Similar Documents at Cook |
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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
BROOKHAVEN NATIONALLABORATORY TECHNICAL EVALUATION REPORTFORUSNUCLEARREGULATORY COMMISSION OFFICEOFNUCLEARREACTORREGULATION
'PWRDIVISIONOFLICENSING
-GROUPAPLANTSYSTEMSBRANCHREVIEWOFAPPENDIXRPROCEDURES FORPOST-PIRE REMOTEEMERGENCY SHUTDOWNOUTSIDETHECONTROLROOMLICENSEE:
Indiana&MichiganElectricCompanyFACILITY:
D.C.CookNuclearPlant,Units1&2REVELCONDUCTED:
October27-29'986NRCREVIEWERS:
A.Singh,NRRD.Wigginton, NRRBNLTECHNICAL SPECIALIST:
AnthyFresco(MechacalSystems)/I0ateBROOKHAVEN NATIONALIABORATOR" lpgQIASSOCIATED UNIVERSITIES, INC.CILII8702030539 870128PDRADOCK05000315FPDR
~~-ii-CONTENTSSectionPage1GENERALSUMMARY~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~2~PERSONSCONTACTED
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ee23~DOCUMENTS REVIEWEDe
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3.13~23.3NRCCorrcapondence.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~LicenseeDocuments.
~~.~~~~~~..~~.~~~~~~~~~~..~~~.~.Procedures.
~~~~~~~~~~~~~~~~~~~~~.~~~~~~~.~~..~~~...~~~~~~~~~~~~~e~~~~~~~3334~POSTFIRESAFESHUTDOWNe~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~4.1SystemsRequiredforSafeShutdown.
~~~~~~~~.~~~~~~~4.2AreasRequiring Alternative Shutdown.
~~~~~~~~~~~~~~~~~~~~~~~~~~~~46~PRCDURFS~~~~~~~~~~~~~~~~~~~~~~~~~e~~~~~~~~~~~~~~~~~~~~~~~~~~~5.1Procedure forUnit1RemoteEmergency Shutdown.
~~~~5.2RepairProcedures RequiredtoAchieveColdShutdown~~~~~~~~~~~~~~710ee 1~GENERALSUMMARYDuringthetimeperiodofOctober27-29,1986,ateamofNRCpersonnel fromtheOfficeofNuclearReactorRegulation, PlantSystemsBranchandtheDivisionofLicensing personnel andA.FrescoofBNLconducted aspecialreviewandwalk-downoftheemergency remoteshutdownandassociated repairprocedures asre-quiredbytheNovember22,1983SafetyEvaluation ReportfortheAlternate Shut-downCapability attheD.C.CookNuclearPowerPlant,Units162.TheteammemberswereassistedinthewalkdownbytheSeniorResidentInspector.
Theresultsofthisreviewwillbetransmitted toRegionIIIHeadquarters.
ThereviewwasnotintendedtoaddressotherAppendixRissues,suchasseparation ofcomponents requiredforsafeshutdown, associated
- circuits, orfireprotection features.
Ingeneral,thelicensee's procedures werefoundtobeworkablebutcertainstepsrequirereorganization,
- revision, oramplification toprovideadditional guidancetotheoperators.
Apotentially seriousproblemwasidentified tothelicenseeinapost-review conference callonNovember5,1986concerning Attach-mentNos.3and7whichrelatetolocalmanualde-energization ofbreakersintheSwitchGearRoomstopreventspuriousoperation ofpumpsandvalves.IfafireoccurredintheSwitchGearRoom,thealternative localoperations werenot'escribed intheprocedure, andupondiscussion withthelicensee, appearedtoinvolvepneumatic orelectrical jumpering duringHotStandbyorHotShutdownconditions.
SeeSection5.1.1(d)forfurtherdiscussion.
Possibleproblemswerealsoidentified withemergency lighting.
