Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 3 - Appendix B,Dma Digraphs and Reference Drawings.Hardcopy and 174 Aperture Cards Available in PDR OnlyML20140E430 |
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Indian Point |
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Issue date: |
01/31/1986 |
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From: |
Alesso H, Altenbach T, Ashmore B, Fromme D, Hershberger M, Kimura C, Lappa D, Patenaude C, Prassinos P, Prassinos P, Sacks I, Will Smith, William Williams ANALYTIC INFORMATION PROCESSING, INC., LAWRENCE LIVERMORE NATIONAL LABORATORY, SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
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To: |
NRC |
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References |
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NUREG-CR-4179, NUREG-CR-4179-V03, NUREG-CR-4179-V3, UCID-20350-V03, UCID-20350-V3, NUDOCS 8603270515 |
Download: ML20140E430 (21) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20101S4391992-06-30030 June 1992 Pump & Valve Inservice Testing Program for Indian Point 3 Nuclear Power Plant, Technical Evaluation Rept ML19351A2461989-09-30030 September 1989 Evaluation of Max Density Spent Fuel Rack Structural Analysis for Indian Point Station Unit 3, Technical Evaluation Rept ML20069N2031988-10-31031 October 1988 Rev 1 to, Conformance to Reg Guide 1.97:Indian Point-3, Technical Evaluation Rept ML20237A5461987-08-31031 August 1987 Reactor Coolant Pump Seal Evaluations ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20140H3071986-03-31031 March 1986 Probabilistic Safety Study Applications Program for Inspection of Indian Point Unit 3 Nuclear Power Plant ML20155E8651986-01-31031 January 1986 Fault Tree Application to the Study of Systems Interactions at Indian Point 3 ML20154S4181986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3 ML20140E4701986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 5 - Appendix D,Probability Data Base. Hardcopy Available in PDR Only ML20140E4641986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume IV - Appendix C.Hardcopy Available in PDR Only ML20140E4301986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 3 - Appendix B,Dma Digraphs and Reference Drawings.Hardcopy and 174 Aperture Cards Available in PDR Only ML20140E3721986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit No. 3.Volume II - Appendix A.Hardcopy Available in PDR Only ML20138K9841985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Byron Station Unit 1,Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20107K9341984-07-10010 July 1984 Draft Control of Heavy Loads - Phase Ii,Indian Point Nuclear Power Plant Unit 2, Technical Evaluation Rept ML20091D2061984-05-31031 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure ML20090H8051984-05-23023 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure Under Combined Loads ML20127M8231984-02-13013 February 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1984 ML20127N6901984-01-16016 January 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Dec 1983 ML20127N6461983-11-17017 November 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Oct 1983 ML20127N6241983-08-31031 August 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Aug 1983 ML20127N5971983-07-31031 July 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jul 1983 ML20072E4341983-06-30030 June 1983 Investigation of the Shell Cracking on the Steam Generators of Indian Point No. 3.Docket No. 50-286.(Consolidated Edison Company) ML20127N5681983-06-16016 June 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for May 1983 ML20084N0881983-06-0101 June 1983 Analysis of PRA Testimony:Indian Point ASLB Hearings, Commission Question 1, Final Rept ML20127N5301983-04-30030 April 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Apr 1983 ML20127N4831983-03-31031 March 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Mar 1983 ML20083Q7111983-03-0404 March 1983 Preliminary Investigation of Interconnected Sys Interactions for Safety Injection Sys of Indian Point 3 ML20127N4001983-02-28028 February 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Feb 1983 ML20127N2761983-01-31031 January 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1983 ML20028D7201982-12-31031 December 1982 Review and Evaluation of the Indian Point Probabilistic Safety Study ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069N7621982-09-30030 September 1982 Review of Indian Point Probabilistic Safety Study ML20065D2901982-09-30030 September 1982 Evaluation of the Prompt Alerting Systems at Four Nuclear Power Stations ML20027C1061982-08-31031 August 1982 Degraded Grid Protection for Class IE Power Sys,Indian Point Nuclear Station Unit 3, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20105B4161982-08-25025 August 1982 Ltr Rept on Review of Evaluation of Indian Point Probabilistic Safety Study, Draft Rept ML1009802071982-06-11011 June 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11,B-60),Con Ed, Indian Point Unit 2, Technical Evaluation Rept ML20054F5101982-05-31031 May 1982 Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures ML20086S6611982-03-0101 March 1982 Review of PASNY Sys Interaction Study ML20086S6481981-06-15015 June 1981 Review of PASNY Sys Interaction