Letter Sequence Request |
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MONTHYEARML20207L3521981-01-29029 January 1981 Informs That 810116 Extension for Time to Request Hearing Re 801024 Order for Mod of Lisense Acceptable & Consistent W/ 810108 Request Project stage: Other ML20041D7681982-03-0303 March 1982 Submits Correction to Util 820225 Ltr Re NUREG-0737,Item II.K.2.13, Thermal-Mechanical Rept - Effect of HPI on Vessel Integrity for Small Break LOCA W/No Auxiliary Feedwater. Project stage: Request ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info Project stage: Request ML20071E4691983-03-10010 March 1983 Responds to NRC Re safety-related Electrical Equipment.Justification for Continued Operation Encl Project stage: Other ML20073K9011983-03-25025 March 1983 Public Version of Rev 27 to Emergency Plan Supporting Procedure Administrative Memo 41, Emergency Duty Officer (EDO) & Other Emergency Duties Project stage: Request ML20073R5471983-04-29029 April 1983 Responds to NRC Re safety-related Electrical Equipment.Justification for Continued Operation Exists for All Equipment Which May Not Be Qualified.Response Submitted 830310 Contains No Changes or Proprietary Info Project stage: Other ML20071G8771983-05-20020 May 1983 Forwards Info Re Environ Qualification of Electrical Equipment Important to Safety,Per 10CFR50.49.List of Activities to Resolve Technical Evaluation Rept Open Items Encl.Namco Limit Switches Scheduled for Replacement Listed Project stage: Other ML20085J3351983-10-10010 October 1983 Discusses 831013 Meeting to Resolve Deficiencies Noted in Franklin Research Ctr Technical Evaluation Rept Re Environ Qualification of safety-related Electrical Equipment.Agenda & Supporting Documentation Encl Project stage: Meeting ML20082G3431983-11-23023 November 1983 Forwards Agenda for 831213 Meeting W/Nrc in Bethesda,Md to Discuss & Resolve Outstanding Issues Re Environ Qualification of Electrical Equipment Project stage: Meeting ML20083A2061983-11-29029 November 1983 Forwards Equipment Qualifications Manual,Rev 2 Project stage: Other ML20088A9051984-04-0303 April 1984 Forwards Generic Issues,Resolution of Open Items & Justifications for Continued Operations Per 831213 Meeting Re Environ Qualifications for safety-related Electrical Equipment Deficiencies Project stage: Meeting ML20090A0571984-06-26026 June 1984 Forwards Sys Component Evaluation Worksheets & Justifications for Continued Operation Re Environ Qualification of Electrical Equipment,In Response to NRC .Methodology Used to Create Master List Described Project stage: Other ML20101T7451985-02-0101 February 1985 Responds to Generic Ltr 84-24 Re Certification of Compliance w/10CFR50.49, Environ Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. Appropriate Actions Taken to Correct Potential Deficiencies Project stage: Other 1983-03-10
[Table View] |
Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl InfoML20207N438 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
04/06/1982 |
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From: |
FRANKLIN INSTITUTE |
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To: |
NRC |
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Shared Package |
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ML20207N422 |
List: |
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References |
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CON-NRC-03-79-118, CON-NRC-3-79-118, RTR-NUREG-0737, RTR-NUREG-737 RAI-C5257-505, TAC-42508, NUDOCS 8701140217 |
Download: ML20207N438 (12) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20129D8211996-02-23023 February 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Davis-Besse Nuclear Power Station ML20071J3931994-06-30030 June 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001, for Plant ML20057E5921993-09-30030 September 1993 Auxiliary Feedwater System RISK-BASED Inspection Guidance for the DAVIS-BESSE Nuclear Power Plant ML20086F7071991-10-31031 October 1991 Ter,Pump & Valve Inservice Testing Program,Davis-Besse Nuclear Power Station,Unit 1 ML20058F8691990-10-31031 October 1990 PRESSURE-DEPENDENT Fragilities for Piping Components.Pilot Study on Davis-Besse Nuclear Power Station ML20069N4871990-08-17017 August 1990 Station Blackout Evaluation, Final Technical Evaluation Rept ML20083B5491990-07-13013 July 1990 Monthly Rept for June 1990 for FIN B-5699, ISLOCA Research Program ML20083B4731990-02-16016 February 1990 Assessment of Potential for ISLOCA at Davis-Besse Nuclear Power Station, Draft Rept ML20070Q6431989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Davis-Besse ML20245E9211988-08-31031 August 1988 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Davis-Besse Unit 1 ML20238A9461987-08-31031 August 1987 DAVIS-BESSE Uncertainty Study ML20214R2061987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Davis-Besse, Final Informal Rept ML20212Q0881986-11-30030 November 1986 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1, Informal Rept ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20210C1661986-03-0707 