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MONTHYEARML20245H2301989-02-15015 February 1989 Internal Conduit Fire Seal Program,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept Project stage: Other 1989-02-15
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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
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l TECHNICAL EVALUATION REPORT INTERNAL CONDUIT FIRE SEAL PROGRAM f.
l DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2 l
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TSAIC-89/1111 TECHNICAL EVALUATION REPORT INTERNAL CONDUIT FIRE SEAL PROGRAM l DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2 t
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_Y February 15, 1989 5AE Prepared for:
U.S. Nuclear Regulatory Comission Washington, D.C.
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Contract NRC-03-87-029, Task 3 Pcwt Offee Bon 130,1710 GocvJhdge Orke McLeon. Vaginia 22102. ()(11) 8214300
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i TABLE OF CONTENTS Section Pace I
j INTRODUCTION.......................,,...
I DISCUSSION.............................
1 EVALUATION.............................
3 CONCLUSION.............................
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FOREWORD This Technical Evaluation Report was prepared by Science Applications International Corporation (SAIC) under a contract with the U.S.
Nuclear Regulatory Commission (Office of Nuclear Reactor Regulation) for technical assistance in support of NRC operating reactor licensing actions.
-The technical evaluation was conducted in accordance with criteria established by the NRC l
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TECHNICAi.EVALUATIONREPORT INTERNAL CONDUIT FIRE SEAL PROGRAM DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2 INTRODUCTION By letter dated October 20, 1988 Indiana Michigan Power, the Licensee, submitted to the NRC, a discussion of the internal conduit seal program for D.C.
Cook Nuclear Plant Units 1 and 2.
This submittal addresses Open Item 2.r from NRC Inspection Report 85013 dated August 23, 1985.
This Technical Evaluation Report (TER) documents an independent review of the information submitted by the Licensee and an assessment of whether closure of the open item is wt,rranted.
DISCUSSION The fire protection licensing basis for D.C. Cook is Appendix A to BTP APCSB 9.5-1.
Section D.I.J of this document states " Floors, walls and ceilings enclosing separate fire areas should have minimum fire ratings of three hours.
Penetrations in these fire barriers, including conduits and
- piping, should be sealed or closed to provide a fire resistance rating at least equal to that of the fire barrier itself...." This guideline does not specifically call for sealing inside of conduits.
Subsequent NRC fire protection guidelines included in BTP CMEB 9.5-1 specifically identify criteria for installing internal conduit seals.
The Safety Evaluation of the Licensee's fire protection program dated July 31,1979 states "The penetration fire stops are provided to prevent the movement of fire from one area to another along the electrical cables which run through these fire areas. Silicone foam poured in and around the cable l
trays and conduits where they penetrate fire barriers make up the penetration fire stops." The NRC Safety Evaluation was based on the Licensee's response to Appendix A to BTP APCSB 9.5-1 dated July 31, 1977 and the plant Fire Hazards Analysis dated March 31, 1977. During an NRC Region III inspection of the plant, conducted April 29 through May 3 June 21, and August 5 through 9, 1985 the inspector reviewed the licensee's penetration l
sealing program. This review included a discussion of a licensee internal memo dated May 3, 1984. This memo identified a program to provide internal conduit seals on all newly installed conduit; however, the program was not J
retroactive and, therefore, did not address previously insta11e3 conduits.
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Based on the r2 view, the inspector concluded that the reference to fire s e a'.. "in and around the cable trays and conduits" in the 1979 SER 1
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constituted a commitment by the Licensee to provide internal conduit seals 1
and therefore, all conduits should have internal seals contrary to the memo.
The Licensee took the position that no commitment was made for internal I
conduit seals and that the wording in the SER was misinterpreted.
The
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Licensee maintained that "in and around" was intended to apply to cable I
trays and 'that only "around" was intended to apply to conduits.
The NRC
-inspection report left this as Open Item 2.r.
