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Category:CONTRACTED REPORT - RTA
MONTHYEARML20063H7431993-12-31031 December 1993 Continuous Ae Crack Monitoring of a Dissimilar Metal Weldment at Limerick Unit 1 ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20073G0371991-03-31031 March 1991 TER on First 10-yr Interval Inservice Insp Program Plan: Philadelphia Electric Co,Limerick Generating Station,Unit 2 ML20069Q5461990-01-31031 January 1990 Pump & Valve Inservice Testing Program,Limerick Generating Station,Units 1 & 2, Technical Evaluation Rept ML20011D1111989-10-31031 October 1989 Final Technical Evaluation Rept on Response from Philadelphia Electric Co to Generic Ltr 88-01 Re Limerick Generating Station,Unit 1. ML19332B5981989-08-31031 August 1989 Conformance to Generic Ltr 83-28 Item 2.2.1:Equipment Classification for All Safety-Related Components: Limerick-1/-2, Technical Evaluation Rept 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 ML20216B9061987-05-31031 May 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Limerick 1 & 2, Final Informal Rept ML20235J8001987-05-31031 May 1987 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual,Rev 4 ML20137Y7151985-11-30030 November 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Limerick Units 1 & 2 ML20198C0931985-09-23023 September 1985 Fission Product Transport for Limerick Plant, Final Rept ML20246F3801985-08-31031 August 1985 Design and Feasibility of Accident Mitigation Systems for Light Water Reactors.Final Report ML20128Q9171985-05-0909 May 1985 BNL Technical Review Rept. Review Conducted on 850422-26 ML20101A9421984-10-0808 October 1984 Review of Limerick Unit 1 Tech Specs ML20106C0851984-09-14014 September 1984 Technical Review Rept for Emergency Svc Water Sys on 840827-31 ML20106A5251984-08-10010 August 1984 Technical Evaluation Rept of Detailed Control Room Design Review for Limerick Generating Station ML20095B9901984-07-31031 July 1984 a Review of the Limerick Generating Station Severe Accident Risk Assessment.Review of Core Melt Frequency ML20107L9681984-06-30030 June 1984 App M to NUREG/CR-3301, Limerick Generating Station ML20092M0211984-04-30030 April 1984 Containment Failure Mode & Fission Product Release Analysis for Limerick Generating Station:Base Case Assessment ML20084B8831984-03-31031 March 1984 Conformance to Reg Guide 1.97,Limerick Generating Stations Units 1 & 2 ML20081L2711983-11-30030 November 1983 Final Draft, Estimating Economic Costs of Radiation- Induced Health Effects ML20086L9901983-10-30030 October 1983 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20083D1621983-09-15015 September 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830730-0831.Addendum Re Value/Impact for Mitigation Encl ML20083D1641983-08-15015 August 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830627-0730 ML20024E6611983-08-15015 August 1983 Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. ML20071E0021983-02-28028 February 1983 a Review of the Limerick Generating Station Probabilistic Risk Assessment ML20067A4781982-11-30030 November 1982 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 1993-08-31
[Table view] Category:QUICK LOOK
MONTHYEARML20063H7431993-12-31031 December 1993 Continuous Ae Crack Monitoring of a Dissimilar Metal Weldment at Limerick Unit 1 ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20073G0371991-03-31031 March 1991 TER on First 10-yr Interval Inservice Insp Program Plan: Philadelphia Electric Co,Limerick Generating Station,Unit 2 ML20069Q5461990-01-31031 January 1990 Pump & Valve Inservice Testing Program,Limerick Generating Station,Units 1 & 2, Technical Evaluation Rept ML20011D1111989-10-31031 October 1989 Final Technical Evaluation Rept on Response from Philadelphia Electric Co to Generic Ltr 88-01 Re Limerick Generating Station,Unit 1. ML19332B5981989-08-31031 August 1989 Conformance to Generic Ltr 83-28 Item 2.2.1:Equipment Classification for All Safety-Related Components: Limerick-1/-2, Technical Evaluation Rept 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 ML20216B9061987-05-31031 May 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Limerick 1 & 2, Final Informal Rept ML20235J8001987-05-31031 May 1987 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual,Rev 4 ML20137Y7151985-11-30030 November 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Limerick Units 1 & 2 ML20198C0931985-09-23023 September 1985 Fission Product Transport for Limerick Plant, Final Rept