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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20216H5141999-09-24024 September 1999 Safety Evaluation Supporting Amend 209 to License DPR-16 ML20195C8141999-06-0202 June 1999 Safety Evaluation Supporting Amend 208 to License DPR-16 ML20206U9511999-05-18018 May 1999 Safety Evaluation Supporting Amend 207 to License DPR-16 ML20206P0241999-05-13013 May 1999 Safety Evaluation Supporting Amend 206 to License DPR-16 ML20206P0881999-05-12012 May 1999 Safety Evaluation Supporting Amend 205 to License DPR-16 ML20205A7451999-03-17017 March 1999 Safety Evaluation Supporting Amend 204 to License DPR-16 ML20196E2741998-11-30030 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-16 ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155G9311998-11-0404 November 1998 Safety Evaluation Supporting Amend 201 to License DPR-16 ML20154M6311998-10-15015 October 1998 Safety Evaluation Supporting Amend 200 to License DPR-16 ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20237B7331998-08-13013 August 1998 Safety Evaluation Supporting Amend 196 to License DPR-16 ML20248L1611998-06-0404 June 1998 Safety Evaluation Supporting Amend 195 to License DPR-16 ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20197B4971998-02-11011 February 1998 Corrected Safety Evaluation for Amend 194 to License DPR-16.Page 2 of SE Was Incorrectly Numbered as Page 3 ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20217Q6581997-08-26026 August 1997 Safety Evaluation Supporting Amend 192 to License DPR-16 ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20140H7761997-05-0808 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-16 ML20137X1071997-04-14014 April 1997 Safety Evaluation Supporting Amend 190 to License DPR-16 ML20137D6111997-03-24024 March 1997 Safety Evaluation Supporting Amend 189 to License DPR-16 ML20136D6001997-03-0606 March 1997 Safety Evaluation Supporting Amend 188 to License DPR-16 ML20133E1681997-01-0707 January 1997 Safety Evaluation Re Third 10-yr Interval ISI Plan,Rev 1 to Relief Request R11 for Plant.Proposed Alternative to ASME Requirements Authorized ML20134G2061996-11-0707 November 1996 Safety Evaluation Supporting Amend 187 to License DPR-16 ML20128L1601996-10-0303 October 1996 Safety Evaluation Accepting Third 10-yr Interval Inservice Insp Plan Request for Relief R15 ML20128F4791996-10-0101 October 1996 Safety Evaluation Accepting Rev to Inservice Testing Program Re Leakage Testing of Containment Isolation Valves ML20115F4151996-07-15015 July 1996 Safety Evaluation Supporting Amend 185 to License DPR-16 ML20117K5371996-06-0404 June 1996 Safety Evaluation Supporting Amend 184 to License DPR-16 ML20100Q4231996-03-0404 March 1996 Safety Evaluation Supporting Amend 183 to License DPR-16 ML20092A3011995-09-0606 September 1995 Safety Evaluation Supporting Amend 182 to License DPR-16 ML20087D0531995-08-0707 August 1995 Safety Evaluation Supporting Amend 181 to License DPR-16 ML20087J2831995-05-0101 May 1995 Safety Evaluation Supporting Amend 180 to License DPR-16 ML20081G9711995-03-21021 March 1995 Safety Evaluation Supporting Amend 178 to License DPR-16 ML20080D9851994-12-29029 December 1994 Safety Evaluation Accepting Licensee Requesting to Change TS to Establish Addl Requirements for Availability of LPRM Associated W/Aprm Sys ML20080D9501994-12-29029 December 1994 Safety Evaluation Supporting Amend 176 to License DPR-16 ML20077E7441994-12-0707 December 1994 Revised Page 18 of SE in Accordance W/Actions Described in Section 8.1.3 of OCNGS IPE Submittal Rept ML20077F7081994-11-30030 November 1994 Safety Evaluation Supporting Amend 174 to License DPR-16 ML20076H7361994-10-19019 October 1994 Safety Evaluation Supporting Amend 172 to License DPR-16 ML20076G4911994-10-11011 October 1994 Safety Evaluation Supporting Amend 171 to License DPR-16 ML20071M8121994-07-29029 July 1994 Safety Evaluation Supporting Amend 169 to License DPR-16 ML20029E6021994-05-11011 May 1994 SER Recommends That Licensee Monitor Conditions of Dsw & Bsw at Periodic Intervals to Ensure Continued Functions ML20063M2281994-03-0707 March 1994 Safety Evaluation Supporting Amend 168 to License DPR-16 ML20198Q4311994-01-14014 January 1994 Safety