|
---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML20012E2671990-03-31031 March 1990 Risk Sensitivity to Human Error in the Lasalle PRA ML19332B5801989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components: La Salle-1/-2, Technical Evaluation Rept ML20058K0861989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to LaSalle County Station,Unit 2 ML20058K0921989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to Lasalle County Station,Unit 1 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 ML20042D0871988-08-0404 August 1988 Simulations of BWR Power Oscillations W/O Scram, Informal Rept ML20150A8641988-05-31031 May 1988 Pump & Valve Inservice Testing Program,Lasalle County Station,Units 1 & 2 ML20153D2101988-01-31031 January 1988 Approaches to Uncertainty Analysis in Probabilistic Risk Assessment ML20236X2871987-10-31031 October 1987 Fire Environment Determination in the Lasalle Nuclear Power Plant Control Room ML20215L9661987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2,Vendor Interface Programs for All Other Safety-Related Components, La Salle Units 1 & 2, Informal Rept ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20155D6271986-02-14014 February 1986 Mod Program Controls, Based on 860210-14 Review ML20141N6051986-01-14014 January 1986 SPDS Progress Review,Lasalle,Units 1 & 2 ML20244D3981985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.1, `Post-Trip Review:Program Description & Procedure' for La Salle County Station.. ML20134J5091985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station & WPPSS-2 ML20244D4411985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station Units 1 & 2 & Washington Nuclear Plant Unit 2. Contains Info for LaSalle ML20101G1541984-12-31031 December 1984 Conformance to Reg Guide 1.97,LaSalle County Station,Units 1 & 2 ML20076J2711983-05-31031 May 1983 Control of Heavy Loads at Nuclear Power Plants,Lasalle Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065B7131982-06-30030 June 1982 Control of Heavy Loads at Nuclear Power Plants LaSalle Units 1 & 2 ML20010E7751981-07-31031 July 1981 Audit of Environ Qualification of Safety-Related Electrical Equipment at La Salle County Station (Unit 1), Technical Evaluation Rept 1995-12-12
[Table view] Category:QUICK LOOK
MONTHYEARML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML20012E2671990-03-31031 March 1990 Risk Sensitivity to Human Error in the Lasalle PRA ML19332B5801989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components: La Salle-1/-2, Technical Evaluation Rept ML20058K0861989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to LaSalle County Station,Unit 2 ML20058K0921989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to Lasalle County Station,Unit 1 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 ML20042D0871988-08-0404 August 1988 Simulations of BWR Power Oscillations W/O Scram, Informal Rept ML20150A8641988-05-31031 May 1988 Pump & Valve Inservice Testing Program,Lasalle County Station,Units 1 & 2 ML20153D2101988-01-31031 January 1988 Approaches to Uncertainty Analysis in Probabilistic Risk Assessment ML20236X2871987-10-31031 October 1987 Fire Environment Determination in the Lasalle Nuclear Power Plant Control Room ML20215L9661987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2,Vendor Interface Programs for All Other Safety-Related Components, La Salle Units 1 & 2, Informal Rept ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20155D6271986-02-14014 February 1986 Mod Program Controls, Based on 860210-14 Review ML20141N6051986-01-14014 January 1986 SPDS Progress Review,Lasalle,Units 1 & 2 ML20244D3981985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.1, `Post-Trip Review:Program Description & Procedure' for La Salle County Station.. ML20134J5091985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station & WPPSS-2 ML20244D4411985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station Units 1 & 2 & Washington Nuclear Plant Unit 2. Contains Info for LaSalle ML20101G1541984-12-31031 December 1984 Conformance to Reg Guide 1.97,LaSalle County Station,Units 1 & 2 ML20076J2711983-05-31031 May 1983 Control of Heavy Loads at Nuclear Power Plants,Lasalle Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065B7131982-06-30030 June 1982 Control of Heavy Loads at Nuclear Power Plants LaSalle Units 1 & 2 ML20010E7751981-07-31031 July 1981 Audit of Environ Qualification of Safety-Related Electrical Equipment at La Salle County Station (Unit 1), Technical Evaluation Rept 1995-12-12
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML20012E2671990-03-31031 March 1990 Risk Sensitivity to Human Error in the Lasalle PRA ML19332B5801989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components: La Salle-1/-2, Technical Evaluation Rept ML20058K0861989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to LaSalle County Station,Unit 2 ML20058K0921989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to Lasalle County Station,Unit 1 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 ML20042D0871988-08-0404 August 1988 Simulations of BWR Power Oscillations W/O Scram, Informal Rept ML20150A8641988-05-31031 May 1988 Pump & Valve Inservice Testing Program,Lasalle County Station,Units 1 & 2 ML20153D2101988-01-31031 January 1988 Approaches to Uncertainty Analysis in Probabilistic Risk Assessment ML20236X2871987-10-31031 October 1987 Fire Environment Determination in the Lasalle Nuclear Power Plant Control Room