Thearrangement andusageof.thecross-ties'nd oppositeunitequipment toachievesafeshutdownintheaffecteduni(requiredclarification andanoverallanalysistojustifytheactions'aken in'"theprocedures toachievetheperfor-mancegoalsofAppendixR,e.g.,isolation ofletdownflow,usagerequirements forpressurizer PORVsandheaters,etc.wasnotavailable duringthereview.Itwasalsorecommended thatthelicenseeprovideachartindicating theassignment ofthepersonnel requiredtoimplement theprocedure.
Thelicenseewasadvisedthatifanylocaloperatoractionsarerequiredtobeperformed intheyardarea,e.g.,verification thattheflowpathisavailable andthereisasufficient highpressurenitrogensupplyforsteamgenerator power-operated reliefvalveoperation, that8-hourbatterypoweredemergency lightingisrequiredfortheaccesspathorelseanexemption requestshouldbefiled.Finally,theteamprovidedguidancetothelicenseeontheconductofafullscopeAppendixRaudit.
2.PERSONSCONTACTED NAMEW.G.Smith,Jr.J.E.Rutkowski PEJacquesK.R.BakerM.OnkenR.Heathcote W.NelsonD.RumpfH.RumserG.TollasJ.St.AmandJ.ConradJ.Stubblefield C.MilesJ.Feinstein A.AuvilR.L.ShobergW.G.SotosE.BrownG.WeberB.Jorgensen TITLEPlantManagerAss'tPlantMgr.QualityControl/FireProtection Coord.Operations Operations Operations Operations Operations Operations Operations Operations Operations TrainingI&CPlanningMgr.-NuclearSafetyLicensing NS&L...Asst.SectionMgr.-I&CI&CElectrical EngineerSectionManagerSeniorResidentInspect.COMPANYIndiana&MichiganElectricCo.I&MI&MI&MI&MI&MI&MI&MI&MI&MI&MI&MI&MI&MAmericanElectricPowerServiceCorp.AEPSCAEPSCAEPSCAEPSCImpellCorp.USNRC 3~DOClJMENTS REVIEWED3.1NRCCorresondence1.LettertoJ.E.Dolan,IndianaandMichiganElectricCompany(1&M)fromMr.C.E.Norelius, NRCRegionIII,datedSeptember 22,1982transmit-tingtheresultsofAppendixRauditconducted April12-16,May14,June10,1982atD.C.Cook.2.LettertoMr.J.E.Dolan,I&M,fromMr.S.A.Varga,Operating ReactorsBranchNo.1,DivisionofLicensing, datedNovember22,1983transmit-tingtheSafetyEvaluation ReportonAlternative ShutdownCapability atD.C.Cook.3.2LicenseeDocuments 1.Indiana&MichiganElectricCompany,"NuclearRegulatory Commission-AppendixRAudit-October27,1986-Alternate ShutdownCapability-DonaldC.CookNuclearPlant-Bridgman, Michigan."
3.3Procedures ZDNo.TitleRev.Effective Datel.**12WHP4023.100.001
=Unit1'Emergency RemoteShutdown02.**1MHP2140.082.001 Maintenance Procedure for-1Repowering an"kHRPump6/10/8610/23/863.**1MHP2140
~082.003Maintenance Procedure forRepowering Pressurizer BackupHeaters10/23/864~**1MHP2140.
082.005Maintenance Procedure forRepowering Containment Valves10/23/866.**1THP6030IMP.305AppendixRPost-Fire Repowering 1ofIn-Containment Valves5.**1THP6030IMP.304Pressurizer PORVCableRepair18/14/8610/23/86 4.POSTFIRESAFESHUTDOWN4.1SstemsRuiredforSafeShutdownThelicenseeprovidedabriefpresentation ofthesystemsrequiredforsafeshutdown.
Theteamreviewedthiswithinthetimeavailable asbackground infor-mation5ustifying theactionstobetakenintheprocedures.
