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Category:CONTRACTED REPORT - RTA
MONTHYEARML17335A1681998-03-31031 March 1998 Final TER on step-2 Review of IPEEE at DC Cook Nuclear Plant,Units 1 & 2, March 1998 ML17334A6111998-01-0707 January 1998 TER Confirmatory Calculations of DC Cook Sump Water Level. ML17333A6911996-06-28028 June 1996 Rev 0 to, Review of Donald C. Cook Nuclear Power Plant Methodology for Analysis of Fire Barrier Ampacity Derating Factors, Ltr Rept ML17333A5511994-12-0404 December 1994 Ltr Rept, Evaluation of Cook Ipe/Hra Matls. ML20126H1381991-07-31031 July 1991 Draft Afs Risk-Based Insp Guide for DC Cook Nuclear Power Plant ML20082K7531991-07-30030 July 1991 Final Rept SAIC-91/6677, Technical Evaluation Rept for Cook Nuclear Plant Units 1 & 2 Station Blackout Evaluation ML17328A1251989-06-30030 June 1989 Pump & Valve Inservice Testing Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20245H2301989-02-15015 February 1989 Internal Conduit Fire Seal Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML17328A8721988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant Unit 2. ML17328A8711988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant,Unit 1. ML17334B1091987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:Cook 1 & 2, Final Informal Rept ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20204G4181987-03-31031 March 1987 Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components) Cook Units 1 & 2 ML17334B1101987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification,Cook Units 1 & 2, Informal Rept ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML17324B2461987-02-0606 February 1987 Dcrdr Evaluations,Phases III-V,DC Cook Units 1 & 2, Informal Technical Communication ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML17324B2191986-11-0606 November 1986 Review of App R Procedures for Post-Fire Remote Emergency Shutdown Outside Control Room,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20207A7041986-06-30030 June 1986 Conformance to Reg Guide 1.97,DC Cook Nuclear Plant Units 1 & 2 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML17324A9561986-03-31031 March 1986 Technical Evaluation Rept of 1984 Meteorological Data from Donald C Cook Nuclear Power Plant. ML17321A9321985-10-17017 October 1985 Review of Licensee...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 DC Cook..., Technical Evaluation 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 ML20206F3131985-02-0404 February 1985 Revised Containment Hydrogen Analysis Review of DC Cook, Program Ltr Rept.Related Documentation Encl ML17320A4811983-09-30030 September 1983 DC Cook,Units 1 & 2 Inservice Insp Plan, Technical Evaluation Rept ML20077L8511983-09-0101 September 1983 Control of Heavy Loads (C-10) Indiana & Michigan Electric Co,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20077K9771983-07-27027 July 1983 Revised Masonry Wall Design (B-59),DC Cook Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML17320A5491983-02-24024 February 1983 Draft Control of Heavy Loads (C-10),Donald C Cook Nuclear Power Plant Units 1 & 2, Technical Evaluation Rept ML20076C4091983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D1821982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),DC Cook Nuclear Plant Unit 1, Technical Evaluation Rept,Vols 1 & 2 ML20027D1811982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept.Vols I & II ML20069H8611982-10-0808 October 1982 Radiological Effluent Tech Spec Implementation (A-2),DC Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17319B6161982-09-0303 September 1982 DC Cook Nuclear Plant Units 1 & 2,Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20069D0761982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Final Technical Evaluation Rept ML20062E2251982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations.D.C. Cook Case Study.Docket Nos. 50-315 and 50-316.(Indiana and Michigan Electric Company) ML18005A0091982-04-0808 April 1982 to 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. ML17319B3231982-04-0707 April 1982 to 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. ML17319B2871982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20041D7251982-01-31031 January 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Preliminary Technical Evaluation Rept ML17326A9271981-11-20020 November 1981 Control of Heavy Loads. ML20132C5541981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for DC Cook Nuclear Power Plant Units 1 & 2 ML19347E9081981-04-30030 April 1981 Adequacy of Station Electric Distribution Sys Voltages,Dc Cook Units 1 & 2, Technical Evaluation Rept ML17319A9411981-04-27027 April 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, Technical Evaluation Rept ML19240C0001981-03-31031 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20003C1061981-01-31031 January 1981 Technical Evaluation Rept,Adequacy of Station Electrical Distribution Sys Voltages,Dc Cook Nuclear Station Units 2 & 3, Preliminary Rept ML17331A6131980-11-30030 November 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Dc Cook Units 1 & 2, Revised Technical Evaluation Rept ML17326A7511980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Donald C. Cook Units 1 & 2, Technical Evaluation Rept 1998-03-31
[Table view] Category:QUICK LOOK
