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Category:CONTRACTED REPORT - RTA
MONTHYEARML20138J8391996-12-10010 December 1996 WPPSS Nuclear Project,Unit 2 TER on IPE Submittal Human Realiability Analysis, Final Rept ML20138J8271996-10-22022 October 1996 Technical Evaluation Rept on IPE Front End Analysis ML20138J8331996-09-30030 September 1996 WPPSS Nuclear Project Unit 2 TER on IPE Back End Analysis ML17291B1631995-08-31031 August 1995 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan:Washington Public Power Supply Sys,Nuclear Project,Unit 2 ML20071J4241994-07-31031 July 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01,WNP-2 ML17291A2631994-07-15015 July 1994 BNL Technical Ltr Rept On-Site Followup Assessment of Post- Fire Safe Shutdown Startup Issues at WNP-2, Conducted on 940620-24 ML20058L7591993-03-27027 March 1993 TER, 'Bwr Transient Analysis Model' WPPSS-FTS-129,Rev 1, for WPPSS WNP-2 ML17289A9451992-09-11011 September 1992 TER of TR WPPS-FTS-127(Qualification of Core Physics Methods for BWR Design & Analysis) for Wpps 2. ML17286A7741991-02-28028 February 1991 Technical Evaluation Rept,Pump & Valve Inservice Testing Program Wppss Nuclear Project 2. ML19332B6141989-10-31031 October 1989 Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20065C6631989-09-30030 September 1989 Final Technical Evaluation Rept on Response from WPPSS to Generic Ltr 88-01 Pertaining to Washington Nuclear Plant 2 ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20195E9271988-04-30030 April 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Washington Nuclear Plant-2 ML20151C2341988-03-31031 March 1988 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual Through Amend 4 Washington Nuclear Plant Unit 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17279A3931987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Washington Nuclear Plant-2, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 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 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 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. ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20245A4191987-03-23023 March 1987 Review of WPPSS Nuclear Project 2 SPDS, Technical Evaluation Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML20207S5231986-11-30030 November 1986 Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys 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. 1996-09-30
[Table view] Category:QUICK LOOK
MONTHYEARML20138J8391996-12-10010 December 1996 WPPSS Nuclear Project,Unit 2 TER on IPE Submittal Human Realiability Analysis, Final Rept ML20138J8271996-10-22022 October 1996 Technical Evaluation Rept on IPE Front End Analysis ML20138J8331996-09-30030 September 1996 WPPSS Nuclear Project Unit 2 TER on IPE Back End Analysis ML17291B1631995-08-31031 August 1995 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan:Washington Public Power Supply Sys,Nuclear Project,Unit 2 ML20071J4241994-07-31031 July 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01,WNP-2 ML17291A2631994-07-15015 July 1994 BNL Technical Ltr Rept On-Site Followup Assessment of Post- Fire Safe Shutdown Startup Issues at WNP-2, Conducted on 940620-24 ML20058L7591993-03-27027 March 1993 TER, 'Bwr Transient Analysis Model' WPPSS-FTS-129,Rev 1, for WPPSS WNP-2 ML17289A9451992-09-11011 September 1992 TER of TR WPPS-FTS-127(Qualification of Core Physics Methods for BWR Design & Analysis) for Wpps 2. ML17286A7741991-02-28028 February 1991 Technical Evaluation Rept,Pump & Valve Inservice Testing Program Wppss Nuclear Project 2. ML19332B6141989-10-31031 October 1989 Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20065C6631989-09-30030 September 1989 Final Technical Evaluation Rept on Response from WPPSS to Generic Ltr 88-01 Pertaining to Washington Nuclear Plant 2 ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20195E9271988-04-30030 April 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Washington Nuclear Plant-2 ML20151C2341988-03-31031 March 1988 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual Through Amend 4 Washington Nuclear Plant Unit 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17279A3931987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Washington Nuclear Plant-2, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 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 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 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. ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20245A4191987-03-23023 March 1987 Review of WPPSS Nuclear Project 2 SPDS, Technical Evaluation Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML20207S5231986-11-30030 November 1986 Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys 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. 1996-09-30
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20138J8391996-12-10010 December 1996 WPPSS Nuclear Project,Unit 2 TER on IPE Submittal Human Realiability Analysis, Final Rept ML20138J8271996-10-22022 October 1996 Technical Evaluation Rept on IPE Front End Analysis ML20138J8331996-09-30030 September 1996 WPPSS Nuclear Project Unit 2 TER on IPE Back End Analysis ML17291B1631995-08-31031 August 1995 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan:Washington Public Power Supply Sys,Nuclear Project,Unit 2 ML20071J4241994-07-31031 July 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01,WNP-2 ML17291A2631994-07-15015 July 1994 BNL Technical Ltr Rept On-Site Followup Assessment of Post- Fire Safe Shutdown Startup Issues at WNP-2, Conducted on 940620-24 ML20058L7591993-03-27027 March 1993 TER, 'Bwr Transient Analysis Model' WPPSS-FTS-129,Rev 1, for WPPSS WNP-2 ML17289A9451992-09-11011 September 1992 TER of TR WPPS-FTS-127(Qualification of Core Physics Methods for BWR Design & Analysis) for Wpps 2. ML17286A7741991-02-28028 February 1991 Technical Evaluation Rept,Pump & Valve Inservice Testing Program Wppss Nuclear Project 2. ML19332B6141989-10-31031 October 1989 Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20065C6631989-09-30030 September 1989 Final Technical Evaluation Rept on Response from WPPSS to Generic Ltr 88-01 Pertaining to Washington Nuclear Plant 2 ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20195E9271988-04-30030 April 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Washington Nuclear Plant-2 ML20151C2341988-03-31031 March 1988 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual Through Amend 4 Washington Nuclear Plant Unit 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML17279A3931987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Washington Nuclear Plant-2, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 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 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 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. ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20245A4191987-03-23023 March 1987 Review of WPPSS Nuclear Project 2 SPDS, Technical Evaluation Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML20207S5231986-11-30030 November 1986 Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys 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. 1996-09-30