4.1.1Reactivity ControlInitialreactivity controlisprovidedbytrippingthereactorcontrolrodsusingthescramswitchesinthemaincontrolroom.Thereactorcanalsobescrammedbytrippingtheturbin'eatthefrontstandardandalsoatotherunspecified locations'dditional negativereactivity toachievetherequiredborationmarginis'rovided bytheboratedwaterintheRefueling WaterStorageTankutilizing theoppositeunit'schargingpumpsdischarging intothereactorcoolantpumpsealinfection lines.Thelicenseewasadvisedtohaveavailable, forthefullscopeAppendixRaudit,ananalysisshowingthattheRWSTalonedoesprovidesufficient negativereactivity capability toachieveandmaintaincoldshutdown.
4.1.2ReactorCoolantMakeup(Inventory andPressureControl)Inventory controlofthereactorcoolantsystemisprovidedbythereactorcoolantpumpsealinfection pines.andchargingsystem.Foralternative shutdownoutsideoftheaffectedurii't.'.s controlroom,sealinfection isprovidedbytheoppositeunit'scharging'pump'viaadischarge headerunitcrosstietoRCPseals.Chargingthroughthenormalcharginglinecanbeprovidedbytheoppo-siteunit'sBoronInfection flowpath.Thesystemalignments aresummarized inthelicensee's introductory presentation onalternate shutdowncapability (Ref.3.2-1)asfollows:BoratedCoolingWaterSource:OppositeUnit'sRWSTorAffectedUnit'sRWST(viaunitcrosstie)
OppositeUnit'sCVCSAuxiliary Systems:OppositeUnit'sEmergency PowerSystemOppositeUnit'sHVACOppositeUnit'sCCWControl:NormalvalveandpumpcontrolonoppositeunitLocalmanualcontrolofvalvesonaffectedunitInstrumentation:
LocalshutdownpanelpoweredfromoppositeunitOtherlocalself-powered indict6rs Pressurizer leveliscontrolled bysupplying sufficient volumeflowtosupporta25'F/hour cooldownrate.Thelicensee's positiononpressurizer pressureanduseofthepressurizer PORVsduringhotstandbyandhotshutdownisthattheheatlossesfromthepressurizer aresuchthatpressurewillberehucedwithina72hourperiodtoallowuseoftheresidualheatremoval(RHR)systemwithoutuseofthepressurizer PORVsandthatthePORVsarenotrequiredtomaintainhotshutdown.
Thelicenseedidnotprovidetheanalysisto)ustifythisbutwasadvisedthattheanalysisshouldbeavailable forthefullscopeAppendixRaudit.ThecablestothePORVscanberepairedtoallowpressurecontrolduringthetransition tocoldshutdown.
4.1.3DecayHeatRemovalForlossofoffsitepowerconditions, naturalcirculation isestablished bydumpingsteamfrom'atleasttwoofthefoursteamgenerators viatheatmospheric steamgenerator PORVswithmakeuptothesteamgenerators providedbytheAuxil-iaryFeedwater SystemfromtheCondensate StorageTanktosupporta25'F/hour cooldownrate.Ref.3.2-1describes thesystemalignments asfollows:Auxiliary Feedwater isprovidedbyeithertheaffectedUnit'sturbine-driven pumpviathenormalflowpathoreitheroftheoppositeUnit'smotor-driven pumpsviaadischarge headerunitcrosstietothenormalflowpath.CoolingWaterSource:Auxiliary Systems:OppositeUnit'sCST.Affected Unit'sCSTLakeMichiganviaoppositeUnit'sessential service,waterOppositeUnit'sEmergency PowerSystem(MDAFPuse)OppositeUnit'sHVAC(appliesonlytooneoftheoppositeUnit'sMDAFP)Control:LocalcontrolpanelforTDAFPNormalvalveandpumpcontrolforoppositeUnit'sMDAFPsLocalmanualcontrolofvalvesonaffectedunitInstrumentation:
LocalTDAFPPanel(TurbineSpeed)Thesteamgenerator PORVsarepoweredfromthealternate sourcewhichisthebackupnitrogensupplylocatedintheyardarea.Controlisateitherlocalcontrolpanelsorasabackupbylocalmanualoperation ofthevalves'andwheels.