ML20246F3801985-08-31031 August 1985 Design and Feasibility of Accident Mitigation Systems for Light Water Reactors.Final Report ML20128Q9171985-05-0909 May 1985 BNL Technical Review Rept. Review Conducted on 850422-26 ML20101A9421984-10-0808 October 1984 Review of Limerick Unit 1 Tech Specs ML20106C0851984-09-14014 September 1984 Technical Review Rept for Emergency Svc Water Sys on 840827-31 ML20106A5251984-08-10010 August 1984 Technical Evaluation Rept of Detailed Control Room Design Review for Limerick Generating Station ML20095B9901984-07-31031 July 1984 a Review of the Limerick Generating Station Severe Accident Risk Assessment.Review of Core Melt Frequency ML20107L9681984-06-30030 June 1984 App M to NUREG/CR-3301, Limerick Generating Station ML20092M0211984-04-30030 April 1984 Containment Failure Mode & Fission Product Release Analysis for Limerick Generating Station:Base Case Assessment ML20084B8831984-03-31031 March 1984 Conformance to Reg Guide 1.97,Limerick Generating Stations Units 1 & 2 ML20081L2711983-11-30030 November 1983 Final Draft, Estimating Economic Costs of Radiation- Induced Health Effects ML20086L9901983-10-30030 October 1983 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20083D1621983-09-15015 September 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830730-0831.Addendum Re Value/Impact for Mitigation Encl ML20083D1641983-08-15015 August 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830627-0730 ML20024E6611983-08-15015 August 1983 Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. ML20071E0021983-02-28028 February 1983 a Review of the Limerick Generating Station Probabilistic Risk Assessment ML20067A4781982-11-30030 November 1982 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 1993-08-31
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20063H7431993-12-31031 December 1993 Continuous Ae Crack Monitoring of a Dissimilar Metal Weldment at Limerick Unit 1 ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20073G0371991-03-31031 March 1991 TER on First 10-yr Interval Inservice Insp Program Plan: Philadelphia Electric Co,Limerick Generating Station,Unit 2 ML20069Q5461990-01-31031 January 1990 Pump & Valve Inservice Testing Program,Limerick Generating Station,Units 1 & 2, Technical Evaluation Rept ML20011D1111989-10-31031 October 1989 Final Technical Evaluation Rept on Response from Philadelphia Electric Co to Generic Ltr 88-01 Re Limerick Generating Station,Unit 1. ML19332B5981989-08-31031 August 1989 Conformance to Generic Ltr 83-28 Item 2.2.1:Equipment Classification for All Safety-Related Components: Limerick-1/-2, Technical Evaluation Rept 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 ML20216B9061987-05-31031 May 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Limerick 1 & 2, Final Informal Rept ML20235J8001987-05-31031 May 1987 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual,Rev 4 ML20137Y7151985-11-30030 November 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Limerick Units 1 & 2 ML20198C0931985-09-23023 September 1985 Fission Product Transport for Limerick Plant, Final Rept ML20246F3801985-08-31031 August 1985 Design and Feasibility of Accident Mitigation Systems for Light Water Reactors.Final Report ML20128Q9171985-05-0909 May 1985 BNL Technical Review Rept. Review Conducted on 850422-26 ML20101A9421984-10-0808 October 1984 Review of Limerick Unit 1 Tech Specs ML20106C0851984-09-14014 September 1984 Technical Review Rept for Emergency Svc Water Sys on 840827-31 ML20106A5251984-08-10010 August 1984 Technical Evaluation Rept of Detailed Control Room Design Review for Limerick Generating Station ML20095B9901984-07-31031 July 1984 a Review of the Limerick Generating Station Severe Accident Risk Assessment.Review of Core Melt Frequency ML20107L9681984-06-30030 June 1984 App M to NUREG/CR-3301, Limerick Generating Station ML20092M0211984-04-30030 April 1984 Containment Failure Mode & Fission Product Release Analysis for Limerick Generating Station:Base Case Assessment ML20084B8831984-03-31031 March 1984 Conformance to Reg Guide 1.97,Limerick Generating Stations Units 1 & 2 ML20081L2711983-11-30030 November 1983 Final Draft, Estimating Economic Costs of Radiation- Induced Health Effects ML20086L9901983-10-30030 October 1983 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20083D1621983-09-15015 September 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830730-0831.Addendum Re Value/Impact for Mitigation Encl ML20083D1641983-08-15015 August 