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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20206A6561999-04-21021 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 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 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,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 ML20210R2071997-08-27027 August 1997 Safety Evaluation Accepting Relief Requests for Pump & Valve Inservice Testing Program 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 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 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 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 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 ML20206L6491988-11-22022 November 1988 Supplemental Safety Evaluation Concluding That Commitment & Schedule Re 14 Open Items Concerning SPDS Acceptable. Commitment to Complete 1000 H Availability Test by 881231 Acceptable.Requirements of License Condition 2.C.7(b) Met ML20155C9901988-10-0303 October 1988 Safety Evaluation Concluding That ATWS Design Proposed by Util Meets 10CFR50.62 Requirements,Subj to Successful Completion of Certain Noted Human Factors Engineering Reviews ML20151E0421988-07-18018 July 1988 Sser Supporting Electrical Cable & Raceway Configurations for Plant ML20236S5251987-11-20020 November 1987 Safety Evaluation Supporting Util 870121,0522,0720 & 0929 Submittals Re Seismic Adequacy for Spent Fuel Pool Racks ML20236D2941987-10-28028 October 1987 Safety Evaluation Supporting Fire Suppression Sys Changes for Facility ML20236A8521987-10-15015 October 1987 Safety Evaluation Concluding That Util 870713,0930 & 1015 Submittals in Support of License Condition 2.C(8) Provide Acceptable Justification That Inorganic Zinc Coating on Fuel Oil Storage Tanks Will Not Adversely Affect Generators ML20235S8101987-10-0707 October 1987 Safety Evaluation Supporting Proposed Redesign of Steam Generator Upper Support of Reactor Coolant Loop Sys for Unit 2 & Proposed Revised FSAR ML20235G7371987-09-22022 September 1987 Safety Evaluation Supporting Rev 2 to Inservice Testing Program,Providing Cold Shutdown Valve Testing Justifications & Addl Relief Requests ML20237H3011987-08-19019 August 1987 Safety Evaluation Accepting 870601 Proposed Deletion of Electrical Penetration Filter & Exhaust Sys NUREG-1137, Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification1987-08-14014 August 1987 Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification ML20236H1151987-07-30030 July 1987 Safety Evaluation Supporting Util long-term Proposal for Support of Cable in Vertical Cable Trays Through Use of Stainless Steel Cable Ties ML20236F3591987-07-29029 July 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 2.1 Re Identification of safety-related Reactor Trip Sys Components.Util Response Adequate ML20235J9441987-07-0707 July 1987 Safety Evaluation Supporting Supplemental Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Per NUREG-1000 ML20212F5381987-01-0808 January 1987 Safety Evaluation of Water Hammer Events & Corrective Actions Taken to Ensure Nuclear Svc Water Cooling Water Sys Integrity & long-term Operability.Sys Functional Integrity & long-term Operability Capability Adequate ML20214P3971986-09-15015 September 1986 SER Supporting Environ Qualification of Asco Solenoid Valves ML20205F2731986-08-0808 August 1986 Safety Evaluation Re Operability & Reliability of Tdi Emergency Diesel Generators.Submittal Concludes Technical Resolution of Generic Tdi Generator Issues ML20215A7521986-07-0707 July 1986 SER Supporting Util 860523 Proposed Changes to Tech Specs Re Reactor Trip Sys Instrumentation & Surveillance in Response to Generic Ltr 85-09.SALP Input Also Encl ML20215A9671986-05-22022 May 1986 SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl ML20215A7821986-05-0808 May 1986 Sser Re Util Response to Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip. Licensee Should Submit Proposed Tech Specs Consistent W/Generic Ltr 85-09 Guidance for NRC Review.Salp Input Also Encl ML20215G1131986-04-11011 April 1986 SER Re Util 830414,850315,0620,0906 & 860121 Responses to Reg Guide 1.97.Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 2,w/exception of Containment Sump Water Temp ML20127G7421985-06-13013 June 1985 Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks in Feedwater Sys 1999-04-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With 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 ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With 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 ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant 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 ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With 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 ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236P6991998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20236Q3051998-06-30030 June 1998 Owner'S Rept for ISI for Sixth Maint/Refueling Outage of Vogtle Electric Generating Plant,Unit 2 ML20249A3911998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Vogtle Electric Generating Plant ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20249A3931998-04-30030 April 1998 Revised MOR for Apr 1998 for Vogtle Electric Generating Plant Unit 1 ML20247F3841998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20154Q9721998-04-20020 April 1998 10CFR50.59(B) Rept of Facility Changes,Tests & Experiments for Vogtle Electric Generating Plant,Units 1 & 2 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 ML20216D6141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20217Q1301998-03-31031 March 1998 Rev 0 to Vepc Unit 2 Cycle 7,COLR 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 ML20216E2421998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203E4831998-02-11011 February 1998 Rev 1 to Vogtle Electric Generating Plant,Units 1 & 2 Second Ten-Yr Interval Pump Inservice Test Program ML20198T1211998-01-31031 January 1998 Owners Rept for Inservice Inspection for Seventh Maintenance/Refueling Outage ML20202G5441998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20199E5431998-01-31031 January 1998 Rev 3 to WCAP-14720, Vogtle Units 1 & 2 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20198L6471997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20202B7881997-12-0101 December 1997 Rev 8 to ISI-P-006, ISI Program for Gpc Vogtle Electric Generating Plant Unit 1 ML20203H0601997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Vegp,Units 1 & 2 1999-09-30