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20138J8391996-12-10010 December 1996 WPPSS Nuclear Project,Unit 2 TER on IPE Submittal Human Realiability Analysis, Final Rept ML20138J8271996-10-22022 October 1996 Technical Evaluation Rept on IPE Front End Analysis ML20138J8331996-09-30030 September 1996 WPPSS Nuclear Project Unit 2 TER on IPE Back End Analysis ML17291B1631995-08-31031 August 1995 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan:Washington Public Power Supply Sys,Nuclear Project,Unit 2 ML20071J4241994-07-31031 July 1994 Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01,WNP-2 ML17291A2631994-07-15015 July 1994 BNL Technical Ltr Rept On-Site Followup Assessment of Post- Fire Safe Shutdown Startup Issues at WNP-2, Conducted on 940620-24 ML20058L7591993-03-27027 March 1993 TER, 'Bwr Transient Analysis Model' WPPSS-FTS-129,Rev 1, for WPPSS WNP-2 ML17289A9451992-09-11011 September 1992 TER of TR WPPS-FTS-127(Qualification of Core Physics Methods for BWR Design & Analysis) for Wpps 2. ML17286A7741991-02-28028 February 1991 Technical Evaluation Rept,Pump & Valve Inservice Testing Program Wppss Nuclear Project 2. ML19332B6141989-10-31031 October 1989 Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20065C6631989-09-30030 September 1989 Final Technical Evaluation Rept on Response from WPPSS to Generic Ltr 88-01 Pertaining to Washington Nuclear Plant 2 ML20248E2121989-08-16016 August 1989 Notification of Contract Execution,Mod 16,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20248E2191989-08-16016 August 1989 Mod 16,reflecting Return of Equipment to Tva,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20247R3851989-05-16016 May 1989 Notification of Contract Execution,Mod 15,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn,For Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20247R3941989-05-16016 May 1989 Mod 15,extending Period of Performance,Providing Addl Work Re Training for NRC Inspectors & Supervisors,Changing NRC Project Officer & Adding TVA Project Manager & Increasing Contract Ceiling & Funding to Use of TVA Reactor.. ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20155B7391988-06-0101 June 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20155B7531988-06-0101 June 1988 Corrected Mod 1,restoring Funds That Was Deobligated & Providing Final Increment of Funding to Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee, Pilgrim & Seabrook Resident Sites ML20195E9271988-04-30030 April 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Washington Nuclear Plant-2 ML20151C2341988-03-31031 March 1988 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual Through Amend 4 Washington Nuclear Plant Unit 2 ML20150D9001988-03-17017 March 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20150D9091988-03-17017 March 1988 Mod 1,deobligating Funds from Total Obligated Amount of Contract & to Correct FIN Number,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20149F1691988-01-11011 January 1988 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20149F1311988-01-11011 January 1988 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee & Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20236T7461987-11-24024 November 1987 Mod 7,extending Period of Performance Through 880930,adding Addl GE Simulator to Contract & Scheduling Four Simulator Courses Through FY88,to Dresden & Perry Simulator ML20236T7371987-11-24024 November 1987 Notification of Contract Execution,Mod 7,to Dresden & Perry Simulator. Contractor:Ge ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P2181987-08-10010 August 1987 Mod 1,increasing Total Amount of Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee, Pilgrim & Seabrook Resident Sites ML20236P2051987-08-10010 August 1987 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Bell Telephone Co ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML17279A3931987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Washington Nuclear Plant-2, Informal Rept ML20214R1561987-05-29029 May 1987 Mod 12,providing Incremental Funds & Increasing Ceiling,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20214R1481987-05-29029 May 1987 Notification of Contract Execution,Mod 12,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. 1996-09-30
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l EGG-EA-5230 APRIL 1933 AUDIT OF THE EtiVIRONMEllTAL QUALIFICATI0fl 0F SAFETY-RELATED j ELECTRICAL EQUIPMENT AT THE WASHIflGTON PUBLIC POWER SUPPLY SYSTEM, NUCLEAR PROJECT NUMBER 2 Q. R. Decker E. R. Holloway Idaho National Engineering Laboratory Operated by the U.S. Department of Energy
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.%g'ig y;.7 This is an informal report intended for use as a preliminary or working document Prepared for the U.S. NUCLEAR REGULATORY COMMISSION Under DOE Contract No. DE-AC07-761001570 FIN No. A6415 P Jl ~
8501180282 840524 /# N %~.-.I"JE.p =2 Idaho PDR FOIA WILLIAM 84-262 PDR
EGG-EA-6230 I
AUDIT OF THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT AT THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NUMBER 2 Q. R. Decker E. R. Holloway Published April 1983 EG&G Idaho, Inc.
Idaho Falls, Idaho .83415 Prepared for the U.S. Nuclear Regulatory Commission
'. Washington, D.C. 20555 Under DOE Con e o -AC07-761001570
ABSTRACT EG&G Idaho, Inc., and NRC Staff members conducted an onsite audit of the Washington Public Power Supply System Nuclear Project Number 2 to determine the environmental qualification of safety-related electrical
- equipment. Results of the audit are summari
- ed in this report.
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l NRC FIN No. A6415--Equipment Qualification Case Reviews .
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FOREWORD This report is supplied as part of the " Equipment Qualification case Reviews" being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Engineering, Equipment Qualification Branch, by EG&G Idaho, Inc., Reliability and Statistics Branch.
The U.S. Nuclear Regulatory Commission funded the work under tne authorization B&R 20-19-40-41-2.