Study ML20086S6201981-04-30030 April 1981 Systems Interaction Evaluation Procedure for Application to Indian POINT-3 ML19341D0011981-01-31031 January 1981 Adequacy of Station Electrical Distribution Sys Voltages, Indian Point Nuclear Station,Unit 2, Technical Evaluation Rept ML20003C2611981-01-31031 January 1981 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant. ML19351F6641980-12-31031 December 1980 Adequacy of Station Electrical Distribution Sys Voltages, Indian Point Nuclear Station,Unit 2, Preliminary Technical Evaluation Rept ML20148H4821980-11-13013 November 1980 Hudson River White Perch, Quarterly Progress Rept Apr-June,1980 ML19341A1571980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Indian Point Unit 3, Technical Evaluation Rept ML19337A8461980-09-26026 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Inidian Point Unit 2, Interim Technical Evaluation Rept ML19320D5461980-06-30030 June 1980 Evaluation of Impingement Losses of White Perch at Indian Point Nuclear Station & Other Hudson River Power Plants. 1992-06-30
[Table view] Category:QUICK LOOK
MONTHYEARML20101S4391992-06-30030 June 1992 Pump & Valve Inservice Testing Program for Indian Point 3 Nuclear Power Plant, Technical Evaluation Rept ML19351A2461989-09-30030 September 1989 Evaluation of Max Density Spent Fuel Rack Structural Analysis for Indian Point Station Unit 3, Technical Evaluation Rept ML20069N2031988-10-31031 October 1988 Rev 1 to, Conformance to Reg Guide 1.97:Indian Point-3, Technical Evaluation Rept ML20237A5461987-08-31031 August 1987 Reactor Coolant Pump Seal Evaluations ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20140H3071986-03-31031 March 1986 Probabilistic Safety Study Applications Program for Inspection of Indian Point Unit 3 Nuclear Power Plant ML20155E8651986-01-31031 January 1986 Fault Tree Application to the Study of Systems Interactions at Indian Point 3 ML20154S4181986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3 ML20140E4701986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 5 - Appendix D,Probability Data Base. Hardcopy Available in PDR Only ML20140E4641986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume IV - Appendix C.Hardcopy Available in PDR Only ML20140E4301986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 3 - Appendix B,Dma Digraphs and Reference Drawings.Hardcopy and 174 Aperture Cards Available in PDR Only ML20140E3721986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit No. 3.Volume II - Appendix A.Hardcopy Available in PDR Only ML20138K9841985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Byron Station Unit 1,Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20107K9341984-07-10010 July 1984 Draft Control of Heavy Loads - Phase Ii,Indian Point Nuclear Power Plant Unit 2, Technical Evaluation Rept ML20091D2061984-05-31031 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure ML20090H8051984-05-23023 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure Under Combined Loads ML20127M8231984-02-13013 February 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1984 ML20127N6901984-01-16016 January 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Dec 1983 ML20127N6461983-11-17017 November 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Oct 1983 ML20127N6241983-08-31031 August 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Aug 1983 ML20127N5971983-07-31031 July 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jul 1983 ML20072E4341983-06-30030 June 1983 Investigation of the Shell Cracking on the Steam Generators of Indian Point No. 3.Docket No. 50-286.(Consolidated Edison Company) ML20127N5681983-06-16016 June 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for May 1983 ML20084N0881983-06-0101 June 1983 Analysis of PRA Testimony:Indian Point ASLB Hearings, Commission Question 1, Final Rept ML20127N5301983-04-30030 April 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Apr 1983 ML20127N4831983-03-31031 March 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Mar 1983 ML20083Q7111983-03-0404 March 1983 Preliminary Investigation of Interconnected Sys Interactions for Safety Injection Sys of Indian Point 3 ML20127N4001983-02-28028 February 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Feb 1983 ML20127N2761983-01-31031 January 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1983 ML20028D7201982-12-31031 December 1982 Review and Evaluation of the Indian Point Probabilistic Safety Study ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069N7621982-09-30030 September 1982 Review of Indian Point Probabilistic Safety Study ML20065D2901982-09-30030 September 1982 Evaluation of the Prompt Alerting Systems at Four Nuclear Power Stations ML20027C1061982-08-31031 August 1982 Degraded Grid Protection for Class IE Power Sys,Indian Point Nuclear Station Unit 3, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20105B4161982-08-25025 August 1982 Ltr Rept on Review of Evaluation of Indian Point Probabilistic Safety Study, Draft Rept ML1009802071982-06-11011 June 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11,B-60),Con Ed, Indian Point Unit 2, Technical Evaluation Rept ML20054F5101982-05-31031 May 1982 Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures ML20086S6611982-03-0101 March 1982 Review of PASNY Sys Interaction Study