MONTHYEARML17335A1681998-03-31031 March 1998 Final TER on step-2 Review of IPEEE at DC Cook Nuclear Plant,Units 1 & 2, March 1998 ML17334A6111998-01-0707 January 1998 TER Confirmatory Calculations of DC Cook Sump Water Level. ML17333A6911996-06-28028 June 1996 Rev 0 to, Review of Donald C. Cook Nuclear Power Plant Methodology for Analysis of Fire Barrier Ampacity Derating Factors, Ltr Rept ML17333A5511994-12-0404 December 1994 Ltr Rept, Evaluation of Cook Ipe/Hra Matls. ML20126H1381991-07-31031 July 1991 Draft Afs Risk-Based Insp Guide for DC Cook Nuclear Power Plant ML20082K7531991-07-30030 July 1991 Final Rept SAIC-91/6677, Technical Evaluation Rept for Cook Nuclear Plant Units 1 & 2 Station Blackout Evaluation ML17328A1251989-06-30030 June 1989 Pump & Valve Inservice Testing Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20245H2301989-02-15015 February 1989 Internal Conduit Fire Seal Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML17328A8721988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant Unit 2. ML17328A8711988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant,Unit 1. ML17334B1091987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:Cook 1 & 2, Final Informal Rept ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20204G4181987-03-31031 March 1987 Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components) Cook Units 1 & 2 ML17334B1101987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification,Cook Units 1 & 2, Informal Rept ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML17324B2461987-02-0606 February 1987 Dcrdr Evaluations,Phases III-V,DC Cook Units 1 & 2, Informal Technical Communication ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML17324B2191986-11-0606 November 1986 Review of App R Procedures for Post-Fire Remote Emergency Shutdown Outside Control Room,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20207A7041986-06-30030 June 1986 Conformance to Reg Guide 1.97,DC Cook Nuclear Plant Units 1 & 2 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML17324A9561986-03-31031 March 1986 Technical Evaluation Rept of 1984 Meteorological Data from Donald C Cook Nuclear Power Plant. ML17321A9321985-10-17017 October 1985 Review of Licensee...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 DC Cook..., Technical Evaluation 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 ML20206F3131985-02-0404 February 1985 Revised Containment Hydrogen Analysis Review of DC Cook, Program Ltr Rept.Related Documentation Encl ML17320A4811983-09-30030 September 1983 DC Cook,Units 1 & 2 Inservice Insp Plan, Technical Evaluation Rept ML20077L8511983-09-0101 September 1983 Control of Heavy Loads (C-10) Indiana & Michigan Electric Co,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20077K9771983-07-27027 July 1983 Revised Masonry Wall Design (B-59),DC Cook Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML17320A5491983-02-24024 February 1983 Draft Control of Heavy Loads (C-10),Donald C Cook Nuclear Power Plant Units 1 & 2, Technical Evaluation Rept ML20076C4091983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D1821982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),DC Cook Nuclear Plant Unit 1, Technical Evaluation Rept,Vols 1 & 2 ML20027D1811982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept.Vols I & II ML20069H8611982-10-0808 October 1982 Radiological Effluent Tech Spec Implementation (A-2),DC Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17319B6161982-09-0303 September 1982 DC Cook Nuclear Plant Units 1 & 2,Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20069D0761982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Final Technical Evaluation Rept ML20062E2251982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations.D.C. Cook Case Study.Docket Nos. 50-315 and 50-316.(Indiana and Michigan Electric Company) ML18005A0091982-04-0808 April 1982 to 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. ML17319B3231982-04-0707 April 1982 to 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. ML17319B2871982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20041D7251982-01-31031 January 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Preliminary Technical Evaluation Rept ML17326A9271981-11-20020 November 1981 Control of Heavy Loads. ML20132C5541981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for DC Cook Nuclear Power Plant Units 1 & 2 ML19347E9081981-04-30030 April 1981 Adequacy of Station Electric Distribution Sys Voltages,Dc Cook Units 1 & 2, Technical Evaluation Rept ML17319A9411981-04-27027 April 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, Technical Evaluation Rept ML19240C0001981-03-31031 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20003C1061981-01-31031 January 1981 Technical Evaluation Rept,Adequacy of Station Electrical Distribution Sys Voltages,Dc Cook Nuclear Station Units 2 & 3, Preliminary Rept ML17331A6131980-11-30030 November 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Dc Cook Units 1 & 2, Revised Technical Evaluation Rept ML17326A7511980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Donald C. Cook Units 1 & 2, Technical Evaluation Rept 1998-03-31
[Table view] Category:ETC. (PERIODIC