March 1986 Masonry Wall Design,Davis-Besse Unit 1, Technical Evaluation Rept ML20151L3451985-12-0606 December 1985 Suppl to Technical Evaluation Rept of Dcrdr for Davis-Besse Nuclear Power Station ML20210K1291985-11-19019 November 1985 Site Survey of Davis-Besse Maint Program & Practices, Technical Ltr Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20132D2071985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Davis-Besse Unit 1 ML20127J5941985-06-14014 June 1985 Preimplementation Audit of Dcrdr of Davis-Besse Nuclear Power Station ML20133P8831985-05-31031 May 1985 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1 ML20108F4441984-11-27027 November 1984 Masonry Wall Design,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20106A6541984-09-24024 September 1984 Control of Heavy Loads (C-10),Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20095H0631984-07-10010 July 1984 Draft Control of Heavy Loads - Phase II,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20086N2451984-02-29029 February 1984 Review of the DAVIS-BESSE Unit No. 1 Auxiliary Feedwater System Reliability Analysis ML20077L7891983-08-0909 August 1983 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Draft Technical Evaluation Rept ML20077K8451983-03-14014 March 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents, (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K1501982-11-24024 November 1982 ECCS Repts (F-47),TMI Action Plan Requirements, Davis-Besse Nuclear Power Station,Unit 1, Technical Evaluation Rept ML20071L3841982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Davis-Besse Nuclear Power Station, Technical Evaluation Rept ML20027C5001982-08-27027 August 1982 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station,Unit 1, Draft Technical Evaluation Rept ML20065S6051982-07-23023 July 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20069C5921982-06-23023 June 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20064L2821982-05-10010 May 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication (F-16,F-17) ML20027A7751982-04-30030 April 1982 Override & Reset of Control Circuitry in Ventilation/Purge Isolation & Other ESF Sys, Technical Evaluation Rept ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info ML20040G1591981-12-22022 December 1981 Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20052A0681981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint. ML19240C0021981-03-31031 March 1981 Inservice Testing Program for Pumps & Valves at Davis-Besse Nuclear Power Station - Unit 1 (Docket 50-346) for Period Nov 1977 Through Nov 1987, Safety Evaluation ML19208B8711979-07-30030 July 1979 Technical Evaluation Rept Re Alternative to Keylock Control to Bypass Valves.Supports Alternative Procedures ML19329C4671970-07-17017 July 1970 Review of Seismic Design Criteria for Davis-Besse. ML19329C4801969-10-31031 October 1969 Seismological & Geological Review. ML19329C4701969-10-28028 October 1969 Seismic Review. 1996-02-23
[Table view] Category:QUICK LOOK
MONTHYEARML20129D8211996-02-23023 February 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Davis-Besse Nuclear Power Station ML20071J3931994-06-30030 June 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001, for Plant ML20057E5921993-09-30030 September 1993 Auxiliary Feedwater System RISK-BASED Inspection Guidance for the DAVIS-BESSE Nuclear Power Plant ML20086F7071991-10-31031 October 1991 Ter,Pump & Valve Inservice Testing Program,Davis-Besse Nuclear Power Station,Unit 1 ML20058F8691990-10-31031 October 1990 PRESSURE-DEPENDENT Fragilities for Piping Components.Pilot Study on Davis-Besse Nuclear Power Station ML20069N4871990-08-17017 August 1990 Station Blackout Evaluation, Final Technical Evaluation Rept ML20083B5491990-07-13013 July 1990 Monthly Rept for June 1990 for FIN B-5699, ISLOCA Research Program ML20083B4731990-02-16016 February 1990 Assessment of Potential for ISLOCA at Davis-Besse Nuclear Power Station, Draft Rept ML20070Q6431989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Davis-Besse ML20245E9211988-08-31031 August 1988 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Davis-Besse Unit 1 ML20238A9461987-08-31031 August 1987 DAVIS-BESSE Uncertainty Study ML20214R2061987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Davis-Besse, Final Informal Rept ML20212Q0881986-11-30030 November 1986 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1, Informal Rept ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20210C1661986-03-0707 March 1986 Masonry Wall Design,Davis-Besse Unit 1, Technical Evaluation Rept ML20151L3451985-12-0606 December 1985 Suppl to Technical Evaluation Rept of Dcrdr for Davis-Besse Nuclear Power Station ML20210K1291985-11-19019 November 1985 Site Survey of Davis-Besse Maint Program & Practices, Technical Ltr Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20132D2071985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Davis-Besse Unit 1 ML20127J5941985-06-14014 June 1985 Preimplementation Audit of Dcrdr of