ML20215L9661987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2,Vendor Interface Programs for All Other Safety-Related Components, La Salle Units 1 & 2, Informal Rept ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20155D6271986-02-14014 February 1986 Mod Program Controls, Based on 860210-14 Review ML20141N6051986-01-14014 January 1986 SPDS Progress Review,Lasalle,Units 1 & 2 ML20244D3981985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.1, `Post-Trip Review:Program Description & Procedure' for La Salle County Station.. ML20134J5091985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station & WPPSS-2 ML20244D4411985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station Units 1 & 2 & Washington Nuclear Plant Unit 2. Contains Info for LaSalle ML20101G1541984-12-31031 December 1984 Conformance to Reg Guide 1.97,LaSalle County Station,Units 1 & 2 ML20076J2711983-05-31031 May 1983 Control of Heavy Loads at Nuclear Power Plants,Lasalle Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065B7131982-06-30030 June 1982 Control of Heavy Loads at Nuclear Power Plants LaSalle Units 1 & 2 ML20010E7751981-07-31031 July 1981 Audit of Environ Qualification of Safety-Related Electrical Equipment at La Salle County Station (Unit 1), Technical Evaluation Rept 1995-12-12
[Table view] Category:RESEARCH AND TECHNICAL ASSISTANCE REPORTS
MONTHYEARML20010E7751981-07-31031 July 1981 Audit of Environ Qualification of Safety-Related Electrical Equipment at La Salle County Station (Unit 1), Technical Evaluation Rept 1981-07-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20106H1261995-12-12012 December 1995 IPE Insight Rept NUREG-1150 Plants ML20058E8911993-11-30030 November 1993 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis ML20045B9481993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G ML20045B9041993-05-31031 May 1993 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C ML20116J5311992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation ML20116J4791992-10-31031 October 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis ML20116J6551992-10-31031 October 1992 Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations ML20105C8221992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices ML20105C8171992-08-31031 August 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report ML20105C7631992-08-31031 August 1992 Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) ML20113H9891992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis ML20099D6251992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification ML20099D5281992-07-31031 July 1992 Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary ML20097H3161992-06-30030 June 1992 Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass) ML20012E2671990-03-31031 March 1990 Risk Sensitivity to Human Error in the Lasalle PRA ML19332B5801989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components: La Salle-1/-2, Technical Evaluation Rept ML20058K0861989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to LaSalle County Station,Unit 2 ML20058K0921989-07-31031 July 1989 Technical Evaluation Rept on Response from Commonwealth Edison to Generic Ltr 88-01 Pertaining to Lasalle County Station,Unit 1 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 ML20042D0871988-08-0404 August 1988 Simulations of BWR Power Oscillations W/O Scram, Informal Rept ML20150A8641988-05-31031 May 1988 Pump & Valve Inservice Testing Program,Lasalle County Station,Units 1 & 2 ML20153D2101988-01-31031 January 1988 Approaches to Uncertainty Analysis in Probabilistic Risk Assessment ML20236X2871987-10-31031 October 1987 Fire Environment Determination in the Lasalle Nuclear Power Plant Control Room ML20215L9661987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2,Vendor Interface Programs for All Other Safety-Related Components, La Salle Units 1 & 2, Informal Rept ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20155D6271986-02-14014 February 1986 Mod Program Controls, Based on 860210-14 Review ML20141N6051986-01-14014 January 1986 SPDS Progress Review,Lasalle,Units 1 & 2 ML20138R8891985-11-0505 November 1985 Notification of Contract Execution,Mod 2,to Study of Uncertainties in Sys Analysis Part of Seismic Pra. Contractor:Future Resources Assoc,Inc ML20138R8971985-11-0505 November 1985 Mod 2,substituting LaSalle Reactor Review for Limerick Reactor & Deleting E Hall from Key Personnel Clause,To Study of Uncertainties in Sys Analysis Part of Seismic Pra ML20244D3981985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.1, `Post-Trip Review:Program Description & Procedure' for La Salle County Station.. ML20134J5091985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station & WPPSS-2 ML20244D4411985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, LaSalle County Station Units 1 & 2 & Washington Nuclear Plant Unit 2. Contains Info for LaSalle ML20101G1541984-12-31031 December 1984 Conformance to Reg Guide 1.97,LaSalle County Station,Units 1 & 2 ML20076J2711983-05-31031 May 1983 Control of Heavy Loads at Nuclear Power Plants,Lasalle Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065B7131982-06-30030 June 1982 Control of Heavy Loads at Nuclear Power Plants LaSalle Units 1 & 2 ML20010E7751981-07-31031 July 1981 Audit of Environ Qualification of Safety-Related Electrical Equipment at La Salle County Station (Unit 1), Technical Evaluation Rept 1995-12-12
[Table view] |
Text
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C INTERIM REPORT Accession No.