MONTHYEARML17335A1681998-03-31031 March 1998 Final TER on step-2 Review of IPEEE at DC Cook Nuclear Plant,Units 1 & 2, March 1998 ML17334A6111998-01-0707 January 1998 TER Confirmatory Calculations of DC Cook Sump Water Level. ML17333A6911996-06-28028 June 1996 Rev 0 to, Review of Donald C. Cook Nuclear Power Plant Methodology for Analysis of Fire Barrier Ampacity Derating Factors, Ltr Rept ML17333A5511994-12-0404 December 1994 Ltr Rept, Evaluation of Cook Ipe/Hra Matls. ML20126H1381991-07-31031 July 1991 Draft Afs Risk-Based Insp Guide for DC Cook Nuclear Power Plant ML20082K7531991-07-30030 July 1991 Final Rept SAIC-91/6677, Technical Evaluation Rept for Cook Nuclear Plant Units 1 & 2 Station Blackout Evaluation ML17328A1251989-06-30030 June 1989 Pump & Valve Inservice Testing Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20245H2301989-02-15015 February 1989 Internal Conduit Fire Seal Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML17328A8721988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant Unit 2. ML17328A8711988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant,Unit 1. ML17334B1091987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:Cook 1 & 2, Final Informal Rept ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20204G4181987-03-31031 March 1987 Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components) Cook Units 1 & 2 ML17334B1101987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification,Cook Units 1 & 2, Informal Rept ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML17324B2461987-02-0606 February 1987 Dcrdr Evaluations,Phases III-V,DC Cook Units 1 & 2, Informal Technical Communication ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML17324B2191986-11-0606 November 1986 Review of App R Procedures for Post-Fire Remote Emergency Shutdown Outside Control Room,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20207A7041986-06-30030 June 1986 Conformance to Reg Guide 1.97,DC Cook Nuclear Plant Units 1 & 2 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML17324A9561986-03-31031 March 1986 Technical Evaluation Rept of 1984 Meteorological Data from Donald C Cook Nuclear Power Plant. ML17321A9321985-10-17017 October 1985 Review of Licensee...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 DC Cook..., Technical Evaluation 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 ML20206F3131985-02-0404 February 1985 Revised Containment Hydrogen Analysis Review of DC Cook, Program Ltr Rept.Related Documentation Encl ML17320A4811983-09-30030 September 1983 DC Cook,Units 1 & 2 Inservice Insp Plan, Technical Evaluation Rept ML20077L8511983-09-0101 September 1983 Control of Heavy Loads (C-10) Indiana & Michigan Electric Co,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20077K9771983-07-27027 July 1983 Revised Masonry Wall Design (B-59),DC Cook Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML17320A5491983-02-24024 February 1983 Draft Control of Heavy Loads (C-10),Donald C Cook Nuclear Power Plant Units 1 & 2, Technical Evaluation Rept ML20076C4091983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D1821982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),DC Cook Nuclear Plant Unit 1, Technical Evaluation Rept,Vols 1 & 2 ML20027D1811982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept.Vols I & II ML20069H8611982-10-0808 October 1982 Radiological Effluent Tech Spec Implementation (A-2),DC Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17319B6161982-09-0303 September 1982 DC Cook Nuclear Plant Units 1 & 2,Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20069D0761982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Final Technical Evaluation Rept ML20062E2251982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations.D.C. Cook Case Study.Docket Nos. 50-315 and 50-316.(Indiana and Michigan Electric Company) ML18005A0091982-04-0808 April 1982 to 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. ML17319B3231982-04-0707 April 1982 to 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. ML17319B2871982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20041D7251982-01-31031 January 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Preliminary Technical Evaluation Rept ML17326A9271981-11-20020 November 1981 Control of Heavy Loads. ML20132C5541981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for DC Cook Nuclear Power Plant Units 1 & 2 ML19347E9081981-04-30030 April 1981 Adequacy of Station Electric Distribution Sys Voltages,Dc Cook Units 1 & 2, Technical Evaluation Rept ML17319A9411981-04-27027 April 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, Technical Evaluation Rept ML19240C0001981-03-31031 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20003C1061981-01-31031 January 1981 Technical Evaluation Rept,Adequacy of Station Electrical Distribution Sys Voltages,Dc Cook Nuclear Station Units 2 & 3, Preliminary Rept ML17331A6131980-11-30030 November 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Dc Cook Units 1 & 2, Revised Technical Evaluation Rept ML17326A7511980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Donald C. Cook Units 1 & 2, Technical Evaluation Rept 1998-03-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML17335A1681998-03-31031 March 1998 Final TER on step-2 Review of IPEEE at DC Cook Nuclear Plant,Units 1 & 2, March 1998 ML17334A6111998-01-0707 January 1998 TER Confirmatory Calculations of DC Cook Sump Water Level. ML17333A6911996-06-28028 June 1996 Rev 0 to, Review of Donald C. Cook Nuclear Power Plant Methodology for Analysis of Fire Barrier Ampacity Derating Factors, Ltr Rept ML17333A5511994-12-0404 December 1994 Ltr Rept, Evaluation of Cook Ipe/Hra Matls. ML20126H1381991-07-31031 July 1991 Draft Afs Risk-Based Insp Guide for DC Cook Nuclear Power Plant ML20082K7531991-07-30030 July 1991 Final Rept SAIC-91/6677, Technical Evaluation Rept for Cook Nuclear Plant Units 1 & 2 Station Blackout Evaluation ML17328A1251989-06-30030 June 1989 Pump & Valve Inservice Testing Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20245H2301989-02-15015 February 1989 Internal Conduit Fire