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SUMMARY
On February,15, 16, and 17, 1983, a team composed of representatives of the Reliability and Statistics Branch of EG&G Idaho, Inc., and the Nuclear Regulatory Commission Staff conducted an audit of the Washington Public Power Supply System Nuclear Project Number 2 (WNP-2). The purpose of the audit was to determine compliance of the environmental qualification of safety related electrical equipment with NRC approved regulations1 and standards.2 Work efforts consisted of: (a) a pre-audit review of the licensee's environmental qualification submittal,3 (b) an audit of the licensee's central files for selected equipment items, and (c) a visual inspection of the audited equipment items. It was concluded from the aucit that the applicant must supply additional information to the staff before a determination of acceptability can be made.
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CONTENTS ABSTRACT ............... .................................. .. . .. ii FOREWORO ......................................................... .. iii
SUMMARY
.................................................. ......... . iv
. 1. INTRODUCTION ..................... ........................... ... 1
- 2. EVALUATION .................................................. .... 2
- 3. CONCLUSIONS ..................................................... 3
- 4. REFERENCES ..........................................'........ .... 4 APPENDIX A--SUMMARIES OF WNP-2 CENTRAL FILE REVI EWS . . . . . . . . . . . . . . . . . . . 5 APPENDIX B--EQUIPMENT QUALIFICATION CONCERNS AND COMMENTS .... .. ..... 10 APPENDIX C--EQUIPMENT QUALIFICATION STATUS ............................ 12 6
V I
t AUDIT OF THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT AT WNP-2
- 1. INTRODUCTION On February 14, 15, and 16.~1983, a team composed of representatives of the Reliability and Statistics Branch of EG&G Idaho, Inc., and the Nuclear Regulatory Commission Staff conducted an audit of tne environmental cualification of safety related' electrical equipment at WNP-2. Tne effort consisted of: (a) a pre-audit review of the licensee's environmental qualification submittal, (b) an audit of'the licensee's central-files for selected equipment items, and (c) a visual inspection of the equipment items for which the central files were audited. Summaries of the central file reviews are provided in Appendix A. Qualification concerns anc comments for individual equipment items are provided in Appendix B.
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- 2. EVALUATION
, General areas of concern which remain as a result of both the audit and the pre-audit review are as follows:
- 1. A large number of items were qualified by analysis only. .
Supporting data were limited to manufacturer's specifications extended to show operability at more severe operating conditions.
- 2. Similarity between installed equipment and equipment tested was not evident in several cases.
- 3. Interfaces were not adequately addressed in that the test conditions did not simulate the actual installed conditions.
- 4. The following additional information is needed to resolve deficiencies noted in the qualification program:
- a. The effects of beta radiation on equipment,
- b. The effects of low level radiation on solid state devices,
- c. The schedule for unqualified equipment replacement, i
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, d. Justification for interim operation, and '
- e. A general description of the maintenance and surveillance program to be used to maintain qualification.
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- 3. CONCLUSIONS As a result of the audit it was concluded that the WNp-2 environmental qualification program is incomplete. Additional information must be supplied to the staff before a determination of acceptability can be made.
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- 4. REFERENCES 1.
Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, NUREG-0588.
- 2. IEEE-Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 323-1974.
- 3. WNP-2 NUREG-0588 Environmental Equipment Qualification Report.
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APPENDIX A SUMMARIES OF WNP-2 CENTRAL FILE REVIEWS s
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APPENDIX A SUMMARIES OF WNP-2 CENTRAL FILE REVIEWS Magnetrol Lev'el Switch. Model No. 3.5-751-1X-mpg-M14HY Tag No. HpCS-LS-2A,8 These switenes are part of the high pressure core spray (HPCS) system and are located in the Reactor Building at elevations of 465 and 468 feet.
They are actuated on a high suppression pool level to provide HPCS valve control.
The specified accident parameters are: temperature, 220*F; pressure, 15.1 psia; relative humidity, 100%; radiation, 7 x 105rads TID; and operability time of 24 hours.
Environmental testing has been performed on a similar level switen Model #8CS-751-EP/VPX-SIMD4DC and is reported in Wyle test report 43235-1.
The maximum environmenta'l test parameters are: temperature, 300*F; relative humidity, 100%; radiation 4.4 x 104 rads TID; and operability, 160 hours at 300*F and 480 hours at 100*F during which >10,000 onhff cycles were performed.
The specified radiation is not enveloped by the test, however, the applicant used " threshold levels" to show that the switch materials are not susceptible to radiation damage up to 2 x 106 rads TID. The switch was not aged prior to testing. The applicant used Arrhenius methodology and data from the "IEEE Transactions on Power Apparatus and Systems," May 1969 and referenced a manufacturer's data sheet, describing aging of Viton 0-rings, to calculate an estimated life of'40 years.
5 The qualification file did not contain the following: (1) maintenance and surveillance requirements, (2) aging data for the Viton 0-rings, and (3) a complete test report. The Wyle test report recommended maintenance:
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at 1 and 5 year intervals to maintain an estimated life of 40 years, nowever, tne applicant statec that maintenance and surveillance were not required to maintain a 40 year estimated life.
In conclusion, the qualification file for the Magnetrol level switen did not contain sufficent documentation to support a 40 year qualified life. .
Westinghouse Low Voltage penetration. Model No. 55-00-0002, TAG #E-X-100A. 107A. '
These penetrations are located in containment at elevations of 507 and 475 feet and are used to provide sealed electrical penetrations thru containment. The specified accident parameters are: temperature, 320 F; pressure, 32 psig; relative humidity, 100%; radiation 7.0 x 107 rads TIO; chemical spray, demineralized water; and operability time, 6 months.