ML20086S6481981-06-15015 June 1981 Review of PASNY Sys Interaction Study ML20086S6201981-04-30030 April 1981 Systems Interaction Evaluation Procedure for Application to Indian POINT-3 ML19341D0011981-01-31031 January 1981 Adequacy of Station Electrical Distribution Sys Voltages, Indian Point Nuclear Station,Unit 2, Technical Evaluation Rept ML20003C2611981-01-31031 January 1981 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant. ML19351F6641980-12-31031 December 1980 Adequacy of Station Electrical Distribution Sys Voltages, Indian Point Nuclear Station,Unit 2, Preliminary Technical Evaluation Rept ML20148H4821980-11-13013 November 1980 Hudson River White Perch, Quarterly Progress Rept Apr-June,1980 ML19341A1571980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Indian Point Unit 3, Technical Evaluation Rept ML19337A8461980-09-26026 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Inidian Point Unit 2, Interim Technical Evaluation Rept ML19320D5461980-06-30030 June 1980 Evaluation of Impingement Losses of White Perch at Indian Point Nuclear Station & Other Hudson River Power Plants. 1992-06-30
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20101S4391992-06-30030 June 1992 Pump & Valve Inservice Testing Program for Indian Point 3 Nuclear Power Plant, Technical Evaluation Rept ML19351A2461989-09-30030 September 1989 Evaluation of Max Density Spent Fuel Rack Structural Analysis for Indian Point Station Unit 3, Technical Evaluation Rept ML20069N2031988-10-31031 October 1988 Rev 1 to, Conformance to Reg Guide 1.97:Indian Point-3, Technical Evaluation Rept ML20237A5461987-08-31031 August 1987 Reactor Coolant Pump Seal Evaluations ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20140H3071986-03-31031 March 1986 Probabilistic Safety Study Applications Program for Inspection of Indian Point Unit 3 Nuclear Power Plant ML20155E8651986-01-31031 January 1986 Fault Tree Application to the Study of Systems Interactions at Indian Point 3 ML20154S4181986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3 ML20140E4701986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 5 - Appendix D,Probability Data Base. Hardcopy Available in PDR Only ML20140E4641986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume IV - Appendix C.Hardcopy Available in PDR Only ML20140E4301986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 3 - Appendix B,Dma Digraphs and Reference Drawings.Hardcopy and 174 Aperture Cards Available in PDR Only ML20140E3721986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit No. 3.Volume II - Appendix A.Hardcopy Available in PDR Only ML20138K9841985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Byron Station Unit 1,Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20107K9341984-07-10010 July 1984 Draft Control of Heavy Loads - Phase Ii,Indian Point Nuclear Power Plant Unit 2, Technical Evaluation Rept ML20091D2061984-05-31031 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure ML20090H8051984-05-23023 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure Under Combined Loads ML20127M8231984-02-13013 February 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1984 ML20127N6901984-01-16016 January 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Dec 1983 ML20127N6461983-11-17017 November 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Oct 1983 ML20127N6241983-08-31031 August 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Aug 1983 ML20127N5971983-07-31031 July 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jul 1983 ML20072E4341983-06-30030 June 1983 Investigation of the Shell Cracking on the Steam Generators of Indian Point No. 3.Docket No. 50-286.(Consolidated Edison Company) ML20127N5681983-06-16016 June 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for May 1983 ML20084N0881983-06-0101 June 1983 Analysis of PRA Testimony:Indian Point ASLB Hearings, Commission Question 1, Final Rept ML20127N5301983-04-30030 April 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Apr 1983 ML20127N4831983-03-31031 March 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Mar 1983 ML20083Q7111983-03-0404 March 1983 Preliminary Investigation of Interconnected Sys Interactions for Safety Injection Sys of Indian Point 3 ML20127N4001983-02-28028 February 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Feb 1983 ML20127N2761983-01-31031 January 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1983 ML20028D7201982-12-31031 December 1982 Review and Evaluation of the Indian Point Probabilistic Safety Study ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069N7621982-09-30030 September 1982 Review of Indian Point Probabilistic Safety Study ML20065D2901982-09-30030 September 1982 Evaluation of the Prompt Alerting Systems at Four Nuclear Power Stations ML20027C1061982-08-31031 August 1982 Degraded Grid Protection for Class IE Power Sys,Indian Point Nuclear Station Unit 3, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20105B4161982-08-25025 August 1982 Ltr Rept on Review of Evaluation of Indian Point Probabilistic Safety Study, Draft Rept ML1009802071982-06-11011 June 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11,B-60),Con Ed, Indian Point Unit 2, Technical Evaluation Rept ML20054F5101982-05-31031 May 1982 Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures ML20086S6611982-03-0101 March 1982 Review of PASNY Sys Interaction Study ML20086S6481981-06-15015 June 1981 Review of PASNY Sys Interaction Study ML20086S6201981-04-30030 April 1981 Systems Interaction Evaluation Procedure for Application to Indian POINT-3 ML19341D0011981-01-31031 January 1981 Adequacy of Station Electrical Distribution Sys Voltages, Indian Point Nuclear Station,Unit 2, Technical Evaluation Rept ML20003C2611981-01-31031 January 1981 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant. ML19351F6641980-12-31031 December 1980 Adequacy of Station Electrical Distribution Sys Voltages, Indian Point Nuclear Station,Unit 2, Preliminary Technical Evaluation Rept ML20148H4821980-11-13013 November 1980 Hudson River White Perch, Quarterly Progress Rept Apr-June,1980 ML19341A1571980-09-30030 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Indian Point Unit 3, Technical Evaluation Rept ML19337A8461980-09-26026 September 1980 Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Inidian Point Unit 2, Interim Technical Evaluation Rept ML19320D5461980-06-30030 June 1980 Evaluation of Impingement Losses of White Perch at Indian Point Nuclear Station & Other Hudson River Power Plants. 1992-06-30
[Table view] Category:NUREG REPORTS
MONTHYEARML20237A5461987-08-31031 August 1987 Reactor Coolant Pump Seal Evaluations ML20140H3071986-03-31031 March 1986 Probabilistic Safety Study Applications Program for Inspection of Indian Point Unit 3 Nuclear Power Plant ML20140E4701986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 5 - Appendix D,Probability Data Base. Hardcopy Available in PDR Only ML20140E4641986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume IV - Appendix C.Hardcopy Available in PDR Only ML20140E4301986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 3 - Appendix B,Dma Digraphs and Reference Drawings.Hardcopy and 174 Aperture Cards Available in PDR Only ML20140E3721986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit No. 3.Volume II - Appendix A.Hardcopy Available in PDR Only ML20154S4181986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3 ML20155E8651986-01-31031 January 1986 Fault Tree Application to the Study of Systems Interactions at Indian Point 3 ML20091D2061984-05-31031 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure ML20072E4341983-06-30030 June 1983 Investigation of the Shell Cracking on the Steam Generators of Indian Point No. 3.Docket No. 50-286.(Consolidated Edison Company) ML20028D7201982-12-31031 December 1982 Review and Evaluation of the Indian Point Probabilistic Safety Study ML20065D2901982-09-30030 September 1982 Evaluation of the Prompt Alerting Systems at Four Nuclear Power Stations ML20054F5101982-05-31031 May 1982 Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures ML20086S6201981-04-30030 April 1981 Systems Interaction Evaluation Procedure for Application to Indian POINT-3 ML19320D5461980-06-30030 June 1980 Evaluation of Impingement Losses of White Perch at Indian Point Nuclear Station & Other Hudson River Power Plants. 1987-08-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20101S4391992-06-30030 June 1992 Pump & Valve Inservice Testing Program for Indian Point 3 Nuclear Power Plant, Technical Evaluation Rept ML19351A2461989-09-30030 September 1989 Evaluation of Max Density Spent Fuel Rack Structural Analysis for Indian Point Station Unit 3, Technical Evaluation Rept ML20069N2031988-10-31031 October 1988 Rev 1 to, Conformance to Reg Guide 1.97:Indian Point-3, Technical Evaluation Rept ML20237A5461987-08-31031 August 1987 Reactor Coolant Pump Seal Evaluations ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20140H3071986-03-31031 March 1986 Probabilistic Safety Study Applications Program for Inspection of Indian Point Unit 3 Nuclear Power Plant ML20140E4701986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 5 - Appendix D,Probability Data Base. Hardcopy Available in PDR Only ML20155E8651986-01-31031 January 1986 Fault Tree Application to the Study of Systems Interactions at Indian Point 3 ML20154S4181986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3 ML20140E4641986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume IV - Appendix C.Hardcopy Available in PDR Only ML20140E4301986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit 3.Volume 3 - Appendix B,Dma Digraphs and Reference Drawings.Hardcopy and 174 Aperture Cards Available in PDR Only ML20140E3721986-01-31031 January 1986 Digraph Matrix Analysis for Systems Interactions at Indian Point Unit No. 3.Volume II - Appendix A.Hardcopy Available in PDR Only ML20138K9841985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Byron Station Unit 1,Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20107K9341984-07-10010 July 1984 Draft Control of Heavy Loads - Phase Ii,Indian Point Nuclear Power Plant Unit 2, Technical Evaluation Rept ML20091D2061984-05-31031 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure ML20090H8051984-05-23023 May 1984 Reliability Assessment of Indian Point Unit 3 Containment Structure Under Combined Loads ML20127M8231984-02-13013 February 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1984 ML20127N6901984-01-16016 January 1984 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Dec 1983 ML20127N6461983-11-17017 November 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Oct 1983 ML20127N1191983-10-20020 October 1983 Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion, Issued to BNL ML20127M8561983-09-0202 September 1983 Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion, Issued to BNL ML20127N6241983-08-31031 August 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Aug 1983 ML20127A8291983-08-0404 August 1983 Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents;Operating Reactor Reviews for Indian Point & Zion, Awarded to BNL ML20127N5971983-07-31031 July 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jul 1983 ML20072E4341983-06-30030 June 1983 Investigation of the Shell Cracking on the Steam Generators of Indian Point No. 3.Docket No. 50-286.