Davis-Besse Nuclear Power Station ML20133P8831985-05-31031 May 1985 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1 ML20108F4441984-11-27027 November 1984 Masonry Wall Design,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20106A6541984-09-24024 September 1984 Control of Heavy Loads (C-10),Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20095H0631984-07-10010 July 1984 Draft Control of Heavy Loads - Phase II,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20086N2451984-02-29029 February 1984 Review of the DAVIS-BESSE Unit No. 1 Auxiliary Feedwater System Reliability Analysis ML20077L7891983-08-0909 August 1983 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Draft Technical Evaluation Rept ML20077K8451983-03-14014 March 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents, (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K1501982-11-24024 November 1982 ECCS Repts (F-47),TMI Action Plan Requirements, Davis-Besse Nuclear Power Station,Unit 1, Technical Evaluation Rept ML20071L3841982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Davis-Besse Nuclear Power Station, Technical Evaluation Rept ML20027C5001982-08-27027 August 1982 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station,Unit 1, Draft Technical Evaluation Rept ML20065S6051982-07-23023 July 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20069C5921982-06-23023 June 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20064L2821982-05-10010 May 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication (F-16,F-17) ML20027A7751982-04-30030 April 1982 Override & Reset of Control Circuitry in Ventilation/Purge Isolation & Other ESF Sys, Technical Evaluation Rept ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info ML20040G1591981-12-22022 December 1981 Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20052A0681981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint. ML19240C0021981-03-31031 March 1981 Inservice Testing Program for Pumps & Valves at Davis-Besse Nuclear Power Station - Unit 1 (Docket 50-346) for Period Nov 1977 Through Nov 1987, Safety Evaluation ML19208B8711979-07-30030 July 1979 Technical Evaluation Rept Re Alternative to Keylock Control to Bypass Valves.Supports Alternative Procedures ML19329C4671970-07-17017 July 1970 Review of Seismic Design Criteria for Davis-Besse. ML19329C4801969-10-31031 October 1969 Seismological & Geological Review. ML19329C4701969-10-28028 October 1969 Seismic Review. 1996-02-23
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20129D8211996-02-23023 February 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Davis-Besse Nuclear Power Station ML20071J3931994-06-30030 June 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001, for Plant ML20057E5921993-09-30030 September 1993 Auxiliary Feedwater System RISK-BASED Inspection Guidance for the DAVIS-BESSE Nuclear Power Plant ML20086F7071991-10-31031 October 1991 Ter,Pump & Valve Inservice Testing Program,Davis-Besse Nuclear Power Station,Unit 1 ML20058F8691990-10-31031 October 1990 PRESSURE-DEPENDENT Fragilities for Piping Components.Pilot Study on Davis-Besse Nuclear Power Station ML20069N4871990-08-17017 August 1990 Station Blackout Evaluation, Final Technical Evaluation Rept ML20083B5491990-07-13013 July 1990 Monthly Rept for June 1990 for FIN B-5699, ISLOCA Research Program ML20083B4731990-02-16016 February 1990 Assessment of Potential for ISLOCA at Davis-Besse Nuclear Power Station, Draft Rept ML20070Q6431989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Davis-Besse ML20245E9211988-08-31031 August 1988 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Davis-Besse Unit 1 ML20238A9461987-08-31031 August 1987 DAVIS-BESSE Uncertainty Study ML20214R2061987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Davis-Besse, Final Informal Rept ML20212Q0881986-11-30030 November 1986 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1, Informal Rept ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20210C1661986-03-0707 March 1986 Masonry Wall Design,Davis-Besse Unit 1, Technical Evaluation Rept ML20151L3451985-12-0606 December 1985 Suppl to Technical Evaluation Rept of Dcrdr for Davis-Besse Nuclear Power Station ML20210K1291985-11-19019 November 1985 Site Survey of Davis-Besse Maint Program & Practices, Technical Ltr Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20132D2071985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Davis-Besse Unit 1 ML20127J5941985-06-14014 June 1985 Preimplementation Audit of Dcrdr of Davis-Besse Nuclear Power Station ML20133P8831985-05-31031 May 1985 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1 ML20108F4441984-11-27027 November 1984 Masonry Wall Design,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20106A6541984-09-24024 September 1984 Control of Heavy Loads (C-10),Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20095H0631984-07-10010 July 1984 Draft Control of Heavy Loads - Phase II,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20086N2451984-02-29029 February 1984 Review of the