Environmental testing ha: been performed on a similiar penetration and is reported in Westinghouse report PEN-TR-75-6. No preaging was performed anc radiation was not enveloped. The maximum environmental parameters to which the penetration was subjected are: temperature, 340*F; pressure, 52 psig; relative humidity, 100%; radiation, 4.45 x 10 7rads TIO; and operability time, 6 hours at 340*F,18 hours at 280*F, 6,576 hours at 302 F. The penetration was not tested for spray, but the installed penetrations are shielded from spray by NEMA 4 enclosures. Radiation analysis reported in Westinghouse report PEN-TR-81-58, was performed to show that the materials in the penetration supplied to WNP-2 was not susceptible to radiatica damage below 1.2 x 108 rads TIO.
Report No. 75-785-BIGAL-R2, " Predicting the Thermal Life of Modular Penetrations," May 27, 1975 by J. F.. Quirk was used to demonstrate, for pressure integrity only, an estimated life of 40 years for the low voltage I modular penetrations. Similarity of penetrations covered by this report to those installed at WNP-2-was not established. ;
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In conclusion the low voltage penetration can not be qualified to tne specified environment unless similarity can be establisned between :ne aged penetrations and those installed at WNP-2, electrical functions are shown to be adequate for the aged penetrations, and a surveillance program to assess age degradation is es'tablished.
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Raycnem Electrical Cable Model Flamtrol Insulation With Cross-Linked Polyolefin Jacket This cable is used throughout WNP-2.
The specified accident parameters are: temperature, 320 F; pressure 32 psig; relative humidity,100%; chemical spray, demineralized water; 7
radiation, 7.0 x 10 rads TID; and operating time, 6 months.
Environmental testing has been performed on similar cable and is reported in Franklin Institute test report F-C4033-1 and Raychem test reports EM 1237 and EM 1403. The maximum environmental parameters to wnich the tested cable were exposed are: temperature, 357*F; pressure, 70 psig; relative humidity, 100%; chemical spray, 10.5 pH; radiation, 2 x 100 rads TID; and operating time, > 6 months using test and analysis. The cable was aged for 7 days at 302 F, and a life of > 40 years at 150 F was-calculated using the Arrhenius methodology.
It is concluded the Raychem electrical cable.is qualified for the specified environment. Documentation to support this conclusion is contained in the applicant's qualification file.
Static-0-Ring Pressure Switch, Model % . 12N-A55-X10TT and 12NA55-X1051TT, Tag Nos. MS-PS-47 A,B,C,0 and MS-PS-48 A,B,C,0.
These pressure switches provide high drywell pressure signals anc are
- ' located in the reactor building at elevations of 526, 527, 535 and 575 feet.
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The specified accident parameters are: temperature, 130 F; pressure 14.7 psia; relative humicity,100%; radiation,1.5 x 105 rads TID; and operability time of 24 hours.
Environmental testing has been performed on this type of pressure switch and is reported in Viking Laboratories, Inc. test report 30203-2, _
November, 1973. The maximum environmental parameters to which the switch was subjected are:
temperature, 212 F; pressure,15.3 psia; humidity, 100%; and ope ;bility time of 8 hours, extended to >6 months by analysis. Accuracy of the switch was determined to be 9.7 Full Scale Percent Error (FSPE), no accuracy had been specified by WNP-2.
Radiation testing and thermal aging were done by analysis only.
Analysis indicates the switches can withstand radiation up to 6
1.5 x 10 rads TIO, and the estimated life, calculated by the Arrhenius methodology, was 16 years at a service temperature of 104 F.
It is concluded that the Static-0-Ring pressure switch is qualified for the specified environment provided maintenance and surveillance procedures are followed. The required accuracy of the switches must also be specified by the applicant.
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APPENDIX B EQUIPMENT QUALIFICATION CONCERNS AND COMMENTS
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AFPENDIX B EQUIPMENT QUALIFICATION CONCERNS AND COMMENTS
- 1. Several pieces of equipment are listed in the Master Equipment
* ~ List (MEL) but not in the Equipment Qualification Reports (ECRs) and vice versa.
- 2. In some instances a qualified life has not been determinec nor maintenance / surveillance programs developed. In these instances, however, the applicant considers the items to be qualified.
- 3. Items which are safety related as pressure boundaries only are listed as qualified with no data given.
- 4. There are many equipment items for which the MEL and *.he EORs disagree concerning the qualification status.
- 5. In some cases a qualified operating time is claimed even when the specific equipment testing has not yet been completed. Example:
Page 5, Appendix C.a
- 6. EQR's do not always list required accu.acy values.
- 7. In most cases the specified operating time is 6 months with qualified operating time listed as >6 months. The adequacy of time margin cannot be determined in these cases.
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-a. WNP-2 NUREG-0588 Environmental Equipment Qualification Report.
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APPENDIX C EQUIPMENT OVALIFICATION STATUS 8
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APPENDIX C EQUIPMENT QUALIFICATION STATUS The following table lists the equipment included in the applicant's EQRs. The applicant's evaluation of the equipment and the reviewer's comments are included.
WNP-2 Status Codes:
A -
Acceptable, thermal aging completed B -
Acceptable, thermal aging being covered by surveillance D -
No documentation in files G -
Being requalified by modification of the hardware or the environment M -
Being requalified by analysis N -
Not acceptable, requalification method not yet cetermined NS -
No WNP-2 evaluation catagory stated P -
Purchasing qualified replacement Q -
Qualified R -
Not reviewed T -
Being requalified by test
/ -
Indicates disparity between MEL/EQR.
Reviewer's Comments:
A -
Aging deficiency AA -
Aging done by analysis only AAA -
Accuracy deficiency AH -
Acceptable for Non-HELB use
. CS -
Chemical spray deficiency H -
Humidity deficiency
., HSE -
Humidity by separate effects ME -
Mild environment questioned 17
M -
Margin deficiency I -
Incomplete qualification documentation MR -
Margin on radiation deficient ND -
No data provided ,.
