Letter Sequence Other |
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TAC:52842, (Approved, Closed) TAC:52844, (Approved, Closed) TAC:52845, (Approved, Closed) TAC:52850, (Approved, Closed) TAC:52854, (Open) TAC:57731, (Approved, Closed) |
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MONTHYEARML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants Project stage: Other ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) Project stage: Other ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept Project stage: Other ML20235X5221987-07-20020 July 1987 Forwards SER Accepting Util 831107,840229 & Re Generic Ltr 83-28,Item 2.1 (Part 2) Re Confirmation That Interface Established W/Nsss Supplier or Vendors of Each Reactor Trip Sys component.EGG-NTA-7591 Technical Rept Encl Project stage: Approval ML20154C6771988-05-11011 May 1988 Forwards Request for Addl Info Re Util 850620 Response to Generic Ltr 83-28,Item 2.2 (Part I) Re Equipment Classification & Vendor Interface Programs for All safety- Related Components.Info Requested by 880615 Project stage: RAI ML20248J8921989-04-0505 April 1989 Forwards Safety Evaluation Accepting Util 831104,841119 & 880401 Responses to Generic Ltr 83-28,Position 2.1 Part 2 Re Vendor Interface for Reactor Trip Sys Components Project stage: Approval 1987-07-20
[Table View] |
Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR PlantsML20214G959 |
Person / Time |
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Site: |
Millstone, Hatch, Grand Gulf, LaSalle, 05000000 |
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Issue date: |
03/31/1986 |
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From: |
Haroldsen R EG&G IDAHO, INC. |
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To: |
NRC |
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Shared Package |
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ML20214G961 |
List: |
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References |
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CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7179, GL-83-28, TAC-52842, TAC-52844, TAC-52845, TAC-52850, TAC-52854, TAC-57731, NUDOCS 8605280198 |
Download: ML20214G959 (12) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20211K7681999-07-30030 July 1999 Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20236U7241998-03-31031 March 1998 Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20140E2991997-06-0202 June 1997 Proposed Criteria for ECCS Strainer Design,Technical Evaluation Rept ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 21996-12-31031 December 1996 Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 ML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20086G5161995-06-29029 June 1995 Technical Evaluation Rept on Individual Plant Exam Front End Analysis ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20086G5211994-12-31031 December 1994 Technical Evaluation Rept on Individual Plant Exam Back-End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20086G5281994-11-30030 November 1994 Technical Evaluation Rept on Individual Plant Exam Human Reliability Analysis ML20079S0781994-09-26026 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Hatch-1/-2 ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045A5211993-05-31031 May 1993 High Pressure Coolant Injection System RISK-BASED Inspection Guide for Hatch Nuclear Power Station ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20058H5991990-11-15015 November 1990 Analysis of Ei Hatch Unit 2 Integrated Leakage Rate Testing Data Using Sbir Analysis of State-of-Art Methods of Containment Integrated Leakage Rate Testing 1999-07-30
[Table view] Category:QUICK LOOK
MONTHYEARML20211K7681999-07-30030 July 1999 Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20236U7241998-03-31031 March 1998 Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20140E2991997-06-0202 June 1997 Proposed Criteria for ECCS Strainer Design,Technical Evaluation Rept ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 21996-12-31031 December 1996 Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 ML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20086G5161995-06-29029 June 1995 Technical Evaluation Rept on Individual Plant Exam Front End Analysis ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20086G5211994-12-31031 December 1994 Technical Evaluation Rept on Individual Plant Exam Back-End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20086G5281994-11-30030 November 1994 Technical Evaluation Rept on Individual Plant Exam Human Reliability Analysis ML20079S0781994-09-26026 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Hatch-1/-2 ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045A5211993-05-31031 May 1993 High Pressure Coolant Injection System RISK-BASED Inspection Guide for Hatch Nuclear Power Station ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20058H5991990-11-15015 November 1990 Analysis of Ei Hatch Unit 2 Integrated Leakage Rate Testing Data Using Sbir Analysis of State-of-Art Methods of Containment Integrated Leakage Rate Testing 1999-07-30