Report No. EGG-EA-5514 Contract Program or Project
Title:
Equipment Qualification Case Reviews Subject of this Document:
Auait of the Environmental Qualification of Safety-Related Electrical Equipment at the La Salle County Station (Unit 1)
Type of Document:
Technical Evaluation Report Author (s):
Martin F. Hinton Thomas G. Humphrey xa o,,e ,, o f,,L,Pst UC .Researc1 anc "ecanical auis 1981 Assistance Report l Responsible NRC Individual and NRC Office or Division:
Zoltan R. Rosztoczy, NRC-DE l
This document was prepared primarily for prelimiriary or internal use. it has not received full review and approval. Since there may be substantive changes, this document should not be considered final.
EG&G Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
Under DOE Contract No. DE-AC07-761001570 NRC FIN No. A6453 e
INTERIM REPORT
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AUDIT OF THE ENVIR0hMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT AT THE LA SALLE COUNTY STATION (UNIT 1)
Docket No.60-373 j
4
. Martin F. Hinton Thomas G. Humparey Max W. Yost i
i Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.
4 1
! NRC Research and iec,anica,,
Assistance Report 1
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e ASSTRACT The La Salle County Station (Unit 1) was auaitea to aetermine tiie environmental qualification of safety-related electrical equipment.
Results of the audit are summarizea in this report.
FOREWORD This report is supplied as part of the " Equipment Qualification Case Reviews" being conaucted 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 funced the work unaer tne authorization, B&R 20-19-04-15, FIN No. A6453.
U' C Researc'a anGec'anica Assistance Report /
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~ CONTENTS ,
1.0 INTRODUCTION
.................................................... 1.
- * - 2.0 -'EVALVATION ......................................................
1~
~
L
-3.0- CONCLUSIONS'..................................................... 2
4.0 REFERENCES
...................................................... 3 APPEhulx A--QUALIFICATION DEFICIENCIES FOR INUIVIDUAL-EQUIPMENT ITEMS ................................................ 5 APPEhulX ti--SUMMARitiS OF L5CS CENTRAL FILE REVIEWS . . . . . . . . . . . . . . . . . . . 17 1
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NRC Research and Technica i w Assistance Report l
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AUDIT OF THE ENVIRONMENTAL QUALIFICATION ~ 0F SAFETY-RELATED ELECTRICAL EQUIPMENT AT THE LA SALLE ' COUNTY STATION (UNIT 1)
1.0 INTRODUCTION
On June 15-19, 1981 a team comprised of representatives of the Reli-ability and Statistics Branch of EG&G Iidaho, Inc. and NRC staff. conducted an audit of the environmental safety related electrical equipment for the LaSalle County Station (LSCS). The w'>rk_ effort consisted of: (1) a pre-audit review of the licensee's submictal (Ref. 1), (2) an audit of the licencee's central files for selected equipment items, and (3) a visi!al
- inspection of the equipment items for which the central files were audited.
Qualification deficienciss for individual equipment items are provided in l, Attachment A. Summaries of the central file reviews are provided in l Attachment B.