DAVIS-BESSE Unit No. 1 Auxiliary Feedwater System Reliability Analysis ML20077L7891983-08-0909 August 1983 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Draft Technical Evaluation Rept ML20077K8451983-03-14014 March 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents, (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K1501982-11-24024 November 1982 ECCS Repts (F-47),TMI Action Plan Requirements, Davis-Besse Nuclear Power Station,Unit 1, Technical Evaluation Rept ML20071L3841982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Davis-Besse Nuclear Power Station, Technical Evaluation Rept ML20027C5001982-08-27027 August 1982 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station,Unit 1, Draft Technical Evaluation Rept ML20065S6051982-07-23023 July 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20069C5921982-06-23023 June 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20064L2821982-05-10010 May 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication (F-16,F-17) ML20027A7751982-04-30030 April 1982 Override & Reset of Control Circuitry in Ventilation/Purge Isolation & Other ESF Sys, Technical Evaluation Rept ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info ML20040G1591981-12-22022 December 1981 Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20052A0681981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint. ML19240C0021981-03-31031 March 1981 Inservice Testing Program for Pumps & Valves at Davis-Besse Nuclear Power Station - Unit 1 (Docket 50-346) for Period Nov 1977 Through Nov 1987, Safety Evaluation ML19208B8711979-07-30030 July 1979 Technical Evaluation Rept Re Alternative to Keylock Control to Bypass Valves.Supports Alternative Procedures ML19329C4671970-07-17017 July 1970 Review of Seismic Design Criteria for Davis-Besse. ML19329C4801969-10-31031 October 1969 Seismological & Geological Review. ML19329C4701969-10-28028 October 1969 Seismic Review. 1996-02-23
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20129D8211996-02-23023 February 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Davis-Besse Nuclear Power Station ML20071J3931994-06-30030 June 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001, for Plant ML20057E5921993-09-30030 September 1993 Auxiliary Feedwater System RISK-BASED Inspection Guidance for the DAVIS-BESSE Nuclear Power Plant ML20086F7071991-10-31031 October 1991 Ter,Pump & Valve Inservice Testing Program,Davis-Besse Nuclear Power Station,Unit 1 ML20058F8691990-10-31031 October 1990 PRESSURE-DEPENDENT Fragilities for Piping Components.Pilot Study on Davis-Besse Nuclear Power Station ML20069N4871990-08-17017 August 1990 Station Blackout Evaluation, Final Technical Evaluation Rept ML20083B5491990-07-13013 July 1990 Monthly Rept for June 1990 for FIN B-5699, ISLOCA Research Program ML20083B4731990-02-16016 February 1990 Assessment of Potential for ISLOCA at Davis-Besse Nuclear Power Station, Draft Rept ML20070Q6431989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Davis-Besse ML20245E9211988-08-31031 August 1988 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Davis-Besse Unit 1 ML20238A9461987-08-31031 August 1987 DAVIS-BESSE Uncertainty Study ML20214R2061987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Davis-Besse, Final Informal Rept ML20212Q0881986-11-30030 November 1986 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1, Informal Rept ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20210C1661986-03-0707 March 1986 Masonry Wall Design,Davis-Besse Unit 1, Technical Evaluation Rept ML20151L3451985-12-0606 December 1985 Suppl to Technical Evaluation Rept of Dcrdr for Davis-Besse Nuclear Power Station ML20210K1291985-11-19019 November 1985 Site Survey of Davis-Besse Maint Program & Practices, Technical Ltr Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20132D2071985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Davis-Besse Unit 1 ML20127J5941985-06-14014 June 1985 Preimplementation Audit of Dcrdr of Davis-Besse Nuclear Power Station ML20133P8831985-05-31031 May 1985 Conformance to Reg Guide 1.97,Davis-Besse Nuclear Power Station,Unit 1 ML20108F4441984-11-27027 November 1984 Masonry Wall Design,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20106A6541984-09-24024 September 1984 Control of Heavy Loads (C-10),Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20095H0631984-07-10010 July 1984 Draft Control of Heavy Loads - Phase II,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20086N2451984-02-29029 February 1984 Review of the DAVIS-BESSE Unit No. 1 Auxiliary Feedwater System Reliability Analysis ML20077L7891983-08-0909 August 1983 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Draft Technical Evaluation Rept ML20077K8451983-03-14014 March 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents, (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K1501982-11-24024 November 1982 ECCS Repts (F-47),TMI Action Plan Requirements, Davis-Besse Nuclear Power Station,Unit 1, Technical Evaluation Rept