NQ -
Not qualified NR -
Harsh environment qualification not required , ,
OE -
Operating experience used in qualified life determination OT -
Demonstrated operating time is deficient P -
pressure ' deficiency P90 -
Equipment is qualified as a pressure boundary only Q -
Qualified R -
Radiation deficiency RA -
Radiation done by analysis only S -
possible surveillance / maintenance program deficiency SE -
Separate effects testing used T -
Temperature deficiency TA -
Temperature by analysis only TM -
Temperature margin deficiency TRA -
Test report applicability is questioned Systems List:
CAC -
Cont 41nment atmosphere control system CEP -
Containment exhaust purge system CIA -
Containment instrument air system CMS -
Containment monitoring system CRD -
Control rod drive system CSP -
Containment supply purge system E -
Electrical system EDR -
Equipment drains radioactive system l FOR -
Floor drain radioactive system -
FDC -
Fuel pool cooling system HPCS -
High pressure core spray system -
IRM -
Intermediate range monitor l
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i LO -
Leak detection system
- LPCS - Low pre;sure core spray system MS -
Main steam (nuclear) system
. MSLC - Main steam leakage control system PI -
Process instrumentation system RCC- -
Closed cooling water system RCIC - Reactor core isolation cooling system REA -
Reactor building exhause air (HVAC) system RFW -
Reactor feedwater system RHR -
Residual heat removal system ROA -
Reactor building outside air (HVAC)-system RPS -
Reactor protection system RRA -
Reactor building return air (HVAC) system RRC -
Reactor recirculation system RWCU -
Reactor water cleanup system S -
Sampling system 19
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status _Co7ments items System (s) Page .
Switchgear Westinghouse 75-DilP-500 M NR9 4
E 106 Circuit Breaker ITE Imperial --
A NR 2 E 80 M A NR 2 Westinghouse E 80 24Y9836811 M NR9 4 E 82 Transformer Sorgel 122091-3/124176-12 Q AH,SE 3 Square D E 107 Motor Control ITE Imperial 5640VA, 8, C-111 A,B NR 4 E 101 Center A NR 3 E 100 n, Electro flydraulic ITT General Nil 91 & NH95 T A 24 c) Operator CAC/SGT 5, 322 Motor Operator Limitorque SMB A Q IC CR0 62 SMB-000-5/P48 A Q 3 CIA 31 SMB-000-5/056A A Q 8 CAC 17 SMB-000-5 A Q 3 FPC 122 SMB-00 SMB-000 P ND 6 FPC 124 SMB-000-25/P128 A Q 1 IIPCS 135 SMB-2-40/C184Y A -J 2c IIPCS 136 SH8-2-60/C184Y SMB-3 A -J 2c ilPCS 136 SMB-4 A -J Ic IIPCS 137 SMB-0-40/156 A Q 3C LPCS 151 SNB-000-3/K48 SMB-3-60/18AR
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APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status Conwents Items System (s) Page Motor Operator SMB-3-100/254UR3 A Q 1 LPCS 153 (continued) SMB-00-7.5/L56 A OT I MS 170 SMB-000-5/056A A M 1 MS 172 SMB-000-5/ A M 4 MS 174 SMB-000-5/P48 A TM 12 MSLC 187 SMB-04-3/42 A 0 4 MSLC 189 SMB-0 P ND RCC 1 205 SM8 A Q 3 RCC 206 SMB-0-15/M56 A Q 2 RCC ~ 208 SMB-0-10/L56 P H.R.CS,P,T I RCC 210 SMB-0-40/0202G A Q 2 RCIC 215 SMB-2-80/052248 SMB-000-P56 R ND RCIC 1 217 SMB-00-15/RS6 A P,0T RCIC Dj 1 218 SMB-2-60/0215R2 A Q l RCIC 220 SMB-015/DTS6F A Q l RCIC 222 SMB-000-5 A SM8-000-5' Q 3 RCIC 224, 229 A/R NO 1 RCIC 225 SM8-00-7.5/056C A Q 1 RCIC 226 SMB-4-250/3260R4 A T,SE 2 RFW 238 SMB-000-5/K48 8 Q 2 RilR 252 SMC-04-5/42 A Q 4 RilR '254 SMB-04-5 A Q 2 RilR 256 SMB-2-80/C215Y A Q 4 RllR 258 SMB-3-80/213R3 A Q l RilR 260 SMB-0-15/056F A Q 2 Rim 262 SMB-000-2/056AA SMB-3-80/213R3 A Q 2 RllR 264
4 APPENDIX C - EQUIPMENT QUALIFICATION STATUS Nurnber Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments items System (s) Page MotorOpe) SMB-00-7.5/L56 A (continued tor SMB-1 40/T56 A Q
Q 10 2 RHR 266 RHR 268 SMB-3-150/256VR3 SMB-0 40/T56 SMB-00-10/L56 A Q 4 RHR 270 -
SMB-3-80/213R3 SMB-000-5/K48 A Q 1 RHR 272 SMB-0-25/RS6 SMB-2-60/215RZ A Q 4 RHR 274
!MB-000-5/48 A Q 3 RHR 276 SMB-0-40/T56 A Q 2 RHR SMC-04-5 278 A Q 4 RHR 280 SMB-2-80/052248 A Q 1 RHR no 282 to SMB-00-10/L56 A Q 2 RllR SMB-2601215R2 284
??/R NO 1 RilR 286 SMB-0-40/T56 A Q 2 P' k 287 SMB-000-5/P48 A TM 2 RHR SMC-04 289 A SE 2 RRC 307 SMB-2-25 Aa P80 1C RRC 309 SMB-0-25/R56 A Q 1 SMB-0-25/DK56H RWCU 313 A Q l RWCU 315 SM8-0-25/RS6 A Q 1 RWCU 317 SMB-00-10/P56 A Q 14 SGT 328 SMC-04-5/42 A Q 5 SW 358 P NO 2 SW 360 M/R NO 4 SW 357 L