Instrumentation isatalocalshutdownpanelpoweredfromtheoppositeunitandatotherlocalselfpoweredindicators fortheN2supply.4.1.4SupportSystemsandProcessMonitoring Instrumentation Thefront-line systemsaresupported bythesystemsdescribed in4.1.1to4.1.3whileprocessmonitoring isprovidedatlocalcontrolpanelswithintheplant.Neitheroftheseaspectswerereviewedinanydetailduetotimecon-straints.
4.1.5ColdShutdownTheRHRsystemisusedtoachieveandmaintaincoldshutdown.
RHRispro-videdbyeithertrainofnormalRHRpoweredfromtheoppositeuniE.Ref.3.2-1describes thesystem"alignments asfollows:Auxiliary Systems:OppositeUnit'sEmergency PowerSystemOppositeUnit'sESW(viaunitcrosstie)
OppositeUnit'sCCW(viaunitcrosstie)
Control:Temporary RHRpumpcontrolfromoppositeunit,NormalESWandCCWpumpandvalvecontrolfromop-positeunitLocalmanualcontrolofRHR,ESW,andCCWvalvesonaffectedunitInstrumentation.
RHRpumploadfromtemporary RHRpumpcontrolstationinoppositeUnit'scontrolroom(Valveoperation coordinated withindications providedatlocalshut-downpanelatanotherlocation)
Thelicenseehasdeveloped repairprocedures forrepowering anRHRpump,pres-surizerbackupheaters,pressurizer PORVcables,andin-containment valves'nly repairoftheRHRpumpsandpressurizer heaterswasdiscussed intheSafetyEvaluation Report(Ref.3'1-.2)~NomentionismadeintheSERconcerning theuseofthepressurizer PORVs.;ICwassuggested tothelicenseethattheirusebe..clarified forthefull-scope'.audit asmentioned in4.1.2above.I4.2AreasRuiriAlternative ShutdownTherearefourareasineachunitwhichrequireimplementation oftheremoteshutdownprocedure intheeventofafire:~ControlRoomCableVaultAuxiliary CableVault~SwitchGearRoom~ControlRoomSincethereisa3-hourratedfirebarrierbetweeneachunit'scontrolroomandthereissignificant crosstiecapability betweensystemsrequiredforsafeshutdown, theShiftSupervisor directsoperations fromtheoppositeunit'scon-trolroom.Thehotshutdownpanelslocatedwithineachcontrolroomwerenotdesignedtomeetthedemandsofafireaspostulated byAppendixR.
5~PROCEDURES Theprocedure reviewedindetailandwalkedthoughduringthisplantvisitwas:**12-OHP4023100001,"Unit1Emergency RemoteShutdown,"
Rev0,6/10/86Thisprocedure isstructured withamainbodyandeightattachments'ttachment No.1relatestotheestablishment ofthechargingheadercrosstiefromtheop-positeunitwhileNo.2providesfortheinitiation ofAuxiliary Feedwater flow.ttachment No.3concernsisolation oftheReactorCoolantSstemandthenerators gorsandNo.4pertainstocontrolofthesteamgenerator PORVs~Attach-mentNos~5&6describethestepstoprovideRHRcoolingusingUnit2Essential ServiceWaterandComponent CoolingWaterPumper'ttachment No.7instructs thee-energization of'quipment fromtheswitchgearroomstopreventspuriousactuations andNo.8providesfortherestoration ofoffsitepower.Therepairprocedures werealsoreviewedbutinlessdetail.5.1Procedure forUnit1RemoteEmerencShutdownThelicenseepersonnel explained, bymeansofahand-drawn chart,thereas-signmentofthenormalplantoperating stafftoformthefirebrigadeandtoimplement theprocedure.