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830627-0730 ML20024E6611983-08-15015 August 1983 Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. ML20071E0021983-02-28028 February 1983 a Review of the Limerick Generating Station Probabilistic Risk Assessment ML20067A4781982-11-30030 November 1982 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 1993-08-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20063H7431993-12-31031 December 1993 Continuous Ae Crack Monitoring of a Dissimilar Metal Weldment at Limerick Unit 1 ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20073G0371991-03-31031 March 1991 TER on First 10-yr Interval Inservice Insp Program Plan: Philadelphia Electric Co,Limerick Generating Station,Unit 2 ML20069Q5461990-01-31031 January 1990 Pump & Valve Inservice Testing Program,Limerick Generating Station,Units 1 & 2, Technical Evaluation Rept ML20011D1111989-10-31031 October 1989 Final Technical Evaluation Rept on Response from Philadelphia Electric Co to Generic Ltr 88-01 Re Limerick Generating Station,Unit 1. ML19332B5981989-08-31031 August 1989 Conformance to Generic Ltr 83-28 Item 2.2.1:Equipment Classification for All Safety-Related Components: Limerick-1/-2, Technical Evaluation Rept 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 ML20216B9061987-05-31031 May 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Limerick 1 & 2, Final Informal Rept ML20235J8001987-05-31031 May 1987 Technical Evaluation Rept for Evaluation of Offsite Dose Calculation Manual,Rev 4 ML20210G1751986-09-0303 September 1986 Notification of Contract Execution,Mod 3,to Review of Tornado Missile PRA-Limerick Generating Station & Seabrook Nuclear Power Plant. Contractor:Nbs ML20210G2141986-09-0303 September 1986 Mod 3,deobligating Funds,To Review of Tornado Missile PRA- Limerick Generating Station & Seabrook Nuclear Power Plant ML20137Y7151985-11-30030 November 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Limerick Units 1 & 2 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 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 ML20198C0931985-09-23023 September 1985 Fission Product Transport for Limerick Plant, Final Rept ML20246F3801985-08-31031 August 1985 Design and Feasibility of Accident Mitigation Systems for Light Water Reactors.Final Report ML20128Q9171985-05-0909 May 1985 BNL Technical Review Rept. Review Conducted on 850422-26 ML20101A9421984-10-0808 October 1984 Review of Limerick Unit 1 Tech Specs ML20106C0851984-09-14014 September 1984 Technical Review Rept for Emergency Svc Water Sys on 840827-31 ML20106A5251984-08-10010 August 1984 Technical Evaluation Rept of Detailed Control Room Design Review for Limerick Generating Station ML20095B9901984-07-31031 July 1984 a Review of the Limerick Generating Station Severe Accident Risk Assessment.Review of Core Melt Frequency ML20107L9681984-06-30030 June 1984 App M to NUREG/CR-3301, Limerick Generating Station ML20092M0211984-04-30030 April 1984 Containment Failure Mode & Fission Product Release Analysis for Limerick Generating Station:Base Case Assessment ML20084B8831984-03-31031 March 1984 Conformance to Reg Guide 1.97,Limerick Generating Stations Units 1 & 2 ML20081L2711983-11-30030 November 1983 Final Draft, Estimating Economic Costs of Radiation- Induced Health Effects ML20086L9901983-10-30030 October 1983 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 (Phase Ii), Draft Technical Evaluation Rept ML20083D1621983-09-15015 September 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830730-0831.Addendum Re Value/Impact for Mitigation Encl ML20083D1641983-08-15015 August 1983 Severe Accident Mitigation Sys, Monthly Project Status Rept for 830627-0730 ML20024E6611983-08-15015 August 1983 Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. ML20071E0021983-02-28028 February 1983 a Review of the Limerick Generating Station Probabilistic Risk Assessment ML20067A4781982-11-30030 November 1982 Control of Heavy Loads at Nuclear Power Plants,Limerick Generating Station Units 1 & 2 1993-08-31
[Table view] |
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CONFORMANCE TO GENERIC LETTER 83-28 ITEMS 3.1.3 AND 3.2.3 LIMERICK UNITS 1 AND 2 R. HAROLDSEN EG G -NTA - 7095 Published November 1985 EG&G Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN Nos. 06001 and 06002 ssguta b
e ABSTRACT This EG&G Idaho, Inc. report provide'. a review of the submittals f Limerick Units 1 and 2 for conformance to Generic Letter 83-28, items 3.1.3 and 3.2.3.