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments items System (s) Page Solenoid Pilot Marotta MV229MQ-52 T --
34 CIA 40A Valve ASCO HVA-103-632 B A,0E P,ll 2 CR0 69C HVA-904052-J AC A,0E ,P,Il 370c CR0 690 llBX8320A1 B A,RA,0E,ll 7 R0A 299 HTX8320A20 Pn ND 16C MS 698, 183 WJitT8316E35F M A,RA,0E,il 2 R0A 301, 302 WJHT831654 8 A,0E,II,RA 2 EDR ll2A B A,0E,H,RA 2 FDR ll3A A A.R RA,M 1 FPC 125A B A,RA,0E,Il 2 RCIC 232 MB A,RA,0E,ll 6 REA/RFW 237, 240 0 Q 8 CEP 30A WJHT836A74 ABd A,0E,RA,ll 13 CSP 76A m 821002M0 Pk ND 2 w SGT 335 821102M0 B A,RA,0E,H 6 SGT 336 HVA1709662A B A,0E , P,Il 740c CRD 69F R ND y4c MS 182 Snlenoid Valve Marotta MV229MS-L2 T A.RA,TH M 4 SW 365 MV229MQ-L2 A A RA,lM,0T 4 SW 366 MV36RP-il3 T Nk 5 RilR 296 MV250-4 NS/T --
1 CAC 28A T --
2 CIA Borg Warner SIA 81560 D ND 2 RRC 311 Root Valve Target Rock 1021010 A A 12 PI 201 A A 2 PI 203 Valve & Trigger Conax 1832-159 R A 2C Assemlily SLC MS
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments items System (s) Page Valve GE Pl36B13026002 R ND Sc TIP -
367 Fan Motor Westinghouse 75D42473 A AA 2 CAC 13 TBDP A RA,AA 4 SGT 326 Reliance --
M NP/TRA 19 CRA 52 Motor Westinghouse 7504786 8 A.SE M Ic HPCS 134 75D40786 B A SE M IC RHR 251 TADP/326TS P Hb 2 FPC 121 SBFC,TBFC,TBAN,7BFC Ba A.SE.M 15 RRA 304 TBFC/76056668 Be A SE.M 1 MSLC 186 SK357XC10A A --
IC HPCS 133 6347XC65A A --
IC LPCS 150 n, SK6339XC122A A AA,TM 3c RHR 250 SK324AK2120/324T M A,0T,R,NQ 2C SLC 345 Electronic Bailey 9T66Y987 A/B --
4 CAC Power Supply 2 298 Contactor ITE imperial A1020202 M 2 CAC 1 Mean Square ITE Imperial 5641 A NR 2 E 97 Voltage Device Electropneumatic GE 15887013P7 Converter D ND Ic CRD 57 Resistance / Bailey 50-740320CAAA1 A/B NR 2 CAC Current Converter 18 Relay ASEA RA 225-052-CP T ND 8 CAC 19 RK225-052-CP T ND 2 CAC 20 RK225-52-CP,EP T ND 9 MSLC 197 RK223067-EP Ta ND 16 MSLC 193 RR223067-EP T ND 1 M5LC 199 RX0MH2-069EP 1 ND 2 MSt C 196 RSMH2-RK223-067-EP T ND 1 MSLC l *Ja t
. s'. ,
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments items System (s) Page Relay (continued) Struthers-Dunn 219BBXP A NR 93 CSP /E/SW 75, 103, 363 219XBXP M/D --
2 CIA 40 219XDXP T ND 1 MSLC 195 R.B. Denison WE-74/EX-2 A NR 11 Allen Bradley CSP 76 700N400Al,700N600A1, B AH 23 SGT 332 7004N800Al Agastat 7012AD,AH A/B A,ME 4 CAC 21 Time Delay 7012AE Be A 13 MSLC 200 Relay 7012AH A/B A PE 2 CAC 22 ro Cable Raychem Various Qe,r Q 27 E 83 Rockbestos Various Q'*F Q 7 Okonite E 88 Various Ae Q 4 E 86 H,02 2 Beckman 70,755 A NR,ND 2 Analyzer CMS 42 Conductivity Beckman CEL-IT-(SS),etc. 8 PB0 Element 2c RHR 241 Radiation GE 807E162TC D/R ND 4c SRM 353 Detector Voltage Amp' GE 112C2276G001 D ND 4c SRM 354 DP Indicator GE 13722,13733 Ne ND 2c CR0 54 DP Indicator / Fisher Controls --
A PB0 1 FPC 114 Controller
__ - ._ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ - - _ _ . - _ _ . ._--_ _ .-_ _ _ = _ .
APPENDIX C - EQUIPMENT QUALIFICATION STATUS
' Number-Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments Items System (s) Page DP Indicating Barton 288 Be A Switch 2C CR0 55 A A,SE 2c LPCS/MS 147 A A,SE 7c RHR 288A 242 A AA 3 CSP 70 A A.SE 8C MS 159 288/288A A A,SE 8c MS 158 288A A RA,A.SE IC HPCS 128 A PB0 2 FPC DP Switch 116 288A A A,SE 4c RCIC 212 DP Transmitter Barton 368 M A,R 2c CR0 56 386 A OE A 4 GE CAC 17 C555011NAA4WCA 8 P80 1c Q3 Rosemount MS 160 1151 8 A,SE 8c REA 233 Flow Indicating Bailey 50-701003AAAA1 A/B NR Controller --
2 CAC 7 P ND 1 FPC 116A Flow Indication Barton 289 A RA,A,$E Switch Ic HPCS 129 289A A 289 A.SE Ic LPCS 148 A A,SE 3c RilR 243 Flow Switch Moore DCA/4-20 MA/D-X2-X3 A/B NR 2 CAC 8 P ND 2 SGI 323 Flow Rosemount 1151 8 SE,A 9 Transmitter CAC,5W 9, 355 1151DP5022T000lP8 Be SE,A 2c CRD 58 Qr AAA,I 4c SGT 324 1153 P ND 2 FPC 117 1153 P ND 4 Barton MSLC 185 386 A OE,A Bailey 8 CAC 10, 12 555111 etc. P ND 3c RilR GE 245 555111 etc. 8 PB0 3 RWCU 312 50-555-11 etc. P ND 2c HPCS/LPCS 130, 149 50-555-11 etc. A PB0 24 f *C 50-555-11 etc.