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20211K7681999-07-30030 July 1999 Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20236U7241998-03-31031 March 1998 Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20140E2991997-06-0202 June 1997 Proposed Criteria for ECCS Strainer Design,Technical Evaluation Rept ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 21996-12-31031 December 1996 Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 ML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20086G5161995-06-29029 June 1995 Technical Evaluation Rept on Individual Plant Exam Front End Analysis ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20086G5211994-12-31031 December 1994 Technical Evaluation Rept on Individual Plant Exam Back-End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20086G5281994-11-30030 November 1994 Technical Evaluation Rept on Individual Plant Exam Human Reliability Analysis ML20079S0781994-09-26026 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Hatch-1/-2 ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045A5211993-05-31031 May 1993 High Pressure Coolant Injection System RISK-BASED Inspection Guide for Hatch Nuclear Power Station ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20058H5991990-11-15015 November 1990 Analysis of Ei Hatch Unit 2 Integrated Leakage Rate Testing Data Using Sbir Analysis of State-of-Art Methods of Containment Integrated Leakage Rate Testing 1999-07-30
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20211K7681999-07-30030 July 1999 Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20236U7241998-03-31031 March 1998 Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20140E2991997-06-0202 June 1997 Proposed Criteria for ECCS Strainer Design,Technical Evaluation Rept ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 21996-12-31031 December 1996 Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 ML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20086G5161995-06-29029 June 1995 Technical Evaluation Rept on Individual Plant Exam Front End Analysis ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20086G5211994-12-31031 December 1994 Technical Evaluation Rept on Individual Plant Exam Back-End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20086G5281994-11-30030 November 1994 Technical Evaluation Rept on Individual Plant Exam Human Reliability Analysis ML20079S0781994-09-26026 September 1994 Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Hatch-1/-2 ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045A5211993-05-31031 May 1993 High Pressure Coolant Injection System RISK-BASED Inspection Guide for Hatch Nuclear Power Station ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20058H5991990-11-15015 November 1990 Analysis of Ei Hatch Unit 2 Integrated Leakage Rate Testing Data Using Sbir Analysis of State-of-Art Methods of Containment Integrated Leakage Rate Testing 1999-07-30
[Table view] |
Text
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EGG-NTA-7179 CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
SELECTED GENERAL ELECTRIC BOILING WATER REACTOR PLANTS GRAND GULF 1 AND 2
' HATCH 1 AND 2 N LA SALLE 1 AND 2 MILLSTONE 1 R. Haroldsen Published March 1986 EG&G I'daho,'Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract NO. DE-AC07-76ID01570 FIN Nos. 06001 and 06002 f A QGO59.8M m
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ABSTRACT This EG&G Idaho, Inc. report provides a review of the submittals from ,
selected operating and applicant Boiling Water Reactor (BWR) plants for conformance to Generic Letter 83-28, Item 2.1 (Part 1). The,following plants are included in this review.
. Plant Name ., Docket Number Tac Number Grand Gulf 1 50 416 52842 Grand Gulf 2 50 417 --
Hatch 1 50 321 52844 Hatch 2 50 366 52845 LaSalle 1 50 373 52850 LaSalle 2 50 374 57731 Millstone 1 50 245 52854 Y
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1 FORWARD This report is supplied as part of the program for evaluating licensee / applicant conformance to Generic Letter 83-28 " Required Actions .
Based on Generic Implications of Salem ATWS Events." This work is being conducted for the U.S. Nuclear Regulatory Comission, Office, of Nuclear Reactor Regulation, Division of PWR Licensing-A, by EG&G Idaho, Inc.
The U.S. Nuclear Regulatory Comission funded this work under the authorization B&R 10-19-11-3, FIN Nos. D6001 and D6002.