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& It UNITED STATES i lN 2 NUCLEAR REGULATORY COMMISSION f WASHINGTON. D.C. 20555-0001
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SAFETY EVALUATION BY THE OFFICE NUCLEAR REACTOR REGULATION CONCERNING A TECHNICAL SPECIFICATION CHANGE FOR THE CONTAINMENT PURGE SUPPLY AND EXHAUST ISOLATION VALVES GEORGIA POWER COMPANY. ET AL. ,
V0GTLE ELECTRIC GENERATING PLANT. UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425
1.0 INTRODUCTION
Ey letter dated November 7, 1991, as supplemented June 17, 1992, Georgia Power Company (GPC) requested to amend the Vogtle Electric Generating Plant (VEGP)
Unit I and Unit 2 Technical Specifications. The proposed amendments would clarify the action statements and surveillance requirements for the containment purge supply and exhaust isolation valves, in light of NRC Information Notice No. 88-73, " Direction-Dependent Leak Characteristics of Containment Purge Valves."
2.0 BACKGROUND
Information Notice No. 88-73 addressed an unexpected direction-dependent leakage characteristic of certain butterfly valves equipped with a tapered seat. Pressure from one direction tended to unseat the resilient seals (gaskets), whereas pressure from the opposite direction tended to seal the gaskets against the tapered valve seats.
Section III.C, " Type C tests," of Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," to 10 CFR Part 50 states that for containment isolation valve local leak rate testing, " pressure shall be applied in the same direction as that when the valve would be required to perform its safety function, unless it can be determined that the results from the tests for a pressure applied in a different direction will provide equivalent or more conservative results." The isolation valves being considered under this request are butterfly valves equipped with a tapered seat. It is the staff's position that testing these kinds of valves in the direction opposite to the one required to perform their safety function is inadequate to meet the requirements for containment isolation valve local leak rate testing.
3.0 EVALUATION The preferred method of performing the quarterly testing at VEGP involves !
pressurizing the space between the inboard and outboard purge supply and exhaust isolation valves (hereafter referred to as a "between valve" test).
This results in the inboard valves being tested in the direction opposite that 9311100061 931110 4 PDR ADDCK 0500
which the valves would experience under accident conditions. As a result of Information Notice No. 88-73, it is uncertain that the preferred method of testing at VEGP can be considered to provide equivalent or more conservative results with respect to the inboard containment purge supply and exhaust isolation valves. Presently, forward direction tests are performed at quarterly intervals as required by existing surveillance requirement 4.6.1.7.2; the necessity of making a containment entry each time the test must be performed represents a hardship on the licensee, especially from the standpoint of maintaining personnel exposure as low as reasonably achievable.
The licensee stated in their request that the purpose of these quarterly surveillance tests is to identify excessive degradation of the resilient seals. The following quarterly test requirement was proposed to provide indication of seal degradation:
, First, the quarterly "between valve" test results will be trended. If the current leakage exceeds the previous leakage by 10 percent of 0.06 La, the "between valve" test frequency will be increased to at least once per month.
Second, if the current "between valve" test results exceed 35 percent of 0.06 La, then a Type C test must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The limit of 35 percent of 0.06 La was chosen by the licensee based on a comparison of historical leak rate test results for these valves.
4.0 CONCLUSION
l The staff disagrees with the licensee's contention that the purpose of the quarterly surveillance tests is to identify excessive degradation of the resilient seals. The staff believes that the purpose of the quarterly surveillance tests is to verify the operability of the valv.e at a frequency that would detect incipient gross failure and allow the licensee to take action to prevent gross failure. The licensee has failed to demonstrate that the proposed testing of the valves in the reverse direction will provide equivalent or more conservative results as required by Section III.C of Appendix J. As identified in Information Notice No. 88-73, the problem of reverse flow testing is that the valve may demonstrate adequate leak tightness in the reverse direction but fail in the direction required to perform its safety function. The licensee's proposal to verify leak tightness in the reverse direction does not adequately address the concerns identified in Information Notice No. 88-73. Therefore, the staff recommends that the licensee remain with its present technical specifications and continue to test the containment purge supply and exhaust isolation valves in the forward direction.
Principal Contributor: M. Snodderly Date: November 10, 1993
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