Seal Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML17328A8721988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant Unit 2. ML17328A8711988-07-30030 July 1988 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant,Unit 1. ML17334B1091987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:Cook 1 & 2, Final Informal Rept ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20204G4181987-03-31031 March 1987 Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components) Cook Units 1 & 2 ML17334B1101987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification,Cook Units 1 & 2, Informal Rept ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML17324B2461987-02-0606 February 1987 Dcrdr Evaluations,Phases III-V,DC Cook Units 1 & 2, Informal Technical Communication ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML17324B2191986-11-0606 November 1986 Review of App R Procedures for Post-Fire Remote Emergency Shutdown Outside Control Room,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20207A7041986-06-30030 June 1986 Conformance to Reg Guide 1.97,DC Cook Nuclear Plant Units 1 & 2 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML17324A9561986-03-31031 March 1986 Technical Evaluation Rept of 1984 Meteorological Data from Donald C Cook Nuclear Power Plant. ML17321A9321985-10-17017 October 1985 Review of Licensee...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 DC Cook..., Technical Evaluation 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 ML20206F3131985-02-0404 February 1985 Revised Containment Hydrogen Analysis Review of DC Cook, Program Ltr Rept.Related Documentation Encl ML17320A4811983-09-30030 September 1983 DC Cook,Units 1 & 2 Inservice Insp Plan, Technical Evaluation Rept ML20077L8511983-09-0101 September 1983 Control of Heavy Loads (C-10) Indiana & Michigan Electric Co,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20077K9771983-07-27027 July 1983 Revised Masonry Wall Design (B-59),DC Cook Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML17320A5491983-02-24024 February 1983 Draft Control of Heavy Loads (C-10),Donald C Cook Nuclear Power Plant Units 1 & 2, Technical Evaluation Rept ML20076C4091983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D1821982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),DC Cook Nuclear Plant Unit 1, Technical Evaluation Rept,Vols 1 & 2 ML20027D1811982-10-28028 October 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept.Vols I & II ML20069H8611982-10-0808 October 1982 Radiological Effluent Tech Spec Implementation (A-2),DC Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML17319B6161982-09-0303 September 1982 DC Cook Nuclear Plant Units 1 & 2,Seismic Qualification of Auxiliary Feedwater Sys, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20069D0761982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Final Technical Evaluation Rept ML20062E2251982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations.D.C. Cook Case Study.Docket Nos. 50-315 and 50-316.(Indiana and Michigan Electric Company) ML18005A0091982-04-0808 April 1982 to 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. ML17319B3231982-04-0707 April 1982 to 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. ML17319B2871982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20041D7251982-01-31031 January 1982 Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Preliminary Technical Evaluation Rept ML17326A9271981-11-20020 November 1981 Control of Heavy Loads. ML20132C5541981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for DC Cook Nuclear Power Plant Units 1 & 2 ML19347E9081981-04-30030 April 1981 Adequacy of Station Electric Distribution Sys Voltages,Dc Cook Units 1 & 2, Technical Evaluation Rept ML17319A9411981-04-27027 April 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, Technical Evaluation Rept ML19240C0001981-03-31031 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20003C1061981-01-31031 January 1981 Technical Evaluation Rept,Adequacy of Station Electrical Distribution Sys Voltages,Dc Cook Nuclear Station Units 2 & 3, Preliminary Rept ML17331A6131980-11-30030 November 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Dc Cook Units 1 & 2, Revised Technical Evaluation Rept ML17326A7511980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Donald C. Cook Units 1 & 2, Technical Evaluation Rept 1998-03-31
[Table view] |
Text
TECHNICAL EVALUATION REPORT
'.CONFORNNCE:TO GENERIC LETTER 83-28, ITEN 2;2.-'l-,-
- .. '.EgUIPNENT 'CLASSIFICATION FOR ALL OTHER SAFETY-RELATED COHPONENTS
COOK-1 AND -2 Oocket Nos 50-315 and 50-316 R. VanderBeek Pub11shed Apr11 1987 Idaho Nat1onal Eng'1neer1ng Laboratory EG&6 Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the 4
41" U.S. Nuclear Regulatory Coam1ss1on Mash1ngton, D.C. 20555 Under OOE Contract No. OE-AC07-76I001570 FIN No. 06001
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ABSTRACT i 1 Th1s EQM Idaho, Inc., report prov1des a rev)m of. the subilttals'-from'onald C. Cook Nuclear Poser Plant, Un)t Nos. 1 and 2 for,'conformance to Generic Letter 83-28, Item 2.2.1.
Oocket Nos. 50-315 and 50-316 TAC Nos. 53661 and 53662
V FOREWORD
.This',report=5s-supp15ed.as par4 of the program for conformanci to.Gener5c Letter 83-28 "Requ1red Act1ons evaluat1ng'15censee/appl5cant Based on.6erier5c.. Impl5cat1ons of Salem ATMS Events." Th1s work,5s.-be1ng
. conducted.,:,for,-the'U;S.; Nuclear Regulatory Cone5ss1on, Off1ce of Nuclear Reactor Regulat1on, 01v1s1on of PMR L1cens1ng-A, by EG&G Idaho, Inc., NRR and I&E Support Branch.