MS/RHR 161, 244 D ND Ic SW 356
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Equipment Number WNP-2 Reviewers of Description Manufacturer Model Status Connents Items System (s) Page Level Barton 289A A A SE M 8 FPC 118 Indicating 288Aa A A,$E 14C Switch Yarway 4418C MS 163, 165 A A.RA,M 4c MS 164 Level Barton 760 M/D ND 6C MS Indicating 166 Transmitter Switch Level Switch Moore DCA/4-20 MA/D-XI-X4 A/B NR 2c CAC 11 Magnetrol 5.0 - 751 8 AA,M 6C CRD 60 3.5 - 751-1X etc.r g S,g 2c itPCS 132 751 - SPX-M14 A A,RA 8 RilR n, -- 248 0 ND 6 FDR
-a -- --
113 M/R ND 2 FPC 119 Level Transmitter Barton 352/358 M/D ND 2 RilR 249 Magnetrol TSI-IX-MFG-M1411Y D ND Ic CMS 43 Rosemount 1151-DP4022T003PB B A,SE IC CMS 44 Bailey 555 P" ND IC MS 169 GE 555 NS ND IC SLC 344 R ND 1 FPC 120 Moisture Sensor Panametrics M2R-600-09A D/P ND 5 CMS 45 Moisture Panametrics 600-M26E D/P ND 5 CMS 46 Transmitter Pressure GE -
-e P80 IC MS 176 Indicator Pressure Barton 288A A,SE Irulicating A Ic HPCS 139 Robert Shaw SP-222-0 Switch --
M ND Ic tPCS 155 A P80 2C RHR 291 Stat ic-0-R ing SN-AA3 A A.RA,R 8C RHR 292, 293 i
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments items System (s) Page Pressure Switch Moore DCA/4-20MA/D-X2-X3 A/B NR 2 CAC 16 Barton 288 A/B AA 2 CIA 34 288,288A A A,SE 16 MSLC 191 288 M A SE Ic LPCS 156 Mercold DAW-7023-804 A PE0 2 CIA 37 Static-0-Ring SN A A,RA 8c flPCS/RilR 140, 141 6N-AA21-X3VTT Be A 2c CRD 68 12N-AA5,4 A A,RA 4c RPS 303 12N-AAS-X10TT/a,r Q S AAA Sc g3 179 X1051TT Barksdale BIT-Gil32SS B A 185C CRD 64 BIT-M12SS Q/Bf r AAA,1 llc MS 177 82T-M12SS/02T-MIS 0SS A A,M 4 FPC 124A N
- 82T-M1255 A A.RA Ic RRC 310 P111-M340SS-V A A,RA IC LPCS 157 Pill-M85SS-V B A.RA 4c RCIC 231 Beckman A900-20COEAA-20 M/0 ND 4 SGT 331 Asco SCllAP/GT10A44R A A,0T 2 SW 361 SB11AKR/TG-1032 A PB0 2 CIA 35 SCllABIGIO B PB0 1 CIA 36 ,
Pressure Rosemount 712203 B A SE IC Transmitter CIA 38 556110EAAAIWEN Pm NO IC SLC 346 1151GP7A22T0003PB B A,SE 2c CIA 39 1151GP4A22MBGE3 8 A SE 8c CMS 47 1151GP9A22MBGE3 B SE,A,M Sc MSLC 192 Bailey 556 P ND IC CR0 69 KG556110EAAA1 P PB0 Ic CR0 69A 556 P ND* 2c MS 180 P NR 2c RilR 294 O
G e g
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer- Model Status Comments Items System (s) Page Radiation GE 237x731G001 D/R ND 4c g5 jgj Element 11781681G001 D ND 2C SW 362 P ND 2 CMS 49 Reuter-Stokes RS-CA-1606-203 0 ND 2 CMS 50 Electric D ND 1 REA- 236 Radiation GE 112C2276G001 --
NR 2c SW 364 Transmitter Temperature Thermoelectric 30500b ,d gr Q 12 CAC 24 Element --
A P80 14 CAC 23/25 flyCal Engineering TC-Il3X-T-A-24-3 N/R ND- 7 CMS 51 D/R ND 24 SPTM 350 C$ Pyco 282-NIA72 M OT.A.TRA,P, 28c LD 143 Tk 13309679P001 M ND 18c gg jg4 NECI N145C3224P1 M ND 21C LD 145 117C3485P022 M ND- 6c RHR 295 Fenwal 21110-0 M/R ND 6 SGT 337 Melton 5641-R-DACAR H ND 4 LD 142 D ND 3 FPC 126 Temperature Bailey 50-701003AAAA1 A/B NR 2 CAC 26 Indicating Controller -- --
D ND 3 FPC 127 Temperature Moore RBA/3W-400/D-X1-X4d A/B NR 10 CAC 27 Switch 18000-0 B 11 71 SGT 339 K idde, Walter CSD-3(A) N/P ND 6 SGT 338
9 APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Uescription Manufacturer Model Status Comments Items System (s) Page Temperature Bailey 740 D/P 2 Transmitter CAC 28 Limit Switch -- --
R/P ND RCIC Namco 1 214 EA74080100/EA1703100 B A,RA 4 CEP 29 EA1703100 B NR Ic RilR 247 EA74080100/EA1703100 A Q 4 CEP 30 74080100 A M 4 02400X REA/SGT 235, 325 B AA RA TRA 7 CSP 71, 72 sal-133 R/PO ND 1 RCIC 213 84836-0577 P ND 1 HPCS l 131 EA700-86010 P* ND 24c MS 167, 168 70050100 PP ND 8 R0A 297 c$ Position Switch Namco 1703100 P ND 11c Micro-Switch RHR 246 BZE6-2RN72 B AA RA,TA 390c CRD 63A, 63C Electric GE 2D433G3,20507G140 D ND 2c Heating SLC 343 Chromalox SA213-T347S5 A AA 2 CAC 4 Coll 27-47499 A AA 4 SGT 321 Control Panel Air Products P-2040,1 A NR 2 E 95 A NR 1 E 96 Hanual/ Auto --