(Consolidated Edison Company) ML20127N5681983-06-16016 June 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for May 1983 ML20084N0881983-06-0101 June 1983 Analysis of PRA Testimony:Indian Point ASLB Hearings, Commission Question 1, Final Rept ML20127N5301983-04-30030 April 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Apr 1983 ML20127N4831983-03-31031 March 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Mar 1983 ML20083Q7111983-03-0404 March 1983 Preliminary Investigation of Interconnected Sys Interactions for Safety Injection Sys of Indian Point 3 ML20127N4001983-02-28028 February 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Feb 1983 ML20127N2761983-01-31031 January 1983 Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Monthly Highlights for Jan 1983 ML20127A4531983-01-24024 January 1983 Std Order for DOE Work: Safety Evaluation of Core Melt Accidents:Indian Point-OR & Zion-OR, Issued to BNL ML20028D7201982-12-31031 December 1982 Review and Evaluation of the Indian Point Probabilistic Safety Study ML20127M3211982-12-30030 December 1982 Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor ML20127M2231982-12-0303 December 1982 Project & Budget Proposal for NRC Work: Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065D2901982-09-30030 September 1982 Evaluation of the Prompt Alerting Systems at Four Nuclear Power Stations ML20069N7621982-09-30030 September 1982 Review of Indian Point Probabilistic Safety Study ML20027C1061982-08-31031 August 1982 Degraded Grid Protection for Class IE Power Sys,Indian Point Nuclear Station Unit 3, Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20105B4161982-08-25025 August 1982 Ltr Rept on Review of Evaluation of Indian Point Probabilistic Safety Study, Draft Rept ML1009802071982-06-11011 June 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11,B-60),Con Ed, Indian Point Unit 2, Technical Evaluation Rept ML20054F5101982-05-31031 May 1982 Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures ML20086S6611982-03-0101 March 1982 Review of PASNY Sys Interaction Study ML20086S6481981-06-15015 June 1981 Review of PASNY Sys Interaction Study ML20086S6201981-04-30030 April 1981 Systems Interaction Evaluation Procedure for Application to Indian POINT-3 ML20003C2611981-01-31031 January 1981 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant. 1992-06-30
[Table view] |
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NUREG CR ,
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AUG 2 01984 DIGRAPH MATRIX ANALYSIS FOR SYSTEMS INTERt.CTIONS
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AT 1NDIAN POINT UNIT 3
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Lawrence Livermore Nation 31.!.d!)orats.ry '
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Livermore, California; '94550-I . J. Sacks B. C. Ashmore, D,, C. 'Frcane, M. Hers'nbergr-r
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Analytic Information Proessing, fnc.
C. F. Smith, W. J. Williams ,
Science Applications, Inc.' ,,. ',
Prepared for U. S. Nuclear Regulatory Co:wnission August 1984 l
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APPENDIX B DMA DIGRAPHS AND REFERENCE DRAWINGS l 1 i
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FOREWORD m
s In general, the digraphs in this appendix fall into one of two catagories:
- 1) traced directly from P&ID's or
- 2) drawn from a group of drawings and/or system descriptions..
In the case of traced drawings, the P&ID used is included here for visual reference. .Three drawings will be grouped together in a. plastic insert and '
when unfolded, will lay out as follows:
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The X's on the drawings should be lined up for viewing. In order to view the main hardware alone, the Location Overlay is removed from the stack revealing a tracing from the P&ID. In a few instances, Location Overlays
'q do not exist.
Case 2 yields all other drawings. Since they are not traced from the P&ID's, the P&ID's are not included. The drawing will stand on its own.
Some of these drawings are actual hardware models, whereas others are failure criterion representations.
The failure-criterion drawings are constructed utilizing written documentation. The analyst uses this material to create these digraphs which represent the number of physical items necessary for a particular situation.
I Drawings titled, " Unit Models" (UM's) may refer to more than one plant i item. In this case, some symbol should be replaced with the plant item I number. This information is given on the drawing.