Subsequent to the inspection, the NRC Chemical Engineering. Branch of the Office of Nuclear Reactor Regulation (NRR) reviewed this issue by request of NRC Region III. NRR informed the Region on May 16, 1985 that the intent of the July 31, 1979 SER statement on fire seals was for the Licensee to seal the inside of conduits. NRR further stated that if the Licensee could provide justification for not sealing the inside of conduits, this justification would be reviewed and dispositioned accordingly.
.This
- r. clarification of the SER was provided to the Licensee by Region III on May
~17, 1985 and also included in the August 23, 1985 inspection report.
The Licensee submittal of October 20, 1988, with which this TER is-primarily concerned, provides a reiteration by the Licensee of its original position, that it was in compliance with Appendix A to. BTP APCSB 9.5-1; however, it also provides a commitment to provide seals based on criteria in the submittal.
The submittal states that the criteria is based on information included in a report entitled " Conduit Fire Protection Research Program" which was submitted to the NRC by Wisconsin Electric Power Company 1
-on November 4, 1987.
The criteria proposed for internal conduit sealing at D.C. Cook, as included in the October 20, 1988 submittal is as follows:
1.
An open-ended conduit is one in which the contained cables exit the conduit into an open air space rather than into an enclosure attached to the conduit.
2.
The distance specified for conduit terminations, in Items 4,
5, and 6 below, represent the linear length of the conduit as measured from the point of exit from the penetration.
3.
When both ends of any size double open-ended conduit terminate at the wall, it will be treated as a sleeve and sealed in accordance with the fire barrier penetration seal program.
4.
Double open-ended conduits smaller than 2 inches in diameter will be sealed on at least one end when either end of the conduit terminates less than one foot from the brrier.
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5.
Double open-ended conduits 2 inches in diameter will be sealed on at least one end when either end of the conduit terminates less than 3 feet from the barrier.
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6.
Double open-ended conduits greaur than 2 inches in diameter will be sealed on at least one end when either end of the conduit terminates less than 3 feet from the barrier or has a cable fill of less than 40 percent.
7.
The sea) inside of conduits will, as a minimum, be as described in the research program report.
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The Licensee states that all new installations or resealed conduit will be sealed to this criteria and that existing conduits are already sealed, as a minimum, to this criteria. The Licensee states that the conduit sealing program is based un a conservative approach and exceeds its licensing requirements and therefore, Item 2.r from Inspection Report NRC 85013 should be closed.
EVALUATION The staff initially reviewed the report " Conduit Fire Protection Research Program" which was used as the basis for the proposed sealing criteria at D.C. Cook. As a result of this review, several concerns were raised regarding the parameters used to support test conclusions.
The NRC staff was concerned with use of the term " closed" to define an acceptable termination of conduit.
It is agreed that the reported test results support the conclusion that termination of conduit in a junction box provides reasonable assurance that fire and smoke will not propagate beyond the junction box.. However, there was concern that also including the term
" noncombustible closure" under the definition for ' closed" may allow for misinterpretation of the test findings. Test sponsors indicated during a meeting on July 12,1988, that noncombustible closure is intended to be limited to conduits which are sealed with an approved noncombustible material. Therefore, " closed" is to be defined as a conduit terminating in a junction box or sealed with a noncombustible material. Based on this, it would not be acceptable for a licensee to define noncombustible closure as equipment cabinet, metal cabinet or some other ty>e of enclosure other an than a junction box unless an analysis is performed witch demonstrated that enclosure would prevent the passage of fire and smoke to the unexposed area at least equivalent to that protection provided by a junction box.
It should also be noted that any conduits, cables and components also being located within the terminating enclosure of concern must be evaluated as associated circuits under 10 CFR 50 Appendix R.
The D.C. Cook submittal defines open-ended conduit as one in which the contained cables exit the conduit into an open air space rather G an into an enclosure attached to the conduit. Since the Licensee uses the term
" enclosure" in its definition of "open" conduit, it must therefore ensure 3
that its enclosures are at least equivalent to the protection provided by a junction box.
The staff was concerned that the application of the proposed sealing criteria in the research program report may not be applied to both sides of a barrier, potentially allowing for an untested configuration to be installed.
