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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1911999-09-20020 September 1999
SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2
ML20211G5261999-08-24024 August 1999
SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1
ML20209E4361999-07-0909 July 1999
SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K6631999-07-0707 July 1999
Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers
ML20206N3511999-05-11011 May 1999
Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs
ML20206A6561999-04-21021 April 1999
Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code
ML20202H9851999-01-29029 January 1999
Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1
ML20198S1781998-12-31031 December 1998
SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2
ML20198A4481998-12-11011 December 1998
Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted
ML20249B6281998-06-12012 June 1998
Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower
ML20248B0441998-05-27027 May 1998
Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety
ML20217H7181998-04-0101 April 1998
Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl
ML20217B8831998-03-24024 March 1998
SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan
ML20197A6551998-03-0202 March 1998
Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet
ML20203H9551998-02-23023 February 1998
SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2
ML20203B1071998-02-0404 February 1998
Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5)
ML20199F3361998-01-28028 January 1998
Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2
ML20203C2811997-12-0909 December 1997
Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program
ML20198T3621997-10-24024 October 1997
Safety Evaluation Authorizing Supporting Second 10-year Interval ISI Program Requests for Relief RR-17 & RR-25 as Submitted by Southern Nuclear Operating Co on 970529
ML20198J7651997-10-15015 October 1997
Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units
ML20211E6871997-09-22022 September 1997
SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20210R2071997-08-27027 August 1997
Safety Evaluation Accepting Relief Requests for Pump & Valve Inservice Testing Program
ML20148S2231997-07-0202 July 1997
Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2
ML20148H2501997-06-0505 June 1997
Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp
ML20134P2421997-02-20020 February 1997
Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications
ML20134G5551996-11-0707 November 1996
Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel
ML20058A3041993-11-19019 November 1993
Safety Evaluation Re Accumulator Pressure & Vol Instrumentation of Reg Guide 1.97 Environ Qualification Requirements,Per Generic Ltr 82-33.Category 3 Qualification of Instrumentation Acceptable
ML20062J8641993-11-10010 November 1993
Safety Evaluation Denying Licensee 920617 Request for Amends to License Changing TS 3/4.6.1.7 & 4.6.1.2f for Plant
ML20059J0061993-11-0303 November 1993
Safety Evaluation Supporting Rev 15 to Emergency Plan for Plant
ML20059G8601993-10-29029 October 1993
SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval
ML20057F8291993-10-12012 October 1993
Safety Evaluation Accepting Util Submittals of Rev 7 to IST Program for Unit 1 & Rev 4 to IST Program for Unit 2
ML20057F4121993-10-12012 October 1993
Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i)
ML20057E3021993-10-0404 October 1993
Safety Evaluation Accepting Proposed Changes to EAL in Rev 15 of Plant Emergency Plan
ML20056H6441993-08-26026 August 1993
Safety Evaluation Denying TS Change for Surveillance of Emergency Core Cooling Sys
ML20057A0361993-08-26026 August 1993
Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively
ML20056H3191993-08-24024 August 1993
SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations
ML20127B7051993-01-0606 January 1993
Safety Evaluation Supporting Rev 4 to First 10-yr Interval Inservice Insp Program for Facility
ML20127B6901993-01-0606 January 1993
Safety Evaluation Supporting Rev 5 to First 10-yr Interval Inservice Insp Program for Facility
ML20126H3171992-12-28028 December 1992
Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage
ML20126F3331992-12-23023 December 1992
Safety Evaluation Accepting Licensee Schedule for Completing MOV Testing Program in Response to GL 89-10
ML20059E9171990-08-31031 August 1990
SER Supporting Util 890928 Request for Exemption from 10CFR20,App a & Authorizing Use of Radioiodine Protection Factor for Sorbent Canisters
ML20058N7961990-08-0909 August 1990
Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys
ML20247K2531989-09-11011 September 1989
Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E3761989-09-0707 September 1989
Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20248C0731989-08-0303 August 1989
Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20247H7611989-07-18018 July 1989
Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively
ML20246C4621989-06-29029 June 1989
Safety Evaluation Granting Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code
ML20246L2571989-06-26026 June 1989
Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20247C0171989-05-18018 May 1989
Safety Evaluation Supporting Util Actions to Recover from 890307-08 Unit 1 Steam Generator Tube Rupture Event
ML20245J0751989-04-25025 April 1989
Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
1999-09-20
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2
ML20217K8041999-09-30030 September 1999
Rev 1 to Vegp,Unit 2 Cycle 7 Colr
ML20217K7741999-09-30030 September 1999
Rev 1 to Vegp,Unit 1 Cycle 9 Colr
ML20217K4591999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With
ML20217F3661999-09-22022 September 1999
Rev 18 to McGuire Unit 1 Cycle 14 Colr
ML20212D1911999-09-20020 September 1999
SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
ML20216E8851999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2
ML20217G8101999-08-31031 August 1999
Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2
ML20216E5061999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with
ML20211G5261999-08-24024 August 1999
SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20210S2371999-07-31031 July 1999
Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2