The U.S. Nuclear Regulatory Conm1ss1on funded th1s work under the author1zat1on B&R No. 20-19-10-11-3, FIN No. 06001.
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'ocket Nos. 50-315 and 50-316 TAC Nos. 53661 and 53662
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. CONTENTS ABSTRACT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 00 ~ ~ ~ ~ ~ 00 0 ~ ~ 0 ~ ~ 000 ~ ~ ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ 0 ~ 0' ~ ~
~ ~ .000"0"o ~ ~ ~ . 'll" F OREWORD ........................................... 1 ~ 1 ~ 00 ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ 0 111 INTRODUCTION .....-..-... - -.- .-. -. . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~
- 2. REVIEM CONTENT AND FORHAT ............-..--.. " ~ 0 ~ ~ ~ ~ 0 ~ 00 ~ ~ ~ ~ 0 ~ ~ ~ ~
- 3. ITEH 2.2.1 PROGRAH ...... - -. - -. - - - - - .. " ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 3.1 3.2 Gu )dellne ................................ ~ ~ ~ ~ ~ 000 ~ ~0 ~ 00 ~ ~ ~ 0 ~ 3 E valuation ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 0 0 ~ ~ 0 ~ ~ 0 ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ \~~0~~~~ 3 3.3 C onclus)on \ ~ 0 ~ ~ ~ ~ ~ ~ 0000 ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ ~ 00 ~ ~ ~ ~ 0 ~ 0 ~ 00 ~ ~ 01 ~ 00 ~ 00 ~ 1 ~ 3 ITEH 2.2.1.1 IDENTIFICATION CRITERIA ......... 0 ~ ~ ~ ~ 0 ~ 0 \~0~~~~~~0~
4.1 Gu )delhne ................................ 1
~ 0 ~ ~ ~ 0 0 ~ ~ ~ 04 ~ ~ ~ ~ 1 ~ ~ 4 4.2 E Va1 ua0 on ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ 1 ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ 0 0 ~ ~ ~ 4 4.3. C OncluS)On 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 0 ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ 0 ~ 4 ITEH 2.2.1.2--INFORHATION HANDLING SYSTEH ..... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
5.1 G u1delhne ................................ ~ ~ ~ ~ 1 ~ ~ \\0 ~ ~ ~ ~ ~ ~ 1 ~ 1 5 5.2 E valuation ............................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ 5 5.3 C onclushon ...............................; ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 1 ~ ~ ~ 0 ~ ~ ~ 5
- 6. 'ITEH 2.2.1.3 USE OF EgUIPHENT CLASSIFICATION L ISTING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ,6 6.1 G u1del)ne ................'................ ~ ~ ~ ~ ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6.2 E valuat)on ............................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ 6 6.3 C onclus1on ............................... ~ ~ ~ ~ 1 ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ 0 0 ~ 6 7- ~ ITEH 2.2.1.4 HANAGEHENT CONTROLS -.----.--.-... ... . ~ ~ ~ -~- ~ ~ ~
0 7.1 Gu1de11ne ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ \~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 7
- 7. 2 E va lua t1on ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 7 7.3 Conclus1on ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ \~~~~0 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 7
- 8. ITEH 2.2.1.5 DESIGN VERIFICATION AND PROCUREHE N T 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
8.1 Gu)delhne .................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ 0000 8 8.2 Evaluat1on ................... ~ ~ ~ ~ ~ 001 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 8 8.3 Conclusion ................... ~ ~ 0 ~ ~ ~ ~ 0 ~ 0 1 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 8
- 9. ITEH 2.2.1.6 "IHPORTANT TO SAFETY'OHPONENTS ............;.....
9..1 Gufdel1ne ..................................................
- 10. CONCLUSION .......... ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 REFERENCES ........................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
'- ONF R C '@ERE IC83~28'<- N 2.2.
UIPHENT CL'ASSI CAT ON .OR.ALL'4THER SAFETY-RELATED COMPONENTS:
COOK'*1 "AND -2
- 1. INTRODUCTION On February 25, 1983; both of the scram c1rcu1t breakers at:Un1t 1 of the Salem Nuclear .Power Plant fa1led to open upon an automat1c reactor tr1p s1gnal from '.the Pea'ctor pre'eat)on'4ystea.-'h1s- 1nc1dent was term1nated:
manually::by 'themperato'r ab'out'30'econds wfter 'the"1n1t1at1on of the automat1c'r1p'<1gnal She fa41ure"'of %he x1'rcu1t breakers i>as determ1ned to be related'-to 'the's't'1ck1rig 'ofthe Under Voltage Cr1p attachment. "Pr1or to th1s 1nc1dent;-on February 22; 1983, at Un1t 1 of 'the Salem Nuclear Po~er Plant, an automat1c tr1p s1gnal was generated based on steam generator'ow-low level dur1ng plant startup. In th1s case, the reactor was tr1pped manually by the operator almost co1nc1dentally w1th the automat1c tr1p.