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CONTENTS ABSTRACT .........................................................'...... -
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FOREWARD ......................................................... .... iii
. 1. INTRODUCTION AND
SUMMARY
......................................... 1
- 2. PLANT RESPONSE EVALUATIONS ....................................... 3 2.1 Grand Gulf 1 and 2 ......................................... 3 2.2 Conclusion ................................................. 3 2.3 Hatch 1 and 2 .............................................. 4 2.4 Conclusion ................................................. 4 ,
2.5 La Salle 1 and 2 ........................................... 6 2.6 Conclusion .....................................:........... 6 2.7 Millstone 1 ................................................ 7
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l 2.8 Conclusion .....,........................................... 7
. 3. GENERIC REFERENCES ............................................... 8 1
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. CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
SELECTED GENERAL ELECTRIC BOILING WATER REACTOR PLANTS , ' -
- 1. INTRODUCTION AND
SUMMARY
On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the irsitiation of the automatic trip signal. The failure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior ,
to this incident, on February 22, 1983, an automatic trip signal was generated at Unit 1 of the Salem Nuclear Power Plant based on steam generator low-low level during plant startup. In this case,' the reactor
' was tripped manually by the operator almost coincidentally with the
. automatic trip. ,
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem Unit 1 incidents are reported in NUREG-1000,
" Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28, dated July 8, 1983 ) all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to generic. issues raised by the analyses of these two ATWS events.
This report is an evaluation of the responses submitted from a selected group of Boiling Water Reactors (BWRs) for Item 2.1 (Part 1) of Generic Letter 83-28.
The results of the review of four individual plant responses are combined and reported on in this document to enhance review efficiency.
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The. specific plants reviewed in this report were selected based on the ,
convenience of review. The actual documents which were reviewed for each evaluation are listed at the end of each plant evaluation. The geqeric -
documents referenced in this report are listed at the end of the report.
Part 1 of Item 2.1 of Generic Letter 83-28 requires the licensee or applicant to confirm that all reactor trip system coraponents are identified, classified, and treated as safety-related as indicated in the following statement:
Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and information handling -
systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.
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, . 2. PLANT RESPONSE EVALUATION 2.1 Grand Gulf 1. 50-416. TAC No. 52842. Grand Gulf 2.50-41L (0L)-
The licensee / applicant for Grand Gulf 1 and 2 (Mississippi Power and Light Co.) responded to the requirements of Item 2.1 (Part 1) with
- submittals dated November f.1983 and August 26, 1985. In the first submittal the licensee / applicant stated intentions to review the equipment list to ensure the safety related components in various systems which contribute to reactor trip are properly classified. Also, the procedures controlling safety related activities related to components which
, contribute to the reactor trip function were to be reviewed to verify ,
proper safety-related identification.
The licensee / applicant confirmed in the August 26, 1985' submittal that
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! the component required to function for reactor trip are identified as
. safety-related on documents., procedures and information handling systems i
used in the plant to control safety-related activities, including maintenance, work orders and parts replacement.
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! 2.2 Conclusion i
Based on the review of the licensee's submittals, we find that the i licensee's responses confirm that the components required to trip the reactor have been identified as safety-related and are appropriately i designated on all relevant plant documents. These responses, therefore, meet the requirements of Item 2.1 (Part,1) of Generic Letter 83-28 and are acceptable. -
References ,
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. 1. Letter, J. P. McGaughy, Jr., Mississippi Power and Light Co., to D. G. Eisenhut. NRC, Novemoer 4, 1983.
- 2. Letter, L. F. Dale, Mississippi Power and Light Co., to H. R. Denton, NRC, August 26, 1985.
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i 2.3 Hatch. Units 1 and 2. 50-321/322. TAC Nos. 52844/52845
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l The licensee for Hatch 1 and 2 (Georgia Power Co.) provided re.sponses to Item 2.1 (Part 1) in 3 submittals dated November 7, 1983, February 29, 1984 and June 3, 1985. The first submittal stated that the necessary review of reactor trip system components had not been initiated but that the existing classification of trip system components was expected
- to be found in conformance. A supplemental response was to be submitted
, prior to February 29, 1984.
l The submittal dated February 29, 1984 described some problems
, encountered in completing the review. The Hatch 1 and 2 plants, like most ,
! General Electric BWR plants, does not have a defined reactor trip system.
The licensee stated their intention to respond to Item 2.1 (Part 1) on a system level basis by reviewing all systems that perform the' reactor trip
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- function. The review was scheduled to be completed by January 1, 1986.