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r TABLE OF CONTENTS Page B.1 Safety Injection System Drawings 1 B.2 Safety Injection Actuation Drawings 3 B.3 Main Feedwater System Drawings 4 B.4 Auxiliary Feedwater System Drawings 6 B.5 Isolation and Actuation Logic Drawings 7 B.6 Electrical AC and DC Power, DC Control Drawings 8 B.7 Reactor Coolant Pump Seals and CVCS Drawings 11 B.8 Component Cooling Water System Drawings 12 B.9 Service Water System Drawings 13 B.10 Pressure Operated Relief Yalve Drawings 15 B.11 Instrument Air System Drawings 16 B.12 Lube Oil System Drawings 17
8.1 Safety Injection System Drawings O
(j B.1.1 Safety Injection and Recirculation System, Sheet No.1 A. Safety Injection and Recirculation System, Sheet No.1 B. P&ID, Flow Diagram, Safety Injection System, Sheet No.1. U.E.8C. Drawing No. 9321-F-27353-14 C. Location Overlay, Safety Injection and Recirculation, Sheet No. 1 B.1.2 Safety Injection and Recirculation System, Sheet No. 2 A. Safety Injection and Recirculation System, Sheet No. 2 B. P&ID, Flow Diagram, Safety Injection System, Sheet No. 2. U.E. AC. Drawing No. 9321-F-27503-11 C. Location Overlay, Safety Injection and Recirculation, Sheet No. 2 B.I.3 Phase and Pump Interconnection with Pump Criteria N (Nlti-Phase)
B.I.4 UM: Motor Operated Valves A. M0V856C, E,H,J B. Westinghouse #500B971 Wiring Diagram, Sheet 155 C. M0V1835A,B, and H0V1852A,8 D. Westinghouse #500B971 Wiring Diagram, Sheet 129 E. MOV888A,B F. Westinghouse #500B971 Wiring Diagram, Sheet 127 G. M0V8568,G H. Westinghouse #5008971 Wiring Diagram, Sheet 128 I. General Valve
PAGE 2 B.1.5 UM: Pumps A. SIP 31,33 B. Westinghouse #5008971 Wiring Diagram, Sheet 28 C. SIP 32 D. Westinghouse #500B971 Wiring Diagram, Sheet 29 E. RHRP31,32 F. Westinghouse #500B971 Wiring Diagram, Sheet 31 G. RECP31 H. Westinghouse #500B971 Wiring Diagram, Sheet 24 I. ~RECP32 J. Westinghouse #500B971 Wiring Diagram, Sheet 36
i PAGE 3 B.2 Safety Injection Actuation Drawings
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(. B.2.1 Low Pressurizer Pressure Trip Logic A. Low Pressurizer Pressure Trip Logic B. P&ID, Flow Diagram, P. A.S.N.Y. 5651072, Pev. 2, Sheet No. 9, Logic Diagrams, Pressurizer Trip Signals B.2.2 Steam Generator Trip Logic A. Steam Generator Trip Logic B. P&ID, Flow Diagram, P. A.S.N.Y 5651072, Rev. 3, Sheet No.10, Logic Diagrams, Steam Generator Trip Signal s B.2.3 Logic Gate Unit Model B.2.4 High-High Containment Pressure Trip Logic A. High-High Containment Pressure Trip Logic B. P&ID, Flow Diagram, P. A.i.N.Y. 5651072, Rev. 6, Sheet 12, Logic Diagrams, Safeguards Actuation B.2.5 High Containment Pressure and Manual Trip Logic A. High Containment Pressure and Panual Trip Logic B. P&ID, Flow Diagram, P. A.S.N.Y. 5651072a, Rev. O, Sheet No.12a, Logic Diagrams, Safeguards Actuation B.2.6 Safety Injection Actuation Train A B.2.7 Safety Injection Actuation Train B B.2.8 Typical Connection to Safety Injection Equipment G
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PAGE 4 B.3 Main Feedwater System Drawings C) B.3.1 Condensate and Main Feed Pump Suction A. Condensate and Main Feed Pump Suction B. P&ID, Flow Diagram, U.E.8C. 9321-F-22703, Rev. 3, Condensate and Main Feed Pump Suction B.3.2 Main Feedwater A. Main Feedwater B. P&ID, Flow Diagram, U.E.&C. 9321-F-20193, Rev.19, Boiler Feedwater B.3.3 Heater Drains Tank and Pump A. Heater Drains Tank and Pump B. P&ID, Flow Diagram, U.E.&C. 9321-F-20223, Rev. 7, Heater Drains and Vents B.3.4 UM: Main Feed Pump Turbine Control Oil System A. Main Feed Pump Turbine Conbrol Oil System O\ B. Pg. 21-9, System Description 21, Feedwater B.3.5 UM: Main Feed Pump Turbine Trip and Reset A. Main Feed Pump Turbine Trip and Reset B. U.E.&C. 9321-LL-31403, Sheet 7 B.3.6 UM: Governor Valve Positioner A. Governor Valve Positioner B. U.E.&C. 9321-LL-31403, Sheet 8 B.3.7 UM: Turbine Low Pressure Stop Valve Controller A. Turbine Low Pressure Valve Controller B. U.E.&C. 9321-LL-31403, Sheet 9 O
