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Category:CONTRACTED REPORT - RTA
MONTHYEARML20199G8601997-04-10010 April 1997 Rev 0 to Technical Evaluation of Oyster Creek Nuclear Generating Station Analysis of Cable Ampacity Limits 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 ML20205L0091988-07-31031 July 1988 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Oyster Creek, Technical Evaluation Rept ML20238D0211987-07-31031 July 1987 Conformance to Reg Guide 1.97:Oyster Creek, Interim Technical Evaluation Rept ML20215L7481987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety Related Components: Oyster Creek, Final Informal Rept ML20214R3841987-03-31031 March 1987 Followup SEP Evaluation of Part of Remaining Open Items for Oyster Creek Nuclear Power Plant ML20212C0721986-08-0404 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Oyster Creek Plant, Supplementary Technical Evaluation Rept ML20211N8751986-06-30030 June 1986 Draft Conformance to Reg Guide 1.97,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20210C3071986-03-19019 March 1986 Final Supplementary Rept,Review of Licensee Responses to SEP Topic III-7.B,Design Codes,Design Criteria & Loading Combinations,Oyster Creek ML20136G4791985-11-0404 November 1985 Masonary Wall Design, Technical Evaluation Rept ML20138L7171985-07-10010 July 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions...Atws Events),Item 1.2, 'Post-Trip Review:Data & Info Capabilities' for Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20151K8961985-05-20020 May 1985 Evaluation of Dcrdr Summary Rept for Oyster Creek Nuclear Generating Station, Supplemental Technical Evaluation Rept ML20115A4171985-01-11011 January 1985 Evaluation of Isolation Condenser Cracks at Oyster Creek Unit 1 ML20140C9991984-10-31031 October 1984 Review of Wind & Tornado Loading Responses,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20094L1551984-07-20020 July 1984 Evaluation of Detailed Control Room Design Review Summary Rept for Oyster Creek Nuclear Generating Station, Final Technical Rept ML20093C7781984-07-0505 July 1984 Evaluation of Spent Fuel Racks Structural Analysis,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20082C0881983-10-31031 October 1983 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Final Report: September 1,1976 - December 31,1982 ML20083J3231983-09-30030 September 1983 Technical Evaluation of Oyster Creek Plant Unique Analysis Repts ML20092N6501983-08-31031 August 1983 Technical Evaluation of Integrity of Oyster Creek Reactor Coolant Boundary Piping Sys ML20080E2641983-08-30030 August 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20079Q7121983-06-10010 June 1983 Control of Heavy Loads (C-10),JCP&L Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20076J4031983-04-0606 April 1983 RCS Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20076C4231983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Jcp&L, Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20070L7311982-12-31031 December 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Docket No. 50-219.(General Public Utilities) ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070J3311982-11-30030 November 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,March - May 1982 ML20071N2601982-09-30030 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A9061982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20065B8501982-08-31031 August 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,December 1981-Februaury 1982 ML20140B7651982-07-31031 July 1982 Review of Operating Experience History of Oyster Creek Through 1981 for NRC SEP, Final Rept ML20027D2261982-07-31031 July 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20058B1171982-06-30030 June 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,September-November 1981 ML20054L4961982-06-0909 June 1982 Hydrological Considerations (SEP,II-3.A,B,B.1,3.C) Jcp&L, Oyster Creek Nuclear Power Plant, Revised Technical Evaluation Rept ML20054E4181982-06-0808 June 1982 Wind & Tornado Loadings (SEP III-2), Technical Evaluation Rept ML20063G7771982-05-31031 May 1982 SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads ML20062A4881982-04-30030 April 1982 Safety Evaluation Rept,Pump & Valve Inservice Testing Program,Oyster Creek Nuclear Generating Station, Interim Rept ML20052H4361982-04-30030 April 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20052B5811982-04-28028 April 1982 Design Codes,Design Criteria, & Loading Combinations (SEP III-7.B) Jersey Central Power & Light Co,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20053D2141982-04-27027 April 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20052D4851982-03-31031 March 1982 Draft SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads. ML20049H9691982-02-18018 February 1982 Comparison of Plant & Model Radiological Effluent Tech Specs,Gpu Nuclear Corp, Draft Radiological Effluent Tech Spec Implementation ML20064L0711982-01-27027 January 1982 Technical Evaluation Rept for BWR Scram Discharge Vol Long-Term Mods Oyster Creek Nuclear Generating Station ML19348A0541981-08-31031 August 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Power Station,Unit 1. ML20010D8041981-07-31031 