Evaluation Supporting Amend 194 to License DPR-16 ML20062M2811993-12-21021 December 1993 Safety Evaluation Supporting Amend 167 to License DPR-16 ML20057A9221993-09-13013 September 1993 Safety Evaluation Supporting Amend 165 to License DPR-16 ML20056H2651993-08-24024 August 1993 SE Re Inservice Testing Program Requests for Relief ML20056E0911993-08-0404 August 1993 SE Re Util 930614 Response to Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs. Util Justification for Not Implementing Addl Short Term Actions Acceptable ML20046B2301993-07-13013 July 1993 SER Concluding That Licensee pipe-support Anchorages Are in Conformance W/Requirements of NRC Bulletin 79-02 ML20045A4381993-06-0707 June 1993 Safety Evaluation Supporting Amend 164 to License DPR-16 ML20035E4171993-04-0707 April 1993 Safety Evaluation Re Reg Guide 1.97 Involving post-accident Neutron Flux Monitoring Instrumentation for BWRs 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-011, :on 980914,three Small Bore Pipe Lines Did Not Meet Design Bases for Seismic & Thermal Allowables.Caused by Inadequate Structural Piping Analysis.Two 1/2 Sdcs Lines Were Modified During 17R RFO & 3rd Was Modified During 19991999-09-30030 September 1999
- on 980914,three Small Bore Pipe Lines Did Not Meet Design Bases for Seismic & Thermal Allowables.Caused by Inadequate Structural Piping Analysis.Two 1/2 Sdcs Lines Were Modified During 17R RFO & 3rd Was Modified During 1999
ML20216H5141999-09-24024 September 1999 Safety Evaluation Supporting Amend 209 to License DPR-16 ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With 05000219/LER-1999-001, :on 990208,prolonged Operation of TB with Condenser & Heater Bay Pressure Less than Design Was Noted. Caused by Lack of Clearly Documented Design Description. Placed Alternate Exhaust Fan in Service.With1999-07-29029 July 1999
- on 990208,prolonged Operation of TB with Condenser & Heater Bay Pressure Less than Design Was Noted. Caused by Lack of Clearly Documented Design Description. Placed Alternate Exhaust Fan in Service.With
ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1999-004, :on 990510,determined That Configurations of Two Pipe Supports in Spent Fuel Pool Cooling Sys Do Not Meet Design Requirements for Deadweight Loads.Caused by Inadequate Analysis.Pipes Upgraded.With1999-06-22022 June 1999
- on 990510,determined That Configurations of Two Pipe Supports in Spent Fuel Pool Cooling Sys Do Not Meet Design Requirements for Deadweight Loads.Caused by Inadequate Analysis.Pipes Upgraded.With
ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195C8141999-06-0202 June 1999 Safety Evaluation Supporting Amend 208 to License DPR-16 ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206U9511999-05-18018 May 1999 Safety Evaluation Supporting Amend 207 to License DPR-16 ML20206P0241999-05-13013 May 1999 Safety Evaluation Supporting Amend 206 to License DPR-16 ML20206P0881999-05-12012 May 1999 Safety Evaluation Supporting Amend 205 to License DPR-16 ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1999-003, :on 990402,cable Trays Did Not Meet Separation Criteria.Caused by Inadequate Engineering Review.Fire Watch Was Stationed Immediately Upon Discovery.With1999-04-30030 April 1999
- on 990402,cable Trays Did Not Meet Separation Criteria.Caused by Inadequate Engineering Review.Fire Watch Was Stationed Immediately Upon Discovery.With
05000219/LER-1999-002-01, :on 990330,fire Protection Deluge Sys Isolation Valve Was Found Out of Position.No Root Cause Determined. Technical Assessment Was Performed.With1999-04-29029 April 1999
- on 990330,fire Protection Deluge Sys Isolation Valve Was Found Out of Position.No Root Cause Determined. Technical Assessment Was Performed.With
ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20205A7451999-03-17017 March 1999 Safety Evaluation Supporting Amend 204 to License DPR-16 05000219/LER-1999-001-02, :on 990208,noted Prolonged Operation of TB with Condenser & Heater Bay Pressure.Caused by Loss of Integrity of Ventilation Envelope (Physical Boundaries).Alternate Exhaust Fan Was Placed in Service.With1999-03-0808 March 1999
- on 990208,noted Prolonged Operation of TB with Condenser & Heater Bay Pressure.Caused by Loss of Integrity of Ventilation Envelope (Physical Boundaries).Alternate Exhaust Fan Was Placed in Service.With
ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-016, :on 981028,single DG Start,Occurred.Caused by Loss of One Source of Offsite Power.Generator Relay Surveillance Revised to Eliminate Possibility of Inadvertent Procedural Breaker Trips.With1999-01-0505 January 1999
- on 981028,single DG Start,Occurred.Caused by Loss of One Source of Offsite Power.Generator Relay Surveillance Revised to Eliminate Possibility of Inadvertent Procedural Breaker Trips.With
ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-019, :on 981118,missed TS Required Surveillance Test.Caused by Inadequate Administrative Controls.Revised Related Surveillance Task Descriptions to Provide Improved Ref.With1998-12-18018 December 1998
- on 981118,missed TS Required Surveillance Test.Caused by Inadequate Administrative Controls.Revised Related Surveillance Task Descriptions to Provide Improved Ref.With
ML20196E2741998-11-30030 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-16 ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-017, :on 981027,discovered That Station Battery Racks Did Not Comply with Seismic Design Basis.Caused by Inadequate Engineering Review.Restored Battery Rack Retainer Plates to Appropriate Configuration.With1998-11-25025 November 1998
- on 981027,discovered That Station Battery Racks Did Not Comply with Seismic Design Basis.Caused by Inadequate Engineering Review.Restored Battery Rack Retainer Plates to Appropriate Configuration.With
05000219/LER-1998-018, :on 981023,DG 2 Failed to Start from App R Local Shutdown Panel During Functional Test.Caused by Incorrectly Designed Wiring.Incorrect Wiring Was Modified & Demonstrated by Testing to Be Correct.With1998-11-23023 November 1998
- on 981023,DG 2 Failed to Start from App R Local Shutdown Panel During Functional Test.Caused by Incorrectly Designed Wiring.Incorrect Wiring Was Modified & Demonstrated by Testing to Be Correct.With
ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155G9311998-11-0404 November 1998 Safety Evaluation Supporting Amend 201 to License DPR-16 ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-014, :on 980928,noted Failure of Isolation Condenser Tube Bundles.Caused by Thermal Stresses/Tgscc Due to Leaky Valve.Replaced Failed Tubes Bundles & Repaired Condensate Return Valve.With1998-10-29029 October 1998
- on 980928,noted Failure of Isolation Condenser Tube Bundles.Caused by Thermal Stresses/Tgscc Due to Leaky Valve.Replaced Failed Tubes Bundles & Repaired Condensate Return Valve.With
05000219/LER-1998-015, :on 980929,SDC Isolation Occurred Due to Equipment Failure.Caused by Damaged Conduit That Appeared to Have Been Damaged by Personnel Error.Instrument Was Repaired & Bypass Was Removed.With1998-10-28028 October 1998
- on 980929,SDC Isolation Occurred Due to Equipment Failure.Caused by Damaged Conduit That Appeared to Have Been Damaged by Personnel Error.Instrument Was Repaired & Bypass Was Removed.With
05000219/LER-1998-013-01, :on 980926,LLRT Results Indicated That MSIV NS03B Exceeded TS Leak Rate Limit.Caused by Component Wear. Maint Was Performed on Subject Valve to Restore Seat Integrity & as-left LLRT Was Acceptable.With1998-10-26026 October 1998
- on 980926,LLRT Results Indicated That MSIV NS03B Exceeded TS Leak Rate Limit.Caused by Component Wear. Maint Was Performed on Subject Valve to Restore Seat Integrity & as-left LLRT Was Acceptable.With
ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R 05000219/LER-1998-012-01, :on 980916,unplanned Actuation of Esfs Occurred.Caused by Written Communication.Procedure Revised to Include Signature Verifications to Install & Subsequently Remove Ohmmeter1998-10-16016 October 1998
- on 980916,unplanned Actuation of Esfs Occurred.Caused by Written Communication.Procedure Revised to Include Signature Verifications to Install & Subsequently Remove Ohmmeter
ML20154M6311998-10-15015 October 1998 Safety Evaluation Supporting Amend 200 to License DPR-16 05000219/LER-1998-011-01, :on 980914,discovered That Three Small Bore Piping Lines Did Not Meet Design Basis Seismic &/Or Thermal Allowables.Caused by Design Deficiency.Subject Lines Will Be Modified During Present Refueling Outage.With1998-10-15015 October 1998