g s, PAGE 5 8.3.8 UM: Turbine High Pressure Stop Valve Controller 9 A. Turbine Low Pressure Valve Controller B. U.E.8C. 9321-LL-31403 Sheet 10 1 .I l
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PAGE 6 B.4 Auxiliary Feedwater System Drawings
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'( ) B.4.1 Auxiliary Feed A. Auxiliary feed B. P&ID, Flow Diagram, U.E.&C. 9321-F-20193, Rev.19, Boiler Feedwater B.4.2 UM: AFW A. AFW Auto Start Circuit B. U.E.&C. 9321-LL-31183, Sheet 5, Schematic Digraph, 480V Switchgear 32 C. AFW Pump CB 52/AF1 D. U.E.&C. 9321-LL-31183, Sheet 11, Schematic Digraph, 480V Switchgear 32 Lv)
PAGE 7 B.5 Isolation and Actuation Logic B.5.1 Main Feedwater Isolation A. Main Feedwater Isolation B. P&ID, Flow Diagram, P. A.S.N.Y. 5651072, Sheet 13, Rev. 5, Logic Diagrams, Feedwater Isolation B.5.2 Auxiliary Feedwater Actuation A. Auxiliary Feedwater Actuation B. PAID, Flow Diagram, P. A.S.N.Y. 5651D72, Sheets 7,8,8a,8b (composite drawing)
PAGE 8 B.6 Electrical y and $ Power, E Control rN B.6.1 Master Flowchart for Electrical Digraphs i
, A. Electrical Distribution and Transmission System l
B. Overlay, Electrical Distribution and -
Transmission System C. P&ID, Electrical Distribution and Transmission System, U.E.8C. Drawing No. 9321-F-33853-1 B.6.2 6.9KV Crosstie A. UM: Power Supplies to 6.9KV Buses 1,2,3, and 4 B. UM: Power Supplies to 6.9KV Buses 5 and 6 B.6.3 6.9KV Breakers I A. UM: Station Auxiliary Xfmr Output Breakers STS & ST6 B. UM: Unit Auxiliary Xfmr Output Breakers UT1, UT2, UT3, UT4
.I C. UM: 6.9KV Bus Tie Breakers UTISTS, UT2STS, UT3ST6, UT4ST6 D. UM: Gas Turbine Feed Breakers GT5 and GT6 B.6.4 480V Crosstie l
A. Power Supplies from 6.9KV Buses and D G 's to 480V Buses B. Appendix "F" Mods to 480V Electrical Distribution System f
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PAGE 9 B.6.5 6.9KY and 480Y Breakers A. UM: 6.9KV Feed Breaker to Station Service
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Xfmrs 5S5,2, 3, 6, 312, 313 UM: 480V Bus Normal Feed. Breakers (5, 2, 3, 6, 312, and 313)
C. UM: Manual 480V Bus Crosstie Breakers 2AT5A, 3AT6A, 312, and T313 D. Automatic 480Y Crosstie Breaker 2AT3A E. UM: Diesel Generator Output Breakers EG3, EG1, EG2 B.6.6 Diesel Generator Systems A. UM: Deisel Engine Starting Air System B. U.E.&C. 9321-H-20293, Rev. 4, P&ID, Flow Diagram, Starting Air to Diesel Generators C. UM: Diesel Generator Support Systems D. UM: Diesel Engine Fuel Oil Transfer System E. UM: Diesel Generator Start Signal ;
F. UM: Diesel Generator Exciter G/ G. UM: Diesel Engine Cooling From Station Service Water B.6.7 Relay Logic for 480Y Equipment for S.I. or Bus Undervoltage B.6.8 Motor Control Centers - Power Supplies from 480V Buses to Motor Control Centers B.6.9 MCC Feed Breakers - UM: Motor Control Center Feed Breakers B.6.10 DC Systems A. Power Supplies from Motor Control Centers to DC Trains 31 & 32 B. UM: Power Supply from MCC to DC Trains (33,34)
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PAGE 10 B.6.11 118V AC System g A. UM: Power Supplies to Instrument Buses 31,
!, 32, and 33 B. Power Supply to Instrument Bus 34 B.6.12 Electrical Component Locations B.6.13 Break Model A. Power Feeds to 480V Buses from 6.9KV Buses and Diesel Generators B. 480V Crossties C. Station Service Transformer Feed Breaker - Failure to Trip D. 480V Bus Feed Breaker - Failure to Trip E. Diesel Generator Supply Breakers - Failure to Trip F. 480V Manual Crosstie Breakers - Failure to Trip G. Breaker 2AT3A - Failure to Trip H. DC Power Supply from 480V Bus to DC Power Panel I. DC Power Supply from Power Panel to Distribution Panel s J. DC Crosstie N
I PAGE 11 B.7 Reactor Coolant Pump Seals and CVCS
! B.7.1 Reactor Coolant Pump LOCA (Failure Criterion)
A. Reactor Coolant Pump LOCA, Sheet No.1
-B. Flow Diagram, System Description No.1, Fi g . 10, Pg . 6 B.7.2 Loss in Seal Water Injection A. Loss in Seal Water Injection - PATHSWINJ B. P&ID, Flow Diagram, Con. Ed. Co. A202246, Rev.16, Sheet- 1, Chemical and Volume Control System B.7.3 Flow Out The No.1 Seal Bypass Line A. Flow Out of No.1 Seal Bypass Line - PATH 1BPNJ B. P&ID, Flow Diagram, Con. Ed. Co. A202246, Rev.16, Sheet 1, Chemical and Volume Control System B.7.4 Flow Out The No.1 Seal Leakoff Line