July 1981 Preliminary Adequacy of Station Electric Distribution Sys Voltages,Oyster Creek Nuclear Power Station, Technical Evaluation Rept ML20009E0601981-07-17017 July 1981 Changes Report Number to NUREG/CR-1939,Volume 1, Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station ML20009F1651981-06-30030 June 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Station Unit 1, Technical Evaluation Rept ML20010B3911981-06-10010 June 1981 Draft Technical Evaluation:Sep Topic VI-4, Electrical, Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML20010A0171981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Oyster Creek Nuclear Power Plant. Setpoint Requirements Have Been Met ML20049J1871981-05-21021 May 1981 Containment Leakage Rate Testing, Technical Evaluation Rept ML20008F7661981-04-30030 April 1981 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station 1997-04-10
[Table view] Category:QUICK LOOK
MONTHYEARML20199G8601997-04-10010 April 1997 Rev 0 to Technical Evaluation of Oyster Creek Nuclear Generating Station Analysis of Cable Ampacity Limits 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 ML20205L0091988-07-31031 July 1988 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Oyster Creek, Technical Evaluation Rept ML20238D0211987-07-31031 July 1987 Conformance to Reg Guide 1.97:Oyster Creek, Interim Technical Evaluation Rept ML20215L7481987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety Related Components: Oyster Creek, Final Informal Rept ML20214R3841987-03-31031 March 1987 Followup SEP Evaluation of Part of Remaining Open Items for Oyster Creek Nuclear Power Plant ML20212C0721986-08-0404 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Oyster Creek Plant, Supplementary Technical Evaluation Rept ML20211N8751986-06-30030 June 1986 Draft Conformance to Reg Guide 1.97,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20210C3071986-03-19019 March 1986 Final Supplementary Rept,Review of Licensee Responses to SEP Topic III-7.B,Design Codes,Design Criteria & Loading Combinations,Oyster Creek ML20136G4791985-11-0404 November 1985 Masonary Wall Design, Technical Evaluation Rept ML20138L7171985-07-10010 July 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions...Atws Events),Item 1.2, 'Post-Trip Review:Data & Info Capabilities' for Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20151K8961985-05-20020 May 1985 Evaluation of Dcrdr Summary Rept for Oyster Creek Nuclear Generating Station, Supplemental Technical Evaluation Rept ML20115A4171985-01-11011 January 1985 Evaluation of Isolation Condenser Cracks at Oyster Creek Unit 1 ML20140C9991984-10-31031 October 1984 Review of Wind & Tornado Loading Responses,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20094L1551984-07-20020 July 1984 Evaluation of Detailed Control Room Design Review Summary Rept for Oyster Creek Nuclear Generating Station, Final Technical Rept ML20093C7781984-07-0505 July 1984 Evaluation of Spent Fuel Racks Structural Analysis,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20082C0881983-10-31031 October 1983 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Final Report: September 1,1976 - December 31,1982 ML20083J3231983-09-30030 September 1983 Technical Evaluation of Oyster Creek Plant Unique Analysis Repts ML20092N6501983-08-31031 August 1983 Technical Evaluation of Integrity of Oyster Creek Reactor Coolant Boundary Piping Sys ML20080E2641983-08-30030 August 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20079Q7121983-06-10010 June 1983 Control of Heavy Loads (C-10),JCP&L Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20076J4031983-04-0606 April 1983 RCS Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20076C4231983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Jcp&L, Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20070L7311982-12-31031 December 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Docket No. 50-219.(General Public Utilities) ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070J3311982-11-30030 November 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,March - May 1982 ML20071N2601982-09-30030 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A9061982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20065B8501982-08-31031 August 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,December 1981-Februaury 1982 ML20140B7651982-07-31031 July 1982 Review of Operating Experience History of Oyster Creek Through 1981 for NRC SEP, Final Rept ML20027D2261982-07-31031 July 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20058B1171982-06-30030 June 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,September-November 1981 ML20054L4961982-06-0909 June 1982 Hydrological Considerations (SEP,II-3.A,B,B.1,3.C) Jcp&L, Oyster Creek Nuclear Power Plant, Revised Technical Evaluation Rept ML20054E4181982-06-0808 June 1982 Wind & Tornado Loadings (SEP III-2), Technical Evaluation Rept ML20063G7771982-05-31031 May 1982 SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads ML20062A4881982-04-30030 April 1982 Safety Evaluation Rept,Pump & Valve Inservice Testing Program,Oyster Creek Nuclear Generating Station, Interim Rept ML20052H4361982-04-30030 April 