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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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t g ENCLOSURE SAFETY EVALUATION RELATED TO GENERIC LETTER 83-28, ITEMS 3.1.1, 3.1.2, 3.2.1, 3.2.2, and 4.5.1 GEORGIA POWER COMPANY V0GTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 and 50-425 INTRODUCTION Generic Letter (GL) 83-28 was issued by the staff on July 8,1983. It described intermediate-term actions to be taken by the licensees and applicants to address the generic issues raised by the two anticipated transients without scram (ATWS) events that occurred at Unit 1 of Salem Nuclear Power Plant. These actions were developed by the staff based on information contained in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." Actions to be performed included development programs to provide for post-trip review, classification of equipment, vendor interface, postmaintenance testing, and reactor trip system reliability improvements. The GL s tated that for Items 3.1.1, 3.1.2, 3.2.1, 3.2.2, and 4.5.1 NRC Regional Offices would perfom a post-implementation review and issue safety evaluations. This report is the Regional safety evaluation of Georgia Power Company responses to the above items.
EVALUATION By letters dated November 8, 1983, and August 26, 1986, the licensee provided information regarding compliance with items 3.1.1, 3.1.2, 3.2.1, 3.2.2, and 4.5.1 of GL 33-28. The staff evaluated the licensee's responses aaainst the NRC positions described in the GL for completeness and adequacy. The staff found the licensee's responses to be incomplete, thus requiring additional information to determine acceptability. These deficiencies were transmitted to the licensee by letter dated December 31, 1986 and in SSER 5.
i The licensee's supplemental responses to Items 3.1.1, 3.1.2, 3.2.1, 3.2.2, and !
4.5.1 submitted by letters dated January 15 and June 9,1987 were reviewed ana !
found acceptable.
Delineated below are the results of the staff's evaluations and a brief summary of the licensee's supplemental responses: ,
l l Generic Letter 83-28, Item 3.1.1 l Item 3.1.1 requires licensees and applicants to submit the results of their l review of test procedures, maintenance procedures, and Technical i Specifications to ensure that postmaintenance operability testing of safety-related components in the reactor trip system is required to be conducted and that the testing demonstrates that the equipment is capable of performing its safety functions before being returned to service.
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The licensee stated in its final response dated January 15, 1987, that l procedures had been established which require postmaintenance testing of the ;
reactor trip switchgear. The response also stated that test procedures had been developed to utilize the solid state protection system panel or the main control board trip handswitch to demonstrate operability of the reactor trip switchgear. During its review, the staff did not interpret the licensee's trip switchgear statement to encompass all safety-related components in the reactor trip system. The licensee's use of " reactor trip switchgear" instead of reactor trip system components was discussed during a telecon between the licensee and NRC on June 1, 1987. The licensee's representative stated that the statement " reactor trip switchgear" meant all safety-related components in the reactor trip system. This was confirmed by letter dated June 9,1987.
Based on the above, the licensee's response is acceptable.
Generic Letter 83-28, Item 3.1.2 Item 3.1.2 requires licensees and applicants to submit the results of their i check of vendor and engineering recommendations to ensure that any appropriate I test guidance is included in the test and maintenance procedures or the Technical Specifications, where required.
The licensee's supplemental response dated January 15, 1987, to Item 3.1.2 stated that procedures are written referencing vendor manuals, if applicable, and when procedures are reviewed, the review criteria requires that the procedure be reviewed against applicable vendor manuals. The licensee also indicated that engineering and vendor recommendations were checked to ensure that appropriate test guidance has been included in the test and maintenance procedures or the Technical Specifications. The licensee's response to Item 3.1.2 is acceptable.
Generic Letter 83-28, Item 3.2.1 Item 3.2.1 requires licensees and applicants to submit a report documenting the extending of test and maintenance procedures and Technical Specifications review to ensure that postmaintenance operability testing of all safety-related equipment is required to be conducted and that the testing demonstrates that the equipment is capable of perfonning its safety functions before being returned to service.
The licensee's supplemental response dated January 15, 1987, to Item 3.2.1 stated that maintenance of safety-related systems / components is controlled and processed via Maintenance Work Order (MW0) procedures. These procedures provide controls which require postmaintenance testing of safety-related systems / components to prove their operability. The licensee also stated that it has completed a review of test and maintenance procedures and appropriate Technical Specifications to ensure that the testing demonstrates that the equipment is capable of performing its safety function. The licensee's response to Item 3.2.1 is acceptable.
g l Generic Letter 83-28, Item 3.2.2 Item 3.2.2 requires licensees and applicants to submit the results of their check of vendor and engineering recommendations to ensure that any appropriate test guidance is included in the test and maintenance procedures or the Technical Specifications, where required.
The licensee's response to Item 3.2.2 states that procedures are written referencing vendor manuals and when procedures are reviewed they are checked against the applicable manual. The licensee indicated that vendor manuals are :
controlled by Administrative Procedure 00108-C and that vendor and engineering I recommendations are reviewed and are included in the test and maintenance i procedures or the Technical Specifications. The licensee's response to Item l 3.2.2 is acceptable.
I Generic Letter 83-28. Item 4.5.1 1 Item 4.5.1 requires that online functional testing of the reactor trip system including independe~nt testing of the diverse trip features be performed. The breaker undervoltage and shunt trip features in Westinghouse plants should be included.
The licensee's supplemental response dated January 15, 1087, stated that a surveillance procedure has been developed which verifies the capability of the undervoltage and shunt trip features to independently trip the reactor trip
< breakers. The surveillance test is performed each month, and each train is tested at least once every 62 days on a staggered test basis. The response stated that a Westinghouse automatic shunt trip panel had been added to the reactor trip switchgear cabinets and provides the capability to independently test the undervoltage and shunt trip devices. The licensee's response to Item 4.5.1 is acceptable.
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CONCLUSION l Based on the above statements, the staff finds the licensee's responses to Items 3.1.1, 3.1.2, 3.2.1, 3.2.2, and 4.5.1 acceptable, thereby meeting the intent of GL 83-28. The licensee has procedures to ensure that vendor and engineering recommendations are included in test and maintenance procedures. ;
The licensee also confirmed that it had reviewed test and maintenance procedures and Technical Specifications and that postmaintenance testing is required on the reactor trip system components and all other safety-related components.
The licensee stated that it has installed equipment to independently verify the capability of the undervoltage and shunt trip devices to trip the reactor trip breakers.
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