I e 2.0 EVALUATION l
General areas of concern which remain as a result of both the audit l
I and the pre-audit review of the LSCS submittal are as follows:
- 1. Many of the items requiring qualification for radiation exposure,
! particularly the NSSS items, did not appear to be qualified.
l l 2. For the NSSS items, much of the qualification was based on mini-l mal testing with the remainder by very general analysis. These general analyses were not then tied to the specific equipment i
! under consideration.
- 3. For many NSSS items the requirement for operability under accident conditions was not addressed.
s 1
- 4. For -sake safety related' systems the associated electrical ' equip-ment (i.e. . pump motors) was not considered for qualification.
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The licensee maintained that- since these systems were redundant '
the equipment associated with them did not need to be qualified.-
- 5. In most cases the-period of. time for which individual items would
- remain' qualified was act indicated.
- 6. In many cases the qualification envelope was not adequately defined and the envelopes'in the individual summary sheets did not agree with the envelopes for' the zones in which various items of equipment were located.
- 7. All items requiring qualification for demineralized water spray.
were not specified.
- 8. In most cases the requirement for aging was not addressed.
- 9. During the plant inspection some items of electrical equipment were noted which had not been qualified (i.e'., terminal blocks and junction boxes).
- 10. In one location the specified item of equipment had been replaced by one from a different manufacturer.
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- 11. For one item the required test report was not included in the central files.
3.0 CONCLUSION
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As a result of the audit it was concluded that the LSCS environmental qualification of safety-related electrical equipment was not complete. The .
licensee will re-submit environmental qualification data at a later date, at which time another audit will be performed. ;-
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4.0 REFERENCES
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-1. Interim' Staff Position on Environmental Qualification of Safety-l --
Related Electrical Equipment ..NUREG-0588..
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- 2. : Environmental Qualification of Electrical. Equipment, LSCS-FSAR
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' Amendment 57, Appendix M.
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APPENDIX A.
.. QUALIFICATION'DEFICIENCIESff0R INDIVIDUAL EQUIPMENTLITEMS 1
. The legend for entries in the deficiency column ~is as follows:
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L A - ' Material. aging evaluation, replacement schedules, ongoing . equip--
- ment surveillance ,
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~ Margin M -
H - : Humidity P Pressure R -
' Radiation QT -- Qualification time Temperature T -
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B0P EQUIPMENT Equipment Description Manufacturer Model Deficiency (TABLE M.5.1)
- 1. Medium Voltage Switchgear(I) Gould/ITE 7.5 HK-500 'A,M
- 2. Motor Control Center (2) Klockner-Moeller Series 170 QT,R,T,H,A,M
- 3. MotorControlCenter(2) Systems Control --
.A,M,QT,T,H,P
- 4. Electrical Penetration CONAX Custom QUALIFIED.
- 5. . Electrical Penetration CONAX Custom QUALIFIED
- 6. SkV Power Cable Kerite HTA, FR or NS QUALIFIED g 7. Low Veltage Power and Okonite Hypalon Jacket QUALIFIED Control Cable
- 8. Instrumentation Cable Cerro/Rockblestos Hypalon Jacket QUALIFIED l
- 9. Instrumentation Cable S. Moore Co. Hypalon Jacket QT
- 10. Instrumentation Cable .Raychem Flamtrol Jacket QT
, 11. Level Transmitter Rosemont 1152 QT,A,M,H 4
- 12. Pressure Transmitter Rosemont 1152 .QT,A,M,H
- 13. Flow Transmitter (2) Hays .T-00252A INCOMPLETE -
- 14. . Thermocouple (2) Weed .E4B INCOMPLETE i 15. RTO(2) Weed 611 INCOMPLETE.