ML20071L3841982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Davis-Besse Nuclear Power Station, Technical Evaluation Rept ML20027C5001982-08-27027 August 1982 Control of Heavy Loads (C-10),Toledo Edison Co,Davis-Besse Nuclear Power Station,Unit 1, Draft Technical Evaluation Rept ML20065S6051982-07-23023 July 1982 Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20069C5921982-06-23023 June 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept ML20064L2821982-05-10010 May 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication (F-16,F-17) ML20027A7751982-04-30030 April 1982 Override & Reset of Control Circuitry in Ventilation/Purge Isolation & Other ESF Sys, Technical Evaluation Rept ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info ML20040G1591981-12-22022 December 1981 Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20052A0681981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint. ML19240C0021981-03-31031 March 1981 Inservice Testing Program for Pumps & Valves at Davis-Besse Nuclear Power Station - Unit 1 (Docket 50-346) for Period Nov 1977 Through Nov 1987, Safety Evaluation ML19208B8711979-07-30030 July 1979 Technical Evaluation Rept Re Alternative to Keylock Control to Bypass Valves.Supports Alternative Procedures ML19329C4671970-07-17017 July 1970 Review of Seismic Design Criteria for Davis-Besse. ML19329C4801969-10-31031 October 1969 Seismological & Geological Review. ML19329C4701969-10-28028 October 1969 Seismic Review. 1996-02-23
[Table view] |
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REQUEST FOR ADDITIONAL INFORMATION EQUIPMENT ENVIRONMENTAL QUALIFICATION (EEQ)
REVIEW OF LICENSEES' RESOLUTION OF OUTSTANDING ISSUES FROM NRC EQUIPMENT ENVIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (SER) AND TMI ACTION PLAN INSTALLED EQUIPMENT The Toledo Edison Company Davis-Besse Unit 1 NRC Docket No. 50-346 December 22, 1981 NRC TAC No. 42508 Rev., 1, April 6, 1982 l
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._ _ Franklin Research Center A Division of The Franklin Institute The Bengmm Franklin Park *ey. Phala . Pa 19103(215)448 1000 l 8701140217 820416 l PDR ADOCK 05000346 l
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, , RAI-C5257-505 Rev. 1, April 6, 1982 BACKGROUND Franklin Research Center (FRC) of Philadelphia, Pa. is providing assis-tance to the U.S. Nuclear Regulatory Commission (NRC) for the equipment environmental qualification (EEQ) ' review of operating reactors. - FRC will perform an EEQ review of the Licensee's 90-day response to outstanding issues from the NRC Equipment Environmental Qualification Safety Evaluation Report-(SER) and the installed TMI Action Plan equipment. The review will be limited to safety-related equipment potentially exposed to a harsh environment. The results will be presented in the form of a technical evaluation report for each plant.
This request for additional information (RAI) is the result of an evaluation of the information provided by letters dated October 12, 1981 [1]
and January 30, 1981 [2].* By letter dated March 3, 1982 [5], the Licensee transmitted all of the documents requested and included three additional reports as follows:I }
h J. A. Sears Test Reports Radiation Test of E10 Series Differential Pressure Transmitters of the MCA/RRW Type Foxboro Co., 00 Aug. 1973 T3-1068 (1) h S. Corbett Seismic Qualification Test Report in Dif ferential Pressure Switches Model Numbers 288A and 289A.
Approved Engineering Test La, 26 Apr. 1979 5480-8386(1) h Environmental Qualification Test Summary for Peach Bottom 2 Barton Core Spray Header to Sparger Differential Pressure Indicating Switch General Electric, NSE $79020(1)
- Nunbers in brackets refer to citations found in the list of references.
- Throughout the text, superscript numbers in parentheses indicate the revision in which the underlined material preceding the superscript was added.
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. RAI-C5257-505 Rev. 1, April 6, 1982
- 4. Environmental Qualification Test Summary for Quad Cities 1 &~2 Barton Recirculation Loop Pressure Differential Pressure Indicating Switch General Electric NSE $80185(1)
A. FRC REVIEW OF THE LICENSEE'S 90-DAY RESPONSE TO THE NRC EEQ SER INFORMATION REQUESTED DATE RECEIVED BY FRC***
- 1. In reference to the Licensee's 90-day response [1] to the NRC SER [3], a legible single copy of each of the following qualification documents is requested in order that the FRC evaluation may proceeds
- a. Wyle Laboratories Report No. 44354-1 3/11/82 [5] (1)
" Qualification Test Report for Four (4)
NEMA 4 Enclosures," March 8, 1979 (for States, Raychem).
- b. Rosemount Test Report ho. 87414, 3/11/82 [5](1)
" Investigation Radiation Requirement, Model 177 HW," 8/16/74
- c. Foxboro Company Test Report No. T2-1075, 3/11/82 [5) (1)
" Radiation Test of E10 Series Differential Pressure Transmitter of the Standard Construction Type," August, 1973.
- d. Rosemount Test Report No. 12756B Rev. A, 3/11/82 [5) (1)
"Rosemount Modified Model 1152 Pressure Transmitter Environmental Class lA Equipment," 12/5/75.