{N A. Flow Out of No.1 Seal Leakoff Line - PATH 1LONJ
(/ B. P&ID, Flow Diagram, Con. Ed. Co. A202246, Rev.16, Sheet 1, Chemical and Volume Control System B.7.5 Flow Out The Thermal Barrier Heat Exchanger Piping A. Flow Out of Thennal Barrier HXR Piping - PATHXRNJ B. P&ID, Flow Diagram, Con. Ed. Co. A202230, Sheets 1, Auxiliary Coolant System B.7.6 Charging Pumps Unit Models A. Charging Pumps - Fails.to Continue to Run B. P&ID, Flow Diagram, Westinghouse 500B971, Rev. 7 Sheets 26, 72, 73, Elementary Wiring Diagram -
Charging Pumps 31, 32, 33 C. Charging Pumps - Fails to Start D. P&ID, Flow Diagram, Westinghouse 500B971, Rev. 7, Sheets 26, 72, 73, Elementary Wiring Diagram -
/"N Charging Pump 31, 32, 33
PAGE 12 B.8 Component Cooling Water System Drawings
'N B.8.1 Component Cooling System A. Component Cooling System, Sheet No.1 B. P&ID, Flow Diagram, Auxiliary Coolant System, Sheet No. 1, U.E.&C. 9321-F-27203-13 B.8.2 Component Cooling System A. Component Cooling System, Sheet No. 2 B. P&ID, Flow Diagram, Auxiliary Coolant System, i Sheet No. 1, U.E.&C 9321-F-27513-16 C. Location Overlay, Component Cooling System Digraph B.8.3 UM: Component Cooling Pump A. CCWP31 B. Westinghouse #500B971 Wiring Diagram, Sheet 27 C.
CCWP32 D. Westinghouse #500B971 Wiring Diagram, Sheet 45
'N E. CCWP33 (s F. Westinghouse #500B971 Wiring Diagram, Sheet 46 G. CCBP31,32,33,34 H. Westinghouse #5008971 Wiring Diagram, Sheet 51 B.8.4 UM: Motor Operated Valves A. MOV1835A,B, and M0V1852A,B B. Westinghouse #500B971 Wiring Diagram, Sheet 129 s
PAGE 13 B.9 Service Water System Drawings
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\ B.9.1 Service Water System A. Service Water System, Sheet No.1 B. P&ID, Flow Diagram, Service Water System, (Nuclear Steam Sunply) U.E.8C 9321-F-27223-21 B.9.2 Service Water System A. Service Water System, Sheet No. 2 B. P&ID, Flow Diagram, Service and Cooling Water (River Water and Fresh Water)
U.E.8C. 9321-F-20333-14 B.9.3 Failure Criterion for Service Water System A. Injection Mode B. Recirculation Mode C. Feedwater Mode I
B.9.4 UM: Service Water Pump
) A. SWP31
! B. Westinghouse #500B971 Wiring Diagram, Sheet 33 C. SWP32
.D. Westinghouse #500B971 Wiring Diagram, Sheet 42 E. SWP33 F. Westinghouse #500B971 Wiring Diagram, Sheet 44
- G. SWP34 H. Westinghouse #500B971 Wiring Diagram, Sheet 76 l I. SWP35 J. Westinghouse #500B971 Wiring Diagram, Sheet 34 f K. SWP36 L. Westinghouse #500B971 Wiring Diagram, Sheet 89
PAGE 14 M. SWP37
@ N. Westinghouse #500B971 Wiring Diagram, Sheet 205
- 0. SWP38 P. Westinghouse #500B971 Wiring Diagram, Sheet 206 Q. SWP39 R. Westinghouse #500B971. Wiring Diagram, Sheet 207
PAGE 15 B.10 Pressure Operated Relief Valve Drawings B.10.1 Primary Pressure Relief Paths B.10.2 Switch to PORY Select Mode Unit Model B.10.3 Pressurizer Pressure Instrumentation and Control B.10.4 Channel Select Switch Unit Model e
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PAGE 16 B.11 Instrumen_t Air System Drawings B.11.1 Instrument Air A. Instrument Air B. P&ID, Flow Diagram, Instrument Air, U.E.8C.
9321-F-20363-19 C. Location Overlay, Instrument Air Digraph B.11.2 Instrument Air A. Instrument Air Supply to Auxiliary Feedwater B. Systems Interaction Study, Flow Diagram, Figure A-1 B.11.3 UM:. Instrument Air Compressor 31 and 32 A. Instrument Air Compressor 31 and 32 B. U.E.8C. 9321-LL-31243-8, 480 V Motor Control Center him......w.... , , , ,. ._. . .. < - , . - - - ~ + * - - -w -..g e,ww m F
PAGE 17 B.12 Lube Oil System Drawings B.12.1 Lube Oil A. Lube Oil B. P&ID, Flow Diagram, Lube Oil, U.E.8C. 9321-F-20373-8 C. Location Overlay, Lube Oil Digraph B.12.2 Boiler Feed Pump Oil Console A. Boiler Feed Pump Oil Console B. Assumed Configuration from Word Description G
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