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BOP EQUIPMENT (continued)
Equipment Description Manufacturer Model Deficiency
- 16. Flow & Temperature (2) Love 54-8115-8134- INCOMPLEfE Controller 8174 i?. Flow Switch Relay (2) Love 56-8115-8174 INCOMPLETE
- 18. Control Panel (2) Systems Control Custom Il1 COMPLETE
- 19. H2 02 Analyzer Panei(2) Delpni K-IV INCOMPLETE
- 20. Power Supply Panel (l) Systems Control Custom INCOMPLETE
- 21. Fan Motor Westinghouse TEFC,182T,286T QT
- 22. Valve Actuator (l) ITT NH91 FAILED m
- 23. Fan Motor (3) Reliance TEAD,184T,256T INCOMPLETE 284T
- 24. Electric Heating Coil (l) CVI --
INCOMPLETE
- 26. Pump Motor Reliance Horiz., DP, QT NEMA 184T
- 26. Recombiner(l) AI Nil 6000024-03 INCOMPLETE
- 27. Solenoid Valve ASCO HVA-206-832- QT,M 3F(2F)
- 28. Solenoid Valve ASCO WPHV-206-381- QT,M 3F
- 29. Solenoid Valve ASCO NP-206-380-7G QT,M c e . , r
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4 B0P EQUIPMENT -(continued)
Equipment Description Manufacturer Model Deficiency
- 30. Solenoid Valve ASCO NP-206-380-3F QT,M
- 31. Solenoid Valve Valcor V526 -QUALIFIED.
- 32. Limit Swtich(I) GPE Controls LICON65-430140 QT,M,A,R,P
- 33. Limit Switch (4) Namco EA-180 INCOMPLETE-
- 34. Valve Motor Operator (2) Limitorque SMB-000 QT
- 35. Valve Motor Operator (2) Limitorque ~ SMB QT
- 36. Valve Motor Operator (2) Limitorque SMB-0 ~QT
- 37. .. Valve Motor Operator (2) Limitorque SMB-1 .QT.
- 38. Valve Motor Operator (2) Limitorque SMB-3 QT
- 39. Valve Motor Operator (2) Limitorque SMB-4 QT-
- 40. Radiation Detector (I). General Atomics RD23 INCOMPLETE
- 41. Control Swtich(I) General Electric SBM ' INCOMPLETE i
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- 42. Tomperature Switch United Electric C302P-103 QUALIFIED.
- 43. Control Swtich(2) General Electric. CR 2940 INCOMPLETE
- 44. Limi.t Swtich' NAMC0 EA700-50100 QUALIFIED.
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BOP EQUIPMENT (continued)
Manufacturer Model Deficiency Equioment Description Amphenol Custom A,QT,M
- 45. Electrical Penetration (2)
(1) Licensee reports that qualification test will be performed on this equipment.
(2) Licensee reports that environmental qualificat son or evaluation not completed.
(3) Insufficent information in submittal.
(4) Testing on connectors has not been completed.
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r NSSS EQUIPMENT Equipment Description Manufacturer Model- ' Deficiency (TABLE M.5.2)
- 1. Safety Relief Valve (2) Crosby HB-65-BP M,A
- 2. Limit Switch NAMC0 EA740 A
- 3. Pressure Switch Barksdale BIT A,R 1
- 4. Pressure Switch STATIC-0-RING. 12N A,R,QT
- 5. Level Indicator Switch BAF. TON 288A .A,R
- 6. Level Inciating Swtich YARWAY 4418C A,R'
- 7. Level Indicating Transmitter BAR 0N 760 A,R,M Switch
-8. Level Transmitter ROSEMONT 1151 8,R,QT 9.- Pressure Tansmitter BAILEY 556 -A,R,P,H,.