- on 980914,discovered That Three Small Bore Piping Lines Did Not Meet Design Basis Seismic &/Or Thermal Allowables.Caused by Design Deficiency.Subject Lines Will Be Modified During Present Refueling Outage.With
ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification 05000219/LER-1998-010, :on 980724,DG Switchgear Was Found Beyond Design Bases.Caused by Inadequate Installation During Original Construction.Evaluated Temporary Mod to Determine If It Should Be Reclassified as Permanent Mod1998-08-24024 August 1998
- on 980724,DG Switchgear Was Found Beyond Design Bases.Caused by Inadequate Installation During Original Construction.Evaluated Temporary Mod to Determine If It Should Be Reclassified as Permanent Mod
ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B7331998-08-13013 August 1998 Safety Evaluation Supporting Amend 196 to License DPR-16 ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station 05000219/LER-1997-013, Has Been Canceled1998-06-30030 June 1998 Has Been Canceled 1999-09-30
[Table view] |
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UNITED STATES j
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20565
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1 SAFETY LVALUATION BY THE OFFICE OF NUCLEAR, REACTOR REGULATION REQUEST FOR EXEMPTION ' ROM-BATTERY POWERED EMERGENCY LIGHTING UNITS IN THE CONTROL ROON GPU NUCLEAR CORPORATION.AND i
JERSEY CENTRAL POWER.& LIGHT COMPANY l
OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 i
1.0 INTRODUCTION
tsy letter dated November 24, 1986, the licensee, GPU Nuclear Corporation (GPUN/ licensee), requested an exemption from the requirement of Section III.J of Appendix R to 10 CFR Part 50 to provide individual battery powered emergency lighting units in the control room.
2.0 EXEMPTION REQUESTED f
The licensee has requested an exemption from the provision of Section III.J of Appendix R to 10 CFR Part 50 to the extent that the batteries which provide power to the emergency lights in the control room can be damaged by fire other than a fire in the control room.
l-3.0 EVALUATION Normal control room lighting is powered from a vital lighting bus. This bus
. receives power from normal offsite source and, by means of automatic transfer switch, to either Emergency Diesel Generator 1 or 2.
l
' Emergency lighting for the control room is provided by a separate 12 volt system powered from 277 volt input,12 volt output battery / charger units.
The battery / charger units are located adjacent to the control room in the office building in fire area.0B-FA-9. These batteries are on constant trickle ch trge, su) ply power only to the control room emergency lights and will last longer t1an 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
These two lighting systems and their power supplies and wiring circuits are physically and electrically independent and separate from each other.
I Although a fire in Fire Area UB-FA-9 could damage the batteries which supply l'
power to the emergency lights, the two lighting systems are so located and l
arranged that a single fire could not threaten both at the same time.
We have reviewed the technical support provided by the licensee in their
~ letter of November 24, 1986, and agree with their presentation and conclusions.
900223o026 900212
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4.0 CONCLUSION
i Based upon the above evaluation. we conclude that the two separate lighting j
systems are adequate to assure continuous lighting in the control room for any fire postulated to occur in the plant. The. technical support for this conclusion is that each lighting system has its own power supply. In addition these'two power. supplies are independent of each other and physically separated so that a single fire will not damage both. Therefore i
'7_
relocation of the existing batteries or battery / charger units or the instal-lation of individual battery powered emergency lighting units in the control room would not significantly enhance safety at Oyster Creek and this requested
. exemption should be granted.
Dated: February 12, 1990 Principal Contributor:
D. Notley e
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