- e. NAM 00 Qualification Report, " Estimation 3/11/82 [5](1) of Qualified Life of EA740-20000 Rev. C, D, or E, Revised 2/27/80.
i l f. Microswitch Engineering Report No. Deleted [5] (1) i LTR-24407, " Preliminary Evaluation of
'LS,' 'HS,' ' CMC,' 'PT,' and ' Series 2' Type Switches Under Electrical Aging, l Environssental Aging, and Seismic Vibration Tests."
i f ***This column will be completed by FRC as the requested information is received.-
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- RAI-C5257-505 -l Rev. 1, April 6, 1982 DATE RECEIVED BY FRC***
- g. ITT Barton Report No. R3-288A-1, "IEEE 3/11/82 [5](1) 344-1975 Seismic and Radiation l
Qualification Tests for ITT Barton Differential Pressure Indicating
- Switches Models 288A and 289A. )
- h. Summary Report No. QSR 027-A-01, BNR 3/11/82 [5](1) '
Equipment Qualification Summary, Barton Model 288 Differential Pressure Switch, 10/2/80.
- i. ITT General Controls Engineering Report 3/11/82 [5](1)
No. 721.77.095 ADDENDUM $2,
" Certification of NH90 Series Actuators For 50"C (122*F) Ambient Temperature and 20,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> Usage at 60% Rated Load,"
5/16/81.
- j. ITT General Controls Engineering Report 3/11/82 [5](1)
No. 721.77.095 ADDENDUM 95, " Summary of NH90 (Model B) Series Actuator Supplemental Generic Qualification Testing for Class lE Requirements, i Outside Containment," 2/10/80.
- k. Letter of 6/4/81 from ASCO to EDS 3/11/82 [5](1) containing materials lists for ASCO coils.
- 1. Intter of 6/18/81 from ASCO to EDS 3/11/82 [5](1) containing Class A and Class F coil lead wires.
- m. Letter of 6/8/81 from ASCO to Toledo 5/11/82 [5](1) l Edison Co. concerning environmental I qualification of ASCO valves.
- n. Letter of 9/22/81 from Bailey Meter Co. 3/11/82 [5] (1) to EDS concerning Bailey Meter Materials lists.
- o. Letter of 5/21/81 from Barksdale to EDS 3/11/82 [5] (1) containing Non-Metallic Material List for I T2H-M155S Temperature Switch.
- p. Letter of 10/30/75 from Boston Insulated 3/11/82 [5] (1)
Wire and Cable Co. to Bechtel concerning ,
IDCA simulation tests of LIW cable. j r nklin Research Center I A Dhesson of The F#enhhn Insuute
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DATE RECEIVED BY FRC***
- q. Letter of 3/26/81 from Fenwal to EDS ) 3/11/82 [5](1) concerning non-metallic parts in Fenwal 27120-22 Thermoswitch.
- c. Letter of 4/21/81 from Foxboro to EDS 3/11/82 [5](1) concerning environmental qualification of Foxboro transmitters.
- s. Letter of 4/13/81 from General Dynamics 3/11/82 [5] (1) to EDS concerning Stator Coil Insulation materials for Electro Dynamic Motors.
- t. Letter of 3/26/81 from Differential 3/11/82 [5] (1)
Pressure Instruments to EDS concerning non-metallic parts in ITT Barton Pressure Indicating Switches Models 288A and 289A.
, u. Letter of 6/17/81 f rom D.P.I. to EDS 3/11/82 [51(1) concerning materials used in 288 and 289 .
ITT Barton Differential Pressure Switch.
- v. Letter of 6/5/81 from Licon to EDS 3/11/82 [5](1) concerning materials in Barton parts Nos.
00068-004-T and 5891-0001-Z.
I w. Letter of 6/19/81 from Kerite to EDS 3/11/82 [ 5] (1)
- concerning submergence of Kerite Cable.
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- x. Letter of 4/27/79 from B&W to TECO 3/11/82 [5]II) concerning Limitorque test reports.
- y. Letter of 7/28/80 from B&W to Bechtel 3/11/82 [5]III
- concerning Limitorque test reports. ,
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- z. Letter of 11/5/80 from Limitorque to TECO 3/11/82 [5] (1) concerning Limitorque test reports.
l aa. Letter of 6/1/81 from B&W to TECO 3/11/82 [ 5) (1) i concerning Limitorque test reports.
bb. Letter of 7/13/81 from Bechtel to EDS 3/11/82 [5] (1) concerning Limitorque test reports.
cc. Letter of 7/21/81 from Limitorque to EDS 3/11/82 [5) (1) concerning Limitorque test reports. i I
dd. Letter of 7/7/81 f rom Limitorque to EDS 3/11/82 [5] II)
, concerning Limitorque test reports.