Theresultswasthatfouroperations personnel arerequiredtoimplement theprocedure, threefromtheaffectedunitandonefromteunaffected unit.Thelicenseewasadvisedtoprovideasimplified staffingassignment chart'for thefull;+cope AppendixRaudit.Commentsgenerated duringthereviewandwalkthrough willbeprovidedseparatelybelow:5.1.1Reviewa)'ainPortionStep4.2.2-Itwasrecommended thatthisstep,whichdirectstheoperatortolocallytripthereactor,includethelocations ofotherftriioermeansorppngthereactoroutsidethecontrolroom.Theseotherloca-tionsshouldbereviewedtodetermine theirsuitability undertheconditions ofafirerequiring controlroomevacuation.
Itwasalsorecommended thatthestepincludeastatement instructing theoperatortoverifythecontrolrodpositions, ifatallpossible, beforeevacuating thecontrolroom.Step4.2-3-Thisstepdirectsthepersonnel torapidlyaccomplish certainoftheattachments withprioritybeinggiventoAttachment Nos.1andine2.SinceAttachment No.1concernsestablishment fRCP1RCSn)ectionflowtocoolthesealsandalsotoprovidemakeutththetimeavailable toperformtheseactionsistypically atmaeupoeleastonehourunlessapressurizerPORVhasspuribusly opened.Therearetypically only30minutesavailable toprovideAFWflowtothesteamgenerators beforeboildrysothatperformance ofAttachment No.2isusuallymoretimelimited.Itwasrecommended thatthisbeindicated intheprocedure.
NotepriortoStep5.3.5Thisnotestatesthatpressurizer PORVuseislimitedbytheairbottle(N2)backupcapability andthatthePressurizer ReliefTank(PRT)hasnoquenchordraincapability andhasbeen'receiving RCPsealleakoff.Further,ittellstheoperatorto"Planitcare-fully."Upondiscussion withlicenseepersonnel, itwasstatedthatthereisadequateN2supplytoprovideover70operations ofthePORVsandthatrupture.ofthePRTrupturedisksisnotofcon-cernexceptthatextensive cleanupofthecontainment wouldberequired.
Again,itwasrecommended tothelicenseethatananaly-sis5ustifying theN2supply,thenumberofPORVoperations requir-edtodepressurize, theassumptions regarding therupturedisk,andtheoverallusageofthePORVsbeavailable forthefullscopeAppendixRaudit.ThelicenseewasalsoadvisedthatiflocaloperatoractionsarerequiredintheyardareatoassureadequateN2supplytothePORVsthat8-houremergency lightsbeprovidedfortheaccesspathoranexemption requestshouldbefiled.Thelicenseeagreedwiththeteam'sconcernovertheuseoftheterm"Planitcarefully",
andindicated thattheprocedure wouldbere-visedaccordingly toprovideclearerinstructions totheoperator.
b)Attachment No.1Therewerenosignificant commentsduringthereviewprocess'~c)Attachment No.2\Caution-Thecautionstates"Sincecorecoolingmodeisnaturalcircula-tion,donotoverfeedoroversteam."Theteamexpressedtheconcernthatthisappearstoprovidearigidmindsettotheoperators thattheprocedure isonlyapplicable forlossofuff-sitepower.Thereisaseparateprocedure forremoteshutdownintheeventofafirewithoffsitepoweravailable.
However,thereisnodirectprovision fortheoperatortoreturntothatprocedure intheeventthatoffsitepowerisrestoredwithoutonsiteoperatoractions~Thelicenseeagreedtorevisethepro-ceduretoaddressthisconcern.Steps2.6,3-6&4'-Thesestepsinstructtheoperators tomanuallyoperatethehandwheels ontheAFWpumpdischarge linestoestablish andmaintainlevelinthesteamgenerators withoutindicating aminimumrecommended level.Theteamrecommended thatthelicenseerevisetheprocedure torecommend maintaining levelatapointproviding sufficient con-tingency.