Follow1ng these inc1dents, on February 28, 1983, the NRC Execut1ve D1rector .for Operat1ons (EDO), d1rected-the NRC staff to 1nvest1gate and report on the gener1c 1mpl1cat1ons of these occurrences at Un1t 1 of the Salem Nuclear Po~er Plant. The results of the staff's 1nqu1ry 1nto the.
gener1c 1mpl1cat1ons of the Salem un1t 1nc1dents are reported 1n NUREG-1000, "Gener1c Impl1cat1ons of the ATMS Events at the Salem Nuclear Power Plant." As a result of th1s 1nvest1gat1on, the Comn1ss1on (NRC) requested (by Gener1c Letter 83-28 dated July 8, 1983 1 ) all 11censees of operat1ng reactors, appl1cants for an operat1ng 11cense, and holders of construct1on perm1ts to respond to the gener1c 1ssues ra1sed by the analyses of these two ASS events.
Th1s report 1s an evaluat1on of the responses subm1tted by Ind1ana and H1ch1gan Electr1c Company, the 11censee for the Donald C. Cook Nuclear Po~er Plant, Un1t Nos. 1 and 2 for Item 2.2.1 of Gener1c Letter 83-28. The documents rev1ewed as a part of th1s evaluat1on are 11sted 1n the references at the end of th1s report.
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2p'f'REVIEW 'CONTENTS" AND'jORNJj
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V ~ p Item 2.2.l of Generic Letter 83-28 requests the licensee or applicant to submit, for the staff rev1ew, a descr1pt1on of their programs for safety-related equipment class1f1cat1on 1ncluding support1ng 1nformat1on, 1n cons1derable detail, as 1nd1cated 1n the guidel1ne sect1on for each sub-item within this report.
As-previously .ind1cated, each of the six sub-items of. -Stem 2;-2;l: is evaluated in a separate. section in which: the guideline -is:,presented; =.yn evaluation -of .the. licensee'slapplicant':s response 1s. made; and.conclusions about the programs of the.l4censee or applicant for. safety-.relaied. " .-.
equipment. class1f1cation are dram;.
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" O':ITN"2 2;3='. PROGRAM; .
- 3. l Guideline L1censee and applicants should conf1rm that an equipment classification program 1s in place which will prov1de assurance that all safety-related components are des1gnated as safety-related on plant documentation such as procedures, system descr1ptions, test and ma1ntenance 1nstructions and in 1nformat1on handling systems so that personnel performing act1vities that affect such safety-related components are aware that they are work1ng on safety-related components and are gu1ded by procedures and constraints. Licensee and.applicant: 'afety-related responses which:address the:features of this program are evaluated.in the remainder of th1s report.
3.2 Evaluation The l1censee for the Donald C. Cook Nuclear Power Plant, Unit Nos. 1 and 2, responded.to,,these:requirements w1th submittals -dated 4
November 4, 1983, 2 March 30. 1984, 3 and December 19, 1986. These subm1ttals include information that describes their existing safety-related equipment classification program. In the review of the licensee's response to th1s item, it was assumed that the information and documentat1on
.supporting this program is ava1lable for audit upon request.
3.3 Conclusion The staff concludes that all the bas1c requirements of the equipment classificat1on program are in place and address the concerns of the 1tems of Item 2.2.1 of Gener1c Letter 83-28.
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~ -4. ITN 2;2!'i';O'-".-'XOENXFICATXON CRITERIA 4.1,6ui del1ne The applicant or licensee should confirm that their program used for equipment class1ftcation includes cr1teria used for identify1ng components as safety-related.-.
4.2- 'Evaluation The *licensee's response states:Chat the cr1teria for determining safety-related:structures', systems, and components are contained in the present corporate procedures. The criteria ~ere 1ncluded 1n the response and conform v1th the definit1on vith1n Item 2.2.l of Generic Letter 83-28.
- 4. 3 Conc 1 us 1 on We find that the cr1ter1a used in the identificat1on of safety-related components meets the requirements of Item 2.2.l.l and are acceptable.
- ~~ i--" 5. -'. XTNi2 2.1.2 'XNFORNATTDN HANDLING SYSTEM~
5.1 '.Gu1del1ne The 11censee or appl1cant should conf1rm that the program for equ1pment classificat1on 1ncludes an informat1on handl1ng system that 1s used to ident1fy safety-related;components. The response should confirm that:this information hapd)4ng;system includes- a l1st:.of saf ety-related equipment and that".procedures.exist- which,. govern:1ts development and validation.
5.2 Evaluation c ~
The licensee's response states that safety-related components (w1th known exceptions) are entered in a computer1zed list known as the N-L1st.
Structural items and p1ping are entered as a s1ngle line 1tem. Electr1cal 1tems such as relays, switches, conduit, fittings, and trays also are covered by single line 1tems.