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ee. Letter of 4/28/81 from Microswitch to EDS 3/11/82 [5]II) containing parts list for Microswitch ILS3.
ff. Letter of 4/28/81 from Microswitch to EDS 3/11/82 [5]III parts list for Microswitch LSD2B-4N.
gg. Letter of 5/1/81 from Okonite to EDS 3/11/82 [5] (1) containing data on EP insulation.
hh. Letter of 9/18/81 from Raychem to EDS 3/11/82 [5] (1) concerning Moisture Resistance of WCSF-N Heat Shrink Tubing.
ii. Letter of 11/10/81 from Rees to Bechtel 3/11/82 [5] (1) containing Rees lists of components and materials lists.
jj. Letter of 3/11/81 f rom Rees to EDS 3/11/82 [5] (1) containing Material List for Pushbutton Switches.
kk. Letter of 4/2/81 from Rees to EDS 3/11/82 [5] (1) containing Material List for Pushbutton Switches.
- 11. Letter of 7/14/80 from Stanwick to 3/11/82 [5) (1)
Bechtel containing component materials lists and testing documentation for Stanwick Terminal Blocks.
mm. Letter of 2/18/81 from Stanwick to EDS 3/11/82 [5)(1) containing component materials lists and testing data for Stanwick Type G Terminal Block.
nn. Letter of 1/27/78 from States to Yankee 3/11/82 [5) (1)
Atomic Electric concerning States NT and ZWM Terminal Blocks.
oo. Letter or 9/18/80 f rom Southern Company 3/11/82 [5] II) services concerning Wyle Test Report l 44354-1.
f pp. Letter of 2/9/81 f rom States to EDS 3/11/82 [51 (1) concerning States ZWM and NT Terminal Block materials.
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- RAI-C5257-505 Eev. 1, April 6, 1982
> DATE RECEIVED BY FRC***
qq. Letter of 12/9/80 from SOR to TECO 3/11/82 [5](1) containing material lists for non-metallic parts in SOR pressure switches.
tr. Letter of 7/9/81 from SOR to EDS 3/11/82 [5](1) concerning qualification of SOR Pressure Switches.
ss. Letter of 7/20/81 from Westinghouse to 3/11/82 [5](1)
EDS containing environmental
. qualification documentation for Westinghouse Hydrog.n Dilution System Motors.
tt. Letter of 8/15/80 from Toledo Edison Co. 3/11/82 [5] (1) to Babcock and Wilcox concerning HPI and LPI pumps.
uu. Telephone conversation of 7/30/81 between 3/11/82 [5] (1)
F. Levancosti and J. Thompson concerning standard test time for Equipment Qualification Tests.
vv. EDS Calculation 1040-001-038, Arrhenius 3/11/82 [5](1)
Model for Rosemount, Foxboro, and Bailey i Transmitters.
! ww. EDS Calculation 1040-001-040, Low pH 3/11/82 [5]II)
- Analysis for Components Tested in a High
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pH Chemical Spray.
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! xx. EDS Calculation 1040-001-042, Chemical 3/11/82 [5] III l Spray Analysis of Safety-Related l Components.
I yy. Boston Insulated Wire & Cable Company 3/11/82 [5)(1)
Prototype Test Report No. 73C212, 6/18/73
- 22. Amphenol SAMS Operation Technical Report 3/11/82 [5) (1) 123-1268, "Special Prototype Radiation, Environmental and Short Circuit Testing of a Type 2 Low Voltage Power Penetration Assembly used on Davis-Besse Nuclear Power Station Unit No. 1," 3/12/75.
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. . RAI-C5257-505 Rev. 1, April 6, 1982 B. FHC REVIIEt OF INSTALLED TMI ACTION PLAN ITEMS INFORMATION REQUESTED DATE RECEIVED BY FRC***
- 1. The correlation of the installed TMI equipment items with the specific sections of NUREG-0737 [4] is requested.
- a. Identification of all TMI Action Plan equipment installed after 1/1/81 is requested.
- b. The approximate installation date for the TMI Action Plan equipment items is requested so that the appropriate qualification criteria (NUREG-0588 or DDR Guidelines) can be used in the EEQ evaluation.
- 2. The qualification documents, e.g., the actual test reports and associated correspondence cited as evidence of qualification listed on the SCEW sheets, for all identified 'IMI Action Plan equipment are requested. [The identification of those reports considered to be proprietary is requested so that proper control of documents can be maintained.)
- 3. Where the Licensee has a standard Owners' Group position with respect to a NUREG-0737 technical area or has requested extensions of implementation dates, this information is requested in order to incorporate it into the review.
C. INSTRUCTIONS FOR TRANSMITTING INFORMATION REQUESTED
- 1. The schedule for completion of the FRC assignment requires that the Licensee provide the roquested information within 3 weeks of the date of the RAI.