d)Attachment Nos.3and7Therewerenosignificant commentsontheseattachments duringthereviewbuttheywerethesubjectofaconference callbetweenthereviewteamandthelicenseeonNovember5,1986.Specifically, No.3concernselectrical isolation oftheReactorCoolantSystemandtheSteamGenerators topreventspurious Oeoperation andNo.7electrical isolation ofpumpsandvalvesfromtheSwitchGearRooms.BNLexpressed theconcernthattheactionsdescribed intheSwitchGearRooms,suchasmanuallytrippingthebreakers, couldnotbgperformed ifthepostulated fireoccurredintheSwitchGearRooms~Thelicensee's responsewasthatthesituation ofafireintheSwitchGearRoomiscoveredbyanotherprocedure forremoteemergency shutdownwhenoffsitepowerisavailable.
Thisalternate procedure wasnotcrossreferenced norwasitreviewedbytheteam.Uponfurtherdiscussion,'t appearedthatitcallsfor3umpering ofvalvesand/orbreakersduringthehotstandbyorhotshutdownconditions topreventspuriousoperations.
Thelicenseewasstronglyadvisedthatanyjumpering isconsidered arepairandassuchisnotallowedduringhotstandbyorhotshut-downconditions
~Also,itcannotbestatedthatthetwoprocedures areinpar-allelsincetheprocedure underreview,i.e.,forthecaseoflossofoffsitepower,doesnotcoverafireintheSwitchGearRooms,whichrequiresevacuation oftheaffectedu'nitscontrolroom.Adequateandpropercrossreferencing, whichtheteamfeltisessential, didnotexistinthereviewedprocedure.
Thelicenseeagreedtoreviewtheprocedural responseandmethodology accordingly inpreparation forafullscopeAppendixRaudit.e)Attachment Nos~4,5,6,and8Therewerenosignificant commentsduringthereviewphaseexceptforanyactionstobetakenintheyardareatoassureN2supplyandtheprovision ofemergency
- lighting, aspreviously notedin(a)above(pertaining toAttachment No.4)~5.1~2Walkdowna)MainPortionSomeoftheteammembersfoundthequalityoftheoperators communicatioris skillstobepoorattimes.Itshouldalsobenotedthathand-held radiosaretheonlycommunications meansavailable underlossofoffsitepower.Inaddi-tion,thereareonlytwochannelsavailable, F-1andF-2,andonlyoneofthosechannels, F-l,isbackedupbyarepeaterstation.TherepeaterstationislocatedintheUnit2Switchgear RoomsothatintheeventofafireinthatSwitchGearRoom,onlytheF-2channelisavailable, whichthelicenseeconcededhassomedifficult areasbetweenwhichthecommunication ispoorornon-.existent.
Therewerenoothersignificant commentsnotedduringthewalkdown.
b)Attachment No.1Step1.1-'hereappearedtobeinadequate emergency lightingfortheoperatortocheckclosedvalves1-CS-536and1-CS-534.
Step2.1-Thesequenceofactionstode-energize thebreakersagMCC1-AZV-Aand1-AM-Dappearedtobereversed.
Thatis,itwasmoretimeeffi-cientfortheoperatortoperformtheactionsrequiredatMCC1-AM-DbeforeMCC1-AZV-Aparticularly sincetheyar'eatdifferent eleva-tions~ Step2.2-AsimilarproblemsexistsinStep2.2inthatitiseasiertoisolatecontrolairto1-RV-251, 1-RV-252, and1-RV-255neartheBatchTankbeforeenteringtheBoronInjection Tank(BIT)Roomtoverify1-IMO-255 and1-IMO-256 closedsothatitappearstheorderofthestepsshouldbereversed.