- 10. Solenoid. Valve (I) ASCO HT832322 INCOMPLETE
- 11. Level Switch Magnetrol 751 A,R,P,H
- 12. Pump Motor (I) GE 324AN INCOMPLETE
- 13. Control Valve (l) CONAX P/N 1812-159- INCOMPLETE
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- 14. Voltage Preamplifier GE N/S A,R,P,QT'
- 15. . Detector (2) GE N/A INCOMPLETE
NSSS EQUIPMENT (continued)-
Equipmerit ' Description Manufacturer Model ' Deficiency
- 16. Pressure Transmitter ROSEMONT 1151 A,R,QT,M,P,H
- 17. Insulated Detector .GE NA05 -A,R,QT,P,HL
- 18. Sensor and Converter GE -- A,R
- 19. Pressure Switch STATIC-0-RING SN,6N- A,R
- 20. Power Range Detector (2) GE NA 200 IN' COMPLETE
- 21. Diff. Press. Indicating BARTON 288 -A,R,QT,M Switch 5 22. Flow Switch BARTON 289 A',R,QT,M i 23. Pressure Indicator Swtich ROBERT SHAW SP 222E A,R,QT,T,M
- 24. Pressure Switch Barksdale PlH A,R,M
- 25. Temperature Element (3) PYC0 300 Series SS INCOMPLETE ,
- 26. Solenoid Valve (l) ITT Hammel-T. M 502 INCOMPLETE
- 27. Temperature Element PYC0 N/A A,P,H
- 28. Guide Tube Valve Assembly GE N/A A,R,H,T,QT~
- 29. Hydraulic Control Unit (l) .GE 761E500 INCOMPLETE -;
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- 30. Temperature Element (3) WEED 300 Series INCOMPLETE
- 31. Flow Transmitter. S&K 91X-16-4-20 A,R,QT,M,H I
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o . t l NSSS EQUIPMENT (continued)
Equipment Description Manufacturer Model Deficiency
- 32. Steam Turbine Terry Corp. GS-2 A,M
- 33. Pressure Switch Barksdale D2H A,M,QT,R
- 34. Diff. Pressure Indicator (3) BARTON 227 INCOMPLETE
- 35. Temperature Element (3) CalAlloy/Pyco N/S INCOMPLETE
- 36. Diff. Pressure Transmitter (3) Statham PD 2000 INCOMPLETE
- 37. Temperature Swtich(3) WEED 22810 INCOMPLETE
- 38. Temperature Indicator (3) WEED 4900-S-4
- INCOMPLETE
- 39. Flow Transmitter Rosemont 1152 A,R,QT
- 40. Level Transmitter Gould Inc. P03018 A,M
- 41. Dry Tube (3) GE N/S INCOMPLETE
- 42. Flange (3) GE N/S INCOMPLETE
- 43. Condensing Chamber (3) GE N/S INCOMPLETE
- 44. Diff. Pressure Indicating Switch rn.RTON 288 A,R,QT,M
- 45. Temperature Element (3) Rosemont N/A INCOMPLETE
- 46. Drywell Penetration Flange (3) GE N/S INCOMPLETE
- 47. Guide Tube (3) Handy & Harmon N/S INCOMPLETE
- 48. Check Valve (3) Matheson Co. Inc. N/S INCOMPLETE
NSSS EQUIPMENT (continued)
Equipment Description Manufacturer Model Deficiency
- 49. Pressure Indicator (3) Robert Shaw 613B INCOMPLETE
- 50. M0 Gate Valve (3) Limitorque SMB-2-25 INCOMPLETE SMB-3-60 (1) Equipment which the licensee has identified as requiring additional evaluation or qualification documentation.
(2) Equipment located in reactor vessel.
(3) Equipment which may not fall within NUREG 0588 requirements.
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e . u ( . o MISC. B0P & NSSS FROM TABLES 5.4 & 5.5 Equipment Description Manufacturer Model Deficiency (TABLE 5.4)
- 3. Vacuum Switch Barksdale DIT-hl855 QT,M,A,R,H (Table 5.6)
- 16. Pressure Indicator Switch (l) Robert Shaw SP-222E INCOMPLETE
- 19. Pressure Transmitter (l) Bailey 556 INCOMPLETE
- 20. Flow Transmitter (I) Rosemont 1151 INCOMPLETE
- 21. Level Transmitter (I) Barton 352/368 INCOMPLETE G
- 43. Heater Assembly GE 478518673 P,H,A
- 44. Leakage Control Blower Siemens 2CH6 T,P,M,A
- 45. Pump Motor Ingersoll Rand 5K6339XC109A P,M
- 46. Pump Motor Ingersoll Rand SK6347XC59A P,M
- 47. Pump Motor Ingersoll Rand 5K6357XC8B P,M
- 48. M.0. Valve Limitorque SMB-00-25 QT,A
- 49. M.0. Valve Limitorque SMB-4-200 QT,A,R
- 50. M.0. Valve Limitorque SMB-3-100 QT,A,R
- 51. M.0. Valve Limitorque SMB-3-80 QT,A,R
- 52. M.0. Valve Limitorque SB-0-25 QT,A
MISC. BOP & NSSS FROM TABLES 5.4 & 5.5 (continued)
Limitorque SMB-2-60 QT,A
- 53. M.0. Valve Limitorque SMB-4-150 QT,A
- 54. M.0. Valve (1) Qualification under NUREG 0588 may not be required.