- 2. The Licensee may transmit the requested information as follows:
o complete package directly to the NRC project manager or 14 0 O.
i -[E'3 ranklin Research Cen A Dueton of the Fre%2n inetsue.ter
. RAI-C5257-505 Rev. 1, April 6, 1982 o copy of cover letter to NRC project manager and complete package to FRC.
FHC mailing address is as follows:
Mr. Cyril J. Crane Franklin Research Center i The Parkway at Twentieth Street
, Philadelphia, PA 19103 Telephone No. 215/448-1353 Telecopy No. 215/448-1296 Telecopy ConfArmation No. 215/448-1215 4
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e e e RAI-C5257-505 Rev. 1, April 6, 1982 REFERENCE 3 3
- 1. R. P. Crouse Letter to J. F. Stolz, NRC.
Subject:
Response to SER for the Environmental Qualification of Safety-Related Electrical Equipment at Davis-Besse Nuclear Power Station Toledo Edison Co., 12-Oct-81 Serial No. 750
- 2. R. P. Crouse Letter to J. Keppler, NRC.
Subject:
Revision 3 of response to IE Bulletin 79-018 for Davis-Basse Nuclear Power Station Unit 1
'Ibledo Edison, 30-Jan-81 1-184
- 3. Of fice of Nuclear Reactor Regulation Safety Evaluation Report for Davis-Besse Unit 1 e Environmental Qualification of Safety-Related Electrical Equipment NHC, 05-Jun-81
- 4. NUREG-0737, " Clarification of TMI Action Plan Requirements" NRC, November 1980
,5_., R. 1. Crouse Letter to J. F. Stolz, NRC. Subiect: Transmittal of Requested Information Concerning Environmental Qualification of Safety-Related Electrical Equipment at Davis-Besse Unit 1 Toledo Edison, 03 Mar. 1982 A82-156B W I
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, RAI-C5257-508 Rev. 5, April 7, 1982 REFERENCES
- 1. E. R. Mathews and C. W. Geisler Letter to J. G. Keppler, NRC.
Subject:
Response to IE Bulletin 79-Olu, Supplement 3 Wisconsin Public Service Corp., 02-Feb-81 NRC-81-15
- 2. E. R. Mathews and C. A. Schrock Letter to S. A. Varga, NRC. Subject Kewaunee Nuclear Power Plant; Environmental Qualification of Safety-Related Elec-trical Equipment Response to NRC SER Wisconsin Public Service Corp., 21-Sep-81 N RC-81-159
- 3. Of fice of Nuclear Reactor Regulation hafety Evaluation Report for Kewaunee Nuclear Power Plant Environmental Qualification of Safety-Related Electrical Equipment NRC, 1981
- 4. E. R. Mathews Letter to J. G. Keppler, NRC. Subjects Kevaunce Nuclear Power Plant, IE Bulletin 7 9-01B, Qualification of Class AE Equipment, with attachments Wisconsin Public Service Corp. 10-Oct-80
- 5. NUREG-0737, " Clarification of TMI Action Plan Requirements" NRC, November 1980 bz E. R. Ma thews Lotter to S. A. Varga, NRC. Subjects Kewaunee Nuclear Power Plant. . .lligh Energy Line Breaks (llELBs) and Submergence Outside of Containment Wisconsin Public Service Corp., 15-Dec-81 NRC-81-204(1) 73 E. R. Mathews Letter to S. A. Varga, NRC. Subject Kewaunee Nuclear Power Planti Environmental Qualification of Safety-Related Electrical Equipment -
Heta Done Equipment Qualification Wisconsin Public Service Corp., 02-Nov-81 NRC-81-178(2)
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. 8. E. R. Mathews l Letter to S. A. Varga, NRC. Subjects Kewaunee Nuclear Power Plantt Environmental Qualification of Safety-Related Electrical Equipment -
Chemical Spray Wisconsin Public Service Corp., 29-Jan-82 (3) h Postulated Pipe Failure Analysis Wisconsin Public Service Corp.
FSAR App. 10-A(4)
- 10. E. R. Mathews Letter to S. A. Varga, NRC. Subjects Kewaunee Nuclear Power Plant; Environmental Qualification of Class lE Electrical Equipment Wisconsin Public Service, 26-Feb-82
- NRC-82-35, 074-TA-508 (5) i
- 11. E. R. Mathews
! Letter to S. A. Varga, NRC. Subjects Kewaunee Nuclear Power Plants Environmental Qualification of Safety-Related Electric Equipment 4 Request for Additional Information Wisconsin Public Service, 18-Mar-82 N RC-82-46 ( 5) 1 i
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