Emergency lightingattheBatchTank"areawasnotavailable toperformtherequiredfunctions whiletheemergency lightingintheBITRoomwasinadequate beingononlyonesideoftheBIT,whichisaverylargeandtalltank,whileactionsarerequiredonbothsidesofthetank.Step2.3-Sinceentry'intotheBITRoom,asrequiredbyStep2',andintotheBITOutletValveRoom,asrequiredbyStep2.3,necessitates theuseofanti-contamination
- clothing, itismuchlesstimeconsuming iftheprocedure includedanotedirecting theoperatortogatheranextrasetofanti-C'swhenperforming Step2.2inpreparation forStep2.3.Insummary,allowingfortheinherentdifficulties ofperforming thisattachment withaninspector taggingalong,itappearsthattheimplementation isexces-sivelylongandcanbe'streamlined.
c)Attachment No.2Thisattachment, whichprovidesforinitiation ofAuxiliary Feedwater flow,waswalkedthroughbytheSeniorResidentInspector whosecommentsfollow:pGeneralComments~~'$1.Thelicenseeshouldwalkthrougheachpersonon.eachintendedfunction.
2.Thelicenseeshouldassureindependence ofactivities byvariousagents,i.e.,whichstepsrequirepriorcommunication andauthoriza-tion.Step2.0-Intheeventthattheaffectedunitsturbine-driven AFWpump,(TDAFP)shouldfailtostartorfailtorunafterstarting, itrequiredap-proximately 10minutestosimulatetheinitiation ofAFMflowusingtheoppositeunit'smotor-driven AFVpumps.Thelicenseeshoulddetermine ifthistimeintervalcanbereduced.Steps2.6,3.6,and4.5-Theprocedure shouldspecifyaquantitative throttlepositionfortheoperatortolocallymanuallyoperatethehandwheels oftheAFWpumpdischarge controlvalvestomaintainsteamgenerator levels.(Thiscommentissimilartothecommentbytheteamonthisstepnotedduringthereviewprocess.)
5.2ReairProcedures ReuiredtoAchieveColdShutdownTheprocedures listedinSection3.3,Nos.2through6werebrieflyreview-edandappearedtobesubstantially detailedtofacilitate implementation.
No walkthrough wasconducted butacheckwasmadeofwhetherthetoolsandequip-mentrequiredtoimplement theprocedures wereavailable onsite.Thisequipment wasfoundtobeinseparately storedandlabeledcontainers inareasreadilyaccessible toplantmaintenance personnel.
January2798.'i.DOCKETNO(S).~0->>5and~0->>6Hr.JohnDolan,Vicepresident IndianaandMichiganElectricCompanyc/ooAmericanAElectric PowerServiceCorporation 1Riverside PlazaColumbus, Ohio43216
SUBJECT:
D.C.CookNuclearPlant,UnitsIand2DISTRIBDIION:
DocketPileLocelPDRNRCPDRPWRf34ReadingBJYoungblood:
ReadingMDuncanDWigginton ACRS(10)NThompson EJordanJPartlowBGrimesNoticeofReceiptofApplication, datedDraft/Final Environmental Statement, datedNoticeofAvailability ofDraft/Final Environmental Statement, datedSafetyEvaluation Report,orSupplement No.datedEnvironmental Assessment andFindingofNoSignificant Impact,datedNoticeofConsideration ofIssuanceofFacilityOperating LicenseorAmendment toFaci1ityOperating License,datedQBi-Weekly Notice;Applications andAmendments toOperating LicensesInvolving Nocededd*ddddd.dd~del3Exemption, datedConstruction PermitNo.CPPR-,Amendment No.datedFacilityOperating LicenseNo.,Amendment No.OrderExtending Construction Completion Date,datedMonthlyOperating Reportfortransmitted byletterdatedAnnual/Semi-Annual Report-datedtransmitted byletterdatedThefollowing documents concerning ourreviewofthesubjectfacilityaretransmitted foryourinformation.
Enclosures:
AsstatedOfficeofNuclearReactorRegulation CC:SeenextpageOFFICE/SURNAME)DATEI3PWR$/4/PWR-~~~~~~~~~~~~~~~~~noan/.ra01////87~~~~/(Pe~~~~~~~~~-A.DVa.gga.ntan....
01/Q7/87~~~eÃe>(e~~~~~~~~~PWRIIO~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~e~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~NRCFORM3181101801 NRCM0240OFFICIALRECORDCOPY
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