ML20216E8951999-07-31031 July 1999
Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2
ML20210P9841999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With
ML20209E4361999-07-0909 July 1999
SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K6631999-07-0707 July 1999
Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers
ML20209H1631999-06-30030 June 1999
Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2
ML20210S2491999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209H1211999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With
ML20209H1731999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20195K3691999-05-31031 May 1999
Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20196F9711999-05-31031 May 1999
Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage
ML20196L1881999-05-31031 May 1999
Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology
ML20195G1731999-05-31031 May 1999
Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with
ML20206N3511999-05-11011 May 1999
Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs
ML20206N2141999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With
ML20195K3761999-04-30030 April 1999
Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206R0891999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206A6561999-04-21021 April 1999
Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML20205L2341999-04-0505 April 1999
SFP Criticality Analysis
ML20206R0931999-03-31031 March 1999
Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205A9581999-03-31031 March 1999
Rev 0 to VEGP Unit 1 Cycle 9 Colr
ML20205Q8081999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with
ML20206C2291999-03-31031 March 1999
Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2
ML20205P8991999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205C4171999-03-25025 March 1999
Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed
ML20207K2051999-03-0505 March 1999
Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed
ML20204C8911999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2
ML20207K6051999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With
ML20205P9021999-02-28028 February 1999
Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209H4091999-02-15015 February 1999
Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2
ML20209H3951999-02-15015 February 1999
Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2
ML20204C8961999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2
ML20202H9851999-01-29029 January 1999
Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1
ML20199F8041999-01-13013 January 1999
Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage
ML20216F9931998-12-31031 December 1998
Piedmont Municipal Power Agency 1998 Annual Rept
ML20199E0301998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2
1999-09-30
[Table view] |
Text
, . .
4 SAFETY EVALUATION REPORT i
TECHNICAL SPECIFICATION CHANGE (MPA B-90)
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 INTRODUCTION By letter dated December 7, 1985, Duke' Power Company proposed changes to the McGuire Technical Specifications pertaining to Reaqtor Trip System Instrumentation and Surveillance in response to Generic Letter 85-09 (MPA B-90). Generic Letter 85-09 concluded that Technical Specification changes should be proposed by licensees to explicitly require independent testing of the undervoltage and shunt trip attachments of the reactor trip breakers during power operation, testing of bypass breakers prior to use, and independent testing of the control room manual switch contacts and wiring during each refueling outage.
EVALUATION Duke Power Company's proposed Technical Specification changes are consistent with those specified in Generic Letter 85-09, except as indicated below by items 1 and 2.
- 1. No provision is included for testing of the Reactor Trip Bypass Breaker prior to each time it is put into service.
~
, 2. No provision is ' included for verifying the operability of the Bypass Breaker trip circuits each refueling outage.
The licensee has declined to provide Technical Specifications for the above items on the basis that there is no significant benefit to be expected from inclusion of Bypass Trip Breaker testing in the Technical Specifications.
This is not acceptable to the NRC staff. When a reactor trip breaker is tested, the reactor trip bypass breaker is put into service as a backup. The Generic Letter 85-09 Technical Specifications specify a manual test of the B612110461 861205 PDR A ADOCK 05000424 PDR
-= . .-.
-2 bypass breaker prior to putting it into service. This testing is a simple procedure and it is prudent to do this, test before relying on this breaker as a backup to the remaining reactor trip' breaker. Although the licensee states that probabilistic risk analyses (PRAs) show that testing of the breaker has an insignificant affect on the overall reliability, no claim is made that the reliability is decreased or that the bypass breaker is not safety related.
Therefore, we believe that these tests should be made as specified in Generic Letter 85-09.
We find the remaining Techncial Specification changes proposed by Duke Power Company to be consistent with Generic Letter 85-09 and therefore acceptable.
CONCLUSION We find the Technical Specification changes propnsed by Duke Power Company for the McGuire Nuclear Station, Units 1 and 2 to be acceptable except that the licensee has declined to provide proposed Technical Specifications to provide for testing of the Reactor Trip Bypass Breakers and associated circuitry. The licensee should submit for staff review proposed Technical Specifications for this purpose as indicated in Generic Letter 85-09.
l l
)
' ' ENCLUbUNt i
ICSB SALP IllPUT , ,
PLANT: McGuire, Units 1 and 2 Technical Specification Change, MPA B-90 i
SUBJECT:
DASIS PERFORitANCE i EVALUATION
' CATEGORY CRITERIA .
N/A No basis for assessment.
) Management l , involvement . . .
Licensee takes issue with some items of G.L. 85-09. Provides basis
. Approach to 2 for doing so. .
Resolution of -
Technical Issues _
2 Response was adequate for issues accepted.
i
... Responsiveness s
1 N/A No basis for assessment. ,
- 1. Enforcement .
illstory
. ~
N/A No basis for assessment.
i j 5. Reportable Events No basis for assessment. ,
- 6. StaffinD N/A N/A No basis for assessment. .
- 7. Train.ing