- The licensee.has confirmed that,a new classification program has been 1mplemented. Jhis new program consists of a new computerized component class1ficat1on record which lists-all:.plant components, their safety class1fication and the1r procurement and gA requ1rements. Cross-references ta draw1ngs and relevant plant and corporate procedures w1ll ensure that the safety role of a component 1s kept 1n focus whenever a component is taken out of service, bought, ma1ntained, replaced or returned to serv1ce.
The fob control classification w1ll rely on the record.
- 5. 3 Conc 1 us 1 on The licensee's response for th1s item is considered to be complete and is acceptable.
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- 6. 'JTBl 2l2 1S-":4SE OF-:KgUIPNENT CLASSIFICAHON t/STING-';1 Guideline The licensee's or applicant's description should conf1rm that the1r program for equ1pment classification 1ncludes cr1ter1a and procedures governing the use of the equ1pment classification information'.handling, system-.to determ1ne that an activity 'is-'safety-related and'what procedureS'or maintenance, surveillance, parts replacement'<and other-activit1es.':
def1ned in the introduction to 10 CFR 50, Appendix B, apply to.
safety-related components.
6.2 Evaluat1on The licensee's response 1ndicates that respons1ble stat1on personnel use the N-List and corporate procedures to des1gnate the safety class1f1cation of the equ1pment and the procedures required to perform the work. The safety classification and procedures are indicated on the Job Order form used for all repa1r and modification work performed at the plant; If any'one within the'plant is unsure of" the class1f1cation of a component,-he 4s required to check.with'he responsible American Electr1c Power Serv1ce. Company (AEPSC) cognizant engineer.
- 6. 3 Conc lus 1 on The licensee's response for this item is considered to be complete and is acceptable.
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',7','.1TEH 2.2.1.4 NNAGEHENT CONTROLS H
7.1 Guideline The appl1cant or 11censee should confirm that the management controls used to ver1fy that the procedures for preparat1on, val1dat1on and routine utilizat1on of the information handling system have been followed.
e'.2 Evaluat1on The licensee's response states that the equality Assurance Department I
performs audits of act1vit1es covered by the plant instruct1ons and procedures and notifies appropriate plant management of any def1ciencies noted. Thus, the audit program provides add1t1onal ver1fication of the rout1ne ut1lization of the 1nformat1on handling system.
7.3 Conclus ion The licensee's response to this item 1s cons1dered to be complete and is acceptable.
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ITN 2.2;1-5 C
8- OESIGN VERIFICATION'AND PROCUREHEHT
- 8. l Gu1del1ne The appl1cant's or l1censee's subm1ttal should document that past usage demonstrates that appropr1ate des1gn ver1f1cat1on and qual1f1cat1on test1ng 1s spec1f1ed for the procurement of safety-related components and parts; The spec)f1catlons~should.1nclude qual1f1cat1on test1ng for expected safety serv1ce cond1t1ons and prov1de support for the appl1cant',s/1)censee! s rece1pt of test1ng,documentat1on to support the l1m1ts of 11fe recoaeended by the suppl1er. If such documentat1on 1s not I ~
avaflable, conf)rmat1on that the present program meets these requ1rements should be prov1ded.
8.2 f valuat1on The 11censee's response states that the current spec1f1cat1ons used to procure nm or replacement components 1dent1fy normal and acc1dent serv1ce cond1t1ons or reference appl1cable codes. gual1f1cat1on test1ng and performance.evaluat1on 1s requ1red for harsh env1ronments and test reports of th1s qual1f1cat1on test1ng are requ1red to meet the cond1t1ons of the spec1f 1ca t1ons.
Pr1or to future use for procurement, each spec1f1cat1on sub]ect to the requ1rements of 10 CFR 50.49 w1ll be rev1sed to 1nclude the requ1rements that the vendor establ1sh serv1ce l1fe by test or performance evaluat1on and requ1re the vendor to supply documentat1on 1n support of the serv1ce 11fe qual1f1cat1on.
8.3 Conc 1us1on The 11censee's response for th1s 1tem 1s cons1dered to be complete and 1s acceptable.
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ITEN 2.2 1- 6 '"IHPORTAHT, TO SAFETY'ONPONEIPS 9; 1 Gui del ine Generic Letter 83-28 states that the l1censee's or appl1cant's equipment classification program should include (in addit1on to the safety-related components) a broader class of components designated as "Important to Safety." However,.since the gener1c letter does not requ1re the licensee or applicant to t'urnish this 1nformation as part of their response, revim of this item vill not be performed.
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- 10. CDHCLUSION Sased on our revi~ of the licensee's response to the spec1f1c requirements of Item 2.2.1, ve find that the information provided by the licensee to resolve the concerns of Item 2.2.1 meet the requirements of Generic Letter 83-28 and is acceptable. Item 2,2.1.6 was not rev1eved as noted in Section 9;l.