The submittal dated Jun) 3,1985 confirmed that the review of the .
- reactor protection system (RPS) and other systems which input signals to the RPS to trip the reactor had been completed. All equipment needed to j trip the reactor with the possible exception of the source range neutron monitors (SRMs) were verified to be properly identified as "Q" on plant documentation. The SRMs were to be given further review regarding safety classification and licensing basis.
l _ The licensee noted that all safety related components are considered
- j. "Q" but the "Q" designation is not restr,1cted to safety related
! components. The "Q" designation is'used on plant documentation for procurement, maintenance, and other plant activities to identify quality requirements. ,
2.4 Conclusion i
i Based on the review of the licensee's submittals, we find that the licensee's responses confirm that the components required to trip the i
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reactor have been designated as safety-related and are designated in all relevant plant documents. These responses, therefore, meet the ,
requirements of Item 2.1 (Part 1) of Generic Letter 83-28 and are .
acceptable.
References
- 1. Letter, L. T. Gucwa, Georgia Power Co., to J. F. Stolz, NRC, November 7, 1983.
- 2. Letter, L. T. Gucwa, Georgia Power Co., to J. F. Stolz, NRC, February 29, 1984. ,
- 3. Letter, L. T. Gucwa, Georgia Power Co., to J. F. Stolz NRC, June 3, 1985.
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2.5 La Salle Units 1 and 2. 50-373/50-374. TAC Nos. 52850/57731 ,
3 ThelicenseeforLaSalleUnits1and2(CommonwealthEdison[Co.-) -
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responded to the requirements of Item 2.1 (Part 1) with submittals' dated November 5, 1983, and June 1, 1984. The licensee emphasized that the components whose functioning is required to trip the reactor do not include all reactor trip components (e.g., some turbine trip components). However.
l the licensee confirmed that those components which must function to trip the reactor, as classified in the licensing-basis documentation, were
- classified as safety-related. The licensee also confirmed that the safety-related components are identified on applicable documents,
, procedures, and information handling systems.
4 2.6 Conclusion
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j Based on the review of the licensee's submittals, we find that the l . licensee's responses state that a system has been implemented to verify i thatthosecomponentsthat5renecessarytoperformreactortripare f t - e ated v nt p1 n do u n n Th e e therefore, meet the requirements of Item 2.1 (Part 1) of Generic i
Letter 83-28, and are acceptable.
l l References
- 1. Letter, P. L. Barnes, Commonwealth Edison Co., to H. R. Denton, NRC, November 5, 1983. ,
- 2. Letter, P. L. Barnes, Commonwealth Edison Co., to H. R. Denton, NRC, June 1, 1984.
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2.7 Millstone Unit 1 50-245. TAC No. 52854 ThelicenseeforM111estoneUnit1(NortheastNuclearEnergygo.') -
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responded to the requirements of Item 2.1 (Part 1) in submittals dated November 8, 1983 and May 9, 1985. The submittals state that all components ,
whose function is required to trip the reactor are identified as Category 1 (safety related) on their Material. Equipment and Parts List (MEPL) and that safety-related activities on these components including maintenance, work orders and parts replacement will be completed using Category 1 controls.
2.8 Conclusion .
Based on the review of the licensee's submittals we find that the '
licensee's responses confirm that the components necessary to perform
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reactor trip are classified safety related and that all activities relating to these components are designated as safety related. These respones, therefore, meet the requirements of Item 2.1 (Part 1) of Generic Letter 83-28, and are acceptable.
References
- 1. Letter, W. G. Counsil, Northeast Nuclear Energy Co., to
- D. G. Eisehnut, NRC, November 8, 1983.
l 2. Letter, J. F. Opeka, Northeast Nuclear Energy Co., to J. A. Zno11nski, NRC, May 9, 1985. ,
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- 3. GENERIC REFERENCES
- 1. Generic Implications of ATWS Events at the Salem Nuclear Powe'r Plarit, NUREG-1000 Volume 1. April 1983; Volume 2. July 1983. *
- 2. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, i " Required Actions 8ased on Generic Implications of Salem ATWS Events (Generic Letter 83-28) " July 8, 1983.
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