FOREWORD l
This report is supplieo as part of the program for evaluating -
licensee / applicant conformance to Generic Letter 83-28 " Required Actions Based on Generic Implications of Salem ATWS Events." This work is conducted.for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of System Integration by EG&G Idaho, Inc...NRC Licensing Support Section.
The U.S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20-19-19-11-3, FIN Nos. 06001 and 06002.
Plant Docket No. TAC Nos.
Limerick 1 50-352 56259 and 56261 Limerick 2 50-353 - -
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CONTENTS A B S TR A C T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii
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+ FOREWORD ......................................................
- 1. INTRODUCTION ..................................................... 1
- 2. 2 R E V I E W R E Q U I R E F. '. T S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 3. REVIEW RESULTS F A L IMERICK UNITS 1 Arid 2 . . . . . . . . . . . . . . . . . . . . . . . . 3 3.1 Evaluation .................................................. 3 3.2 Conclusion .................................................. 3 4 REFERENCES ....................................................... 4 b
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CONFORMANCE TO GENERIC LETTER 83-28 ITEMS 3.1.3 AND 3.2.3 LIMERICK UNITS 1 AND 2 e
, , 1. INTRL JCTION On July 8, 1933, Generic Letter No. 83-28 was issued by D. G.
Eisenhut, Director of the Division of Licensing, Nuclear Reactor Regulation, to all licensees of cparating reactors, applicants for operating licenses, and holders of construction permits. This letter included required actions based on generic implications of the Salem ATWS events. These requirements have been published in Volume 2 of NUREG-1000, -
" Generic Implications of'ATWS Events at the Salem Nuclear Power Plant".2 This report documents the EG&G Idaho, Inc. review of the submittals from Limericx Units 1 and 2 for conformance to items 3.1.3 and 3.2.3 of Generic Letter 83-28. Tne submittals and other documents utilized in this evaluation are referenced in section 4 of this report.
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- 2. REVIEW RE0VIREMENTS Item 3.1.3 (Post-Maintenance Testing of Reactor Trip System Components) requires licensees and applicants to identify, if applicable, any post-maintenance test requirements for the Reactor Trip System (RTS) in existing technical specift.ations which can be demonstrateo to degrade rather than ennance safety. Item 3.2.3 appl '- th . same requirement to all other safety-related components. Any proposed technical spe:ification changes resulting from this action shall receive a pre-implementation review by NRC.
The relevant submittals from the Limerick Units 1 and 2 were reviewed to determine compliance with items 3.1.3 and 3.2.3 of the Generic Letter.
First, the submittals from this plant were reviewed to determine that these two items were specifically addressed. Second, the submittals were checked to determine if there were any post-maintenance test items specified by the technical specifications that were suspected to degrade rather than enhance safety. Last, the submittals were reviewed for evidence of special conditions or other significant information relating to the two items of Concern.
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- 3. REVIEW RESULTS FOR LIMERICK UNITS 1 AND 2 3.1 Evaluation )
. Pniladelphia Ele -ic Company, the licensec for Limerick Ur. - 1 and the applicant for Unit 2, provided responses to items 3.1.3 and 3.." 3 of Generic Letter 83-28 in their submittal dated November 10, 1983 In that sttmittal the licensee / applicant stated that the !achnical specifications for the Limerick plants were in the process of being written, were not complete but would be completed by January 1984. The submittal did not specifically address the concerns of items 3.1.3 and 3.2.3.
The licensee provided a subsequent response dated May 29, 1985 . In this latter submittal the licensee s'tates that during the preparation of the Limerick Technical Specifications, no post-maintenance testing requirements were identified that may degrade safety.
3.2 Conclusion The response from the licensee / applicant meets the requirements of items 3.1.3 and 3.2.3 of Generic Letter 83-28, and is acceptable.
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- 4. REFERENCES
- 1. NRC Letter, D. G. Eisennut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, i
" Required Actions Based on Generic Im lications of Salem ATWS Events (Generic Letter 83-28)", July 8,1983.
- 2. Generic Implicatite.s of ATWS Events at the Salem t . : lear Power 'lart, NbHtG-lUUU, Vo lume I, Aprt i 1964; volume 2, July i,dd.
- 3. Letter, V. S. Boyer, Dhiladelphia Electric Company, to D. G. Eisenhut, NRC, November 10, 1983.
- 4. Letter S. L. Daltroff, Philadelphia Electric Company, to A. Schwencer, NRC, May 29, 1985.
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