This is of concern since the conclusions drawn from the test data can only be substantiated for the configurations on the unexposed side of the test slab. Therefore, this concern is eliminated if a licensee ensures that the sealing criteria is implemented in all fire areas regardless of the configuration on the opposite side of the barrier.
The proposed criteria for D.C. Cook does differ in that it uses the phrase " double open-ended" and establishes that this type of conduit will be provided with a seal on at least one side. The research program report criteria are concerned with the sealing requirements within a fire area, and therefore seals may be required at both ends of a " double open-ended" conduit if the specified criteria in the research program report are not met.
This may allow for variation in required seals between the D.C.
Cook criteria and the research program criteria. However, the sealing program proposed for D.C.
Cook is considered to be more conservative than that required by Appendix A to BTP APCSB 9.5-1 and therefore, as a minimum, complies with regulatory guidelines.
It must also be noted that the Licensee did initiate a conduit sealing program in 1984 which provided internal seals in a number of conduits in compliance with BTP CMEB 9.5-1.
While the Licensee has stated that this program should not be construed has a commitment to the more recent NRC guidelines, it does mean that many internal sea?$,
installed to current NRC criteria, are in the plant and would serve the purpose of preventing fire propagation it necessary.
This provides additional conservatism in the Licensee's fire protection program.
The research program report has incorporated the parameter of percent cable fill into the sealing criteria. The staff was concerned over the use of 40% cable fill as a cutoff point for no sealing and that use of cable fill in sealing criteria could be a difficult program to implement and also to enforce.
The specific concern for the 40% level or greater as a level requiring no seals for certain size diameter conduits is whether this would be a l
conservative value. The level of 40% is generally considered to be maximum l
fill and a majority of conduits are filled to this level. Therefore, if the level requiring no seals was 41%, a large number of conduits nnt requiring seals would now require seals. This was discussed with test sponsors during the July meeting. The tett sponsors were able to demonstrate that the test results supported cable fill as a contributing factor to eliminate seals and additionally that cable fill helped to prevent the passage of flames and smoke at levels far less than 40%. Therefore, it is concluded thtt the use of cable fill is a legitimate parameter and the establishment of 40% or greater as the level not requiring seals for certain conditions is corHdered to be a conservative value.
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present implementation problems for licensees and would be-difficult to verify both by plant personnel during periodic inspections and by NRC inspectors.
This issue was discussed at length among the NRC and test-sponsors.
The sponsors indicated that cable fill is the least controlling parameter and therefore the last one to be considered when detemining the need for conduit seals.
It was indicated that if plants do have a detailed tracking system for conduits which includes percent of cable fill in addition to other parameters of concern, 'these systems would be the basis for determining the need for seals and could be readily accessible by both plant inspection personnel and NRC inspectors. The staff agrees that there is sound technical justification to use percent cable fill as one of the-sealing parameters. However, licensees choosing to use this parameter must accept the burden of providing a tracking program that is functional and can be readily demonstrated to satisfy the accepted criteria.
The proposed D.C.
Cook criteria incorporates the 40% cable fill criteria as one of the. determining parameters. The review of the research program demonstrated that use of cable fill was a valid parameter; however, since D.C.
Cook chose to use this parameter, they accept the burden of maintaining a program to adequately track cable fill.
Based on the submittal by D.C. Cook dated October 20, 1988 and the report
- Conduit Fire Protection Research Program" dated November 4, 1987 for which it was based, it is concluded that the proposed internal conduit sealing method for D.C. Cook is in compliance with the licensing basis of the plant and provides reasonable assurance that fire and significant smoke and hot gases would not propagate from one fire area to another. Therefore, the Licensee has provided adequate justification for their conduit sealing program and Open Item 2.r from Inspection Report 85013 should be closed.
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CONCLUSION Based on a review of the Licensee submittal dated October 20, 1988 and I
evaluation of a report entitled " Conduit Fire Protection Research Program,"
the internal conduit sealing program proposed by the Licensee for D.C.
Cook has been found to be in compliance with Appendix A to BTP APCSB 9.5-1.
In addition, the Licensee has provided adequate justification for its internal conduit sealing program and therefore, Open Item 2.r from NRC Inspection Report 85013 should be closed.
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