize and close 3 AC01 in step 2.4, breaker 3 AC16 failed to trip ooen automatically. The failure was later discovered to be the result of misalignment in the breaker trip mechanism. The test was continued on Unit 4 on February 22,1984, and comoleted with satisfactory results. All interlocks functioned as designed. Breaker 3AC16 was removed and replaced with breaker 4AC16. An insocction of other breakers on the 3C bus was conducted and no other oroblems were identified.
The testing was performed again on the Unit 3 3C bus on February 23, 1984, with all interlocks performing as expected. The testing is now completed.
Safety Evaluation:
This test is non-nuclear safety related and does not involve an unreviewed safety question for the following reasons:
This test checks interlocks between the 3C and 4C bus feeder breakers, those breakers and busses do not power any safety related equipment.
The test does not de-energize equioment and all conditions are checked prior to attempting to test interlocks to ensure no on/off phase paralleling can occur.
For these reasons, the probability of occurrence or consequences of any accident or equipment malfunction described in the FSAR is not affected. No ootential for new accidents exists and the basis for the Technical Specifications is unchanged.
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SPECIAL TEST 84-05
                                                                                                                                ~
Units 3 and 4 MOISTURE SEPARATOR PERFORM ANCE EVALUATION TEST Baektround Information:
The intent of this test is to support JPE in conducting parametric studies on critical \1SR performance parameter (i.e., terminal Delta-T, shell side Deita-P, and \1SR removal effectiveness).
Test Results:
Test ongoing.
Safety Evaluation:
The test will determine the molsture removal effectiveness of the \1SR by both direct measurement (calorimeter techniques and by calculational methods utilizing heat transfer correlations). This is done on a none nuclear safety related system and does not affect the safety of any safety related equipment. Therefore, conducting this test does not involve an unreviewed safety question.
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r                                                                                                a SPECIAL TEST 84-06 Unit 4 480 LC UNDERVOLTAGE MONITORING
    ": f _m n o information:
This special test is being performed to monitor the undervoltage logic and 480 volt system status to enable promot and accurate evaluation /cause identification of any undervoltage event.
Test Results:
This special test is on-going.
Safety Evaluation:
This test does not involve an unreviewed safety question as it DOES NOT:
: 1)    increase the orobability of occurrence of an accident or the malfunction of equipment imoortant to safety,
: 2)    create the possibility of an accident or malfunction different than those n!rcady analyzed in the FS AR, or
: 1)    decrease the margin of safety as defined in the Basis for any Technical Specification.
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SPECIAL TEST 84-07 Unit 3 IMPROVEMENT OF LIGHTING HEATER DRAIN PUMP AREA Beehrround information:
This soecial test is to provide better lighting for plant operation on a temporary basis until a final lighting uograde plan is developed and implemented. This temporary installation will also serve as a test to evaluate any additionallighting needs in this area.
Test Results:
Test is to be performed in July 1984.
Safety Evaluation:
This special test involves the upgrade of light fixtures in the heater drain pump area Unit
: 1. The fixtures that are presently installed are not safety related and do not perform any nuclear safety function. The power for these fixture replacements will come from the same circuit that is in service now. the new fixtures are energy efficient and draw less current oer watt than existing fixtures.
Therefore, this soecial test is not nuclear safety related as it does not affect any safety related system or features in the plant. Furthermore, it does not involve an unroviewed safety question as this modification does not affect, create, or increase any accident /
malfunction already addressed or new in the FS AR.
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                                        ~      -                              --
l SPECIAL TEST 84-08 Unit 4 1MPROVEMENT OF UGHTING HEATER DRAIN PUMP AREA
    "+/ n _M information:
This soecial test is to provide better lighting for plant operation on a temoorary basis untti a final lighting upgrade olan is developed and implemented. 'this temporary installation will also serve as a test to evaluate any additional 11ghting needs in this area.
Test Results:
Test is to be performed in July 1984.
Safety Evaluation
.9 This special test involves the upgrade of light fixtures in the heater drain pump area Unit
: 4. The fixtures that are presently installed are not safety related and do not perform any nuclear safety fu.7ction. The power for these fixture replacements will come from the same circuit that is in service now. the new fixtures are energy efficient and draw less current per watt than existing fixtures.
Therefore, this special test is not nuclear safety related as it does not affect any safety related system or features in the plant. Furthermore, it does not involve an unreviewed Safety question as this modification does not affect, create, or increase any accident /
malfunction already addressed or new in the FS AR.                                                 .
                                                                                                            ,1 o
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                                                                       "'"lt 29,1984 L-84-224 Mr. James P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission Sulte 2900 101 Marietta Street, NW At1anta, GA 30323 W       

==Dear Mr. O'Reilly:==

Re: Turkey Point Units 3 andAA Docket Nos. 50-250 ang'60-2 10 CFR 50.59 Report ( _.
Florida Power & Light's Report on " Changes, Tests, and Experiments Made Without Prior Commission Approval" for the period July 1,1983 through June 30, 1984 is attached.
very truly yours, f, ,
yc .
doch s, Jr.
              .WilJ Group V(t President Nuclear Energy JWW/PLP/js Att achment    ,
cc: Director, Of fice of Inspection and Enforcenent Harold F. Reis Esquire PNS-L1-84-297
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