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4 E ll. REFERENCES
- l. NRC Letter, D. 6. Eisenhut to all Licensees of Operating Reactors, App11cants for Operat1ng License, and Holders of Construct1on Permits, "Required Actions Based on Generic Impl1cat1ons of Salem ASS Events (Generic Letter 83-28), July 8, 1983.
- 2. Indiana and H1chigan Electric Company letter, H. P. Alexich to D. 6. Eisenhut, NRC; November 4, 1983, AEP:NRC:0838A.
3; Ind1ana and Hichigan Electric Company letter, H. P. Alexich to D. 6. Eisenhut, NRC, Harch 30, 1984, AEP:NRC:0838B.
- 4. Indiana and H1chigan Electric Company letter, H. P. Alexich to H. R. Denton, NRC, December 19, 1986, AEP:NRC:0838M.
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.I-- * -.. . CI,Y . - ,=. ", -" 'I,GGUCLIANOOOULATONTCOGNATION I. httOht IHNjNthTAHOMTST TIOC~ V&Nao H~
Sttt,Stot - ',; '= BIBLIOGRAPHIC:DATASHEET EGG-kA-7329 St t INSthUCTIONG ON THt IISVthtt .. ' ~ ~
S. TITLS AHO SUSTITLt 1 LSAVt SLAING CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.1 E(UIPMENT CLASSIFICATION FOR ALL OTHER SAFETY-RELATED COMPONENTS: COOK-1 AND -2 4. OATS httOht COLMLtttO MONtH YSAN
- l. AUTHOAISI April 1987 R. VanderBeek t, OATS httOh t ISSUGO April 1987 T.tthtOHMIHOONQAHISATIONNAMSAHOMAILINOAOOhtSSI eWA CO%I L GNO3SCTITASIUWIÃNCUIHT NUMSth EGSG Idaho, Inc.
P. 0. Box 1625 IN Idaho Falls. ID 83415 D6001 I IL SKNCCOAIHO ONQANISATION NAMt ANO MAILINO AOOhtSS Division of PWR Lfcensfng - A
(~ ZM O94al 11e, TY1t IÃ httOht Offfce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission IL tCHIOO COVthtO IlaAeeoeAIHI Washington, 'DC 20555 It SUtf LSMGNTANYHOTSS
- 13. ASSTNACT QOG aw& or Heel This EGI* Idaho, Inc., report provides a review of the submittal from the Indiana and Mfchfgan Electric Company regarding conformance to Generic Letter 83-28, Item 2.2. 1 for the Donald C. Cook, Unit Nos. 1 and 2.
I~ OOCUMtHT ANALYSIS ~ HSYWOIIOSIOSSCNPTOIIS IS AYAILASILITY STATtMGNT Unlimited Distribution IS SGCUAITY CLASSIAICATION
- e. IOSNTI>lthaOPCN4HOGOTSNMS Unclassified ITIINneWd Unclassified
- 17. HUMSth
'l Distrib~- "'on:
Docket. ~es w/o Encl~
P. Kreutzer D. Wigginton PD III-3 1/2 August 7, 1987 DOCKET NO(S) . 50"315/316 H'r. John Dolan, Vice President Inaliana and Michigan Electric Company c/o American Electric Pamr Service Corporation 1 Riverside Plaza Columbus, Ohio d+3216 SUB JECT: DGNALf) C. COOK NUCLEAR PLAHXS The following documents concerning our review of the subject facility are transmitted for your information.
Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding of No Significant Impact, dated Q Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating Li cense, dated Bgis tH d C id ti,d gg Bi-Weekly Notice; Applications and Amendments d J129 to Operating Licenses Involving No 8g f33 Exemption, dated Construction Permit No. CPPR- , Amendment No. dated
+ Facility Operating License No. , Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated Office of Nuclear Reactor Regulation
Enclosures:
As stated cc: See next page 0FFiCEQ
'URNAggEJ ~~
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NRC FORM 318110/801 NRCM 0240 OFFICIAL RECORD COPY
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Distrib 'on:
Docket es P,';eQtzer D. Wigginton PD III-3 r/f July 27, 1987 DOC~ET NO(S). 50-315/316 Mr.. John Dolan, Vice President Indiana and? hchigan Electric Company
@'o American Electric Pamr Service Corporation 1 Riverside Plaza Columbus, Onio 43216 SUB JECT: II~T C. COCK EJCLEIt R PLANXS The following documents concerning our review of the subject facility are transmitted for your information.
Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding, of No Significant Impact, dated Q Notice of Consideration of Issuance of Facility Operating License or Amendment to Faci 1 i ty Operating Li cense, dated Q Bi-Meekly Notice; Applications and Amendments to 0 crating Licenses Involving No Significant Hazards Considerations, dated July, 8rsee page(s) 3 Exemption, dated Construction Permit No. CPPR- , Amendment No. dated Facility Operating License No. , Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated Office of Nuclear Reactor Regulation
Enclosures:
As stated cc: See next page OFFICE/
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NRC FORM 318 (IOIBOI NRCM 0240 OFFICIAL RECORD COPY
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