NRe NR 2C CR0 61 Station Remote Manual GE CR2940 B NR 1C SLC 347 Switch CR2940 M PB0,H.R.A.M 6 RRA 306 B NR 12 SGT 335 P ND 2 FPC 125
~
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers' of '
Description Manufacturer Model Status Comments items System (s) Page Moisture Control 'llygrometrics XMA/C-103 B A ,il 8 SGT 327 System Moisture Element flygrometrics XMA-103 Ba NR 24 SGT 341 Motor Starters ITE Imperial .Various. A NR E 77 133{
169 Instrument Rack GE --
A NR 28c I JELCO CRD/E 59/99 A NR 14 E 93 Power Panet Square D QM-02653-28EE6 P ND 2 E 102 Farr, Co. --
A NR 4 SGT 330 w
Sample Rack -- --
A NR 4 S 319 Connector 'Amphenol 82-503/28650 T AA,RA 8 '
E 91 0 ND 4c SRM 352 Shrink Tube Raychem WCSF-N A Q 2 E 93
. Splice AMP 34130 A NR,SE 2 E 92 Tenninal Block Curtis industries BT-17 P h
ND 4 h
E 108 HT-15 P ND 2 E 108 TRW-Cinch 27/13-541 h P ND 8 E 108 25-541 Ph ND 2 E 108 Penetration Westinghouse 55-00-00021 ,r Q TRA,S,AA 24 F 110
APPENDIX C - EQUIPMENT QUALIFICATION STATUS Number Equipment WNP-2 Reviewers of Description Manufacturer Model Status Comments Items System (s) Page Prog. Auto, and Timing 1820BLQ20XX T --
2 CIA 33 Control, Inc.
Positions Anderson, Greenwood 04-3869-001, A/R ND 18 CSP 74 and Co. 04-3869-002
- a. The Master Equipment List (MEL) disagrees with the sunnary sheets concerning manufacturer and/or model number for some of these components,
- b. The MEL Ifsts the model number for these as 80500.
- c. Includes NSSS equipment, k$
- d. Model number discrepancy between MEL and EQR.
- e. Not listed in MEL.
- f. The number of items do not agree between MEL and EQR.
- g. Harsh environment but will not fall in detrimental manner.
- h. Replace with Weidmuller Terminal Blocki.
- 1. EQR model nt:mber and qualification documentation are not the same.
J. These EQRs do not give the qualified environment.
^
- k. See Profile 17.'
- 1. Replace with Namco EA180.
l e
?
r I
APPENDIX C - EQUIPMENT QUALIFICATION STATUS m .- Replace with Rosemount DPT 11530.
- n. -Replace with HP8320A173E.
- o. Will be replaced.
- p. Replace with EA740.
... 'q. Replace with NP8316
- r. Equipmc.it. Item reviewed at plant audit. ,
'0"" '
ist 34 U.S. NUCLEAR REGULATORY COMMISSION BIBLIOGRAPHIC DATA SHEET EGG-EA-6230 4 TITLE AND SUSTITLE 2. (Leave asevel Audit of the Environmental Qualification of Safety-Related Electrical Equipment at the Washington Public 3. RECIPIENT S ACCESSicN NO Power Supply System, Nuclear Project Number 2 7 AUTHOR ($) 5. DATE REPORT COMPLE TED MONTH lvtAR
. Q. R. Decker, E. R. Holloway April 1983 9 PERFORMING ORGANIZATION NAME AND MAILING ADDRESS tincivoe I.0 Cocal DATE REPORT ISSUED
. MONTH l YEAR
. April 1983 EG&G Idaho, Inc. e ft ,,v, ,,,, , ,
Idaho Falls, ID 83415
- 8. (Leave manal
- 12. SPONSORING ORGANIZATION NAME AND MAILING ADORESS (sac /vor 2,0 Coorf
- 10. PROJECT /T ASK, WORN UNIT NO Division of Engineering Office of Nuclear Regulatory ReSearcn is ,,y so.
U.S. Nuclear Regulatory Commission Washington, DC 20555 A6415 13 TYPE OF REPORT PE RICO CQVE RE D tinclus,ve caress 15 $UPPLEVENTARY NOTES 14 Aleeve usint 16 ABSTR ACT (200 woros or less)
EG&G Idaho, Inc., and NRC staff members conducted an onsite audit of the Washington Public Power Supply System Nuclear Project Number 2 to determine the environmental qualification of safety-related electrical equipment. Results of the audit are summarized in this report.
17 KE Y WORDS AND OOCUME NT AN ALYSIS 1 73 CE SC RIPTO RS 170 IDENTIFIE RS.CPEN ENDE D TE RVS 18 AV AIL ABIL4TV ST ATEVENT 19 SE CU R i T V O L A SS
- Ta s co ort: 2Y NO 06PAdt>
Unclassified Unlimited 20 gj'h's sY[$ ^'" =
N Rc .O.u sas ,n ...}}