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APPENDIX B
" SUMMARIES OF LSCS CENTRAL FILE REVIEWS Item: Bailey Pressure Tansmitter (Model 556)
The Bailey pressure transmitter is used to provide the reactor vessel f pressure signal for the post accident monitoring recorder. The transmitter
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is located within the reactor building in zone RB2. Bounding environmental-
- qualification parameters are identified as temperature (145*F for one day then 134'F to 100 days), pressure (atmospheric), relative humidity (95%),
and radiation (1.8 x 105 Rads TID). The required operating time within an adverse environment is up to 100 days.
l The audit of the envrionmental qualification documentation indicated
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that this type of unit was exposed to a temperature of 212*F'for six hours.
Qualification for temperature, humidity, and radiation, as well as the U requirement for aging, for the required 100 day operability were by analy-l
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sis only. Qualification time, humidity, radiation, and aging remain as i
concerns resulting from the audit.
Item: Yarway Level Indicating Switch (Model 4418C)
The Yarway level indicating switch is used to sense reactor water level to trip the recirculation pump. The switch is located within the reactor building in zone RB2. Bounding environmental qualification para-meters are identified as temperature (145'F), pressure (atmospheric), rela-5 tive humidity (95%), and radiation (1.8 x 10 Rads TID). The required operating time within an adverse environment is 45 sec.
l Of major concern is the fact that the test report for this item was
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not in the central files. The audit was therefore done on the summary sheet, t.ome documentation present in the file, and the qualification envi-ronment presented in the submittal. The item appears to be qualified for 15
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temperature and humidity. ' Qualification for aging and radiation was by analysis only.
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L Item: SkV Power Cable--Kerite Co.
l The SkV Kerite power cable is used throughout the plant (except con-tainment). The most severe environment is in the reactor building. The abnormal environment is defined as Zone H5. The limiting environmental parameters in this zone are identified as.tempertature (0-6 hr at 212*F),
(6-12 hr at 150*F), and (12 hr-100 days at 150*F);. pressure (0-6 hr at f 7"iH 0), (6-12 hr at 7" H O), 2 and (12 hr-100 days at atmospheric);
2 relative humidity (0-6 hr at steam), (6-12 hr at l'00%), and (12 hr-100 days 6
at 90%); radiation (8.93 x 10 Rad); operability requirements (100 days).
o The audit of the referenced qualification documentation confirmed that this item was exposed to compatible environmental conditions to those indi-cated above. Qualification method was by prototype test and analysis.
l Margin for time remains a concern as results'from the audit. Justification t
I for this concern will be reflected in a future submittal and the test. report will be updated to show the time margin requirement.
Item: Instrumentation Cable--Samual Moore Company This instrumentation cable is used throughout the plant with the con-tainment being the harshest environment. The limiting environmental para-meters are identified as temperature (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 340*F, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 320 F, 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> at 250 F, 99 days at 200*F), pressure (-2 to 45 psig for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 7
0-25 psig for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />, 0-20 psig for 99 days), radiation (4.4 x 10 Rads TID), and . relative humidity (steam /100%). The operability requirement is 100 days.
The audit of the environmental qualification documentation confirmed that this item was exposed to compatible environmental conditions to those indicated above, with slight deviatiun in pressure. The test included pre-
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w aging and electrical energization under test. No margin is demonstrated for operability requirement time or for temperature, and no justification 16
7 is shown for lack of margin. These margins remain a concern and justifi-cation will be previded in the next submitcal.
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. s Item: Gould Inc. Level Transmitter (Model PD 3018)
The Gould level transmitter is used to measure the scram discharge volume water level and signals-the RPS to scram the reactor when the level i is too high. The transmitter is located within the reactor building in zone RBl. Bounding environmental qualification parameters are identified as temperature (145*F), pressure (atmospheric), relative humidity (95%), ,
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! andradiation(1.8x10 RadsTID). The required operating time sithin an adverse environment is one hour.
The audit of the envrionmental qualification documentation confirmed that this type of unit was exposed to environmental conditions which exceeded those listed above by adequate margin; i.e. tem; mature (220'F),-
7 pressure (atmospheric), relative humidity (steam), radiation (2.0 x 10 l'
l Rads TID) and time (three hours). The requirement for aging, however, was by analysis only. The audit indicates that this item is qualified per l
NUREG 0588 Category II with the exception of aging.
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