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20052B5811982-04-28028 April 1982 Design Codes,Design Criteria, & Loading Combinations (SEP III-7.B) Jersey Central Power & Light Co,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20053D2141982-04-27027 April 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20052D4851982-03-31031 March 1982 Draft SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads. ML20049H9691982-02-18018 February 1982 Comparison of Plant & Model Radiological Effluent Tech Specs,Gpu Nuclear Corp, Draft Radiological Effluent Tech Spec Implementation ML20064L0711982-01-27027 January 1982 Technical Evaluation Rept for BWR Scram Discharge Vol Long-Term Mods Oyster Creek Nuclear Generating Station ML19348A0541981-08-31031 August 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Power Station,Unit 1. ML20010D8041981-07-31031 July 1981 Preliminary Adequacy of Station Electric Distribution Sys Voltages,Oyster Creek Nuclear Power Station, Technical Evaluation Rept ML20009E0601981-07-17017 July 1981 Changes Report Number to NUREG/CR-1939,Volume 1, Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station ML20009F1651981-06-30030 June 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Station Unit 1, Technical Evaluation Rept ML20010B3911981-06-10010 June 1981 Draft Technical Evaluation:Sep Topic VI-4, Electrical, Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML20010A0171981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Oyster Creek Nuclear Power Plant. Setpoint Requirements Have Been Met ML20049J1871981-05-21021 May 1981 Containment Leakage Rate Testing, Technical Evaluation Rept ML20008F7661981-04-30030 April 1981 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station 1997-04-10
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20199G8601997-04-10010 April 1997 Rev 0 to Technical Evaluation of Oyster Creek Nuclear Generating Station Analysis of Cable Ampacity Limits 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 ML20205L0091988-07-31031 July 1988 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Oyster Creek, Technical Evaluation Rept ML20238D0211987-07-31031 July 1987 Conformance to Reg Guide 1.97:Oyster Creek, Interim Technical Evaluation Rept ML20215L7481987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety Related Components: Oyster Creek, Final Informal Rept ML20214R3841987-03-31031 March 1987 Followup SEP Evaluation of Part of Remaining Open Items for Oyster Creek Nuclear Power Plant ML20212C0721986-08-0404 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Oyster Creek Plant, Supplementary Technical Evaluation Rept ML20211N8751986-06-30030 June 1986 Draft Conformance to Reg Guide 1.97,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20210C3071986-03-19019 March 1986 Final Supplementary Rept,Review of Licensee Responses to SEP Topic III-7.B,Design Codes,Design Criteria & Loading Combinations,Oyster Creek ML20136G4791985-11-0404 November 1985 Masonary Wall Design, Technical Evaluation Rept ML20138L7171985-07-10010 July 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions...Atws Events),Item 1.2, 'Post-Trip Review:Data & Info Capabilities' for Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20151K8961985-05-20020 May 1985 Evaluation of Dcrdr Summary Rept for Oyster Creek Nuclear Generating Station, Supplemental Technical Evaluation Rept ML20115A4171985-01-11011 January 1985 Evaluation of Isolation Condenser Cracks at Oyster Creek Unit 1 ML20140C9991984-10-31031 October 1984 Review of Wind & Tornado Loading Responses,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20094L1551984-07-20020 July 1984 Evaluation of Detailed Control Room Design Review Summary Rept for Oyster Creek Nuclear Generating Station, Final Technical Rept ML20093C7781984-07-0505 July 1984 Evaluation of Spent Fuel Racks Structural Analysis,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20082C0881983-10-31031 October 1983 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Final Report: September 1,1976 - December 31,1982 ML20083J3231983-09-30030 September 1983 Technical Evaluation of Oyster Creek Plant Unique Analysis Repts ML20092N6501983-08-31031 August 1983 Technical Evaluation of Integrity of Oyster Creek Reactor Coolant Boundary Piping Sys ML20080E2641983-08-30030 August 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20079Q7121983-06-10010 June 1983 Control of Heavy Loads (C-10),JCP&L Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20076J4031983-04-0606 April 1983 RCS Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20076C4231983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Jcp&L, Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20070L7311982-12-31031 December 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Docket No. 50-219.(General Public Utilities) ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070J3311982-11-30030 November 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,March - May 1982 ML20071N2601982-09-30030 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A9061982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20065B8501982-08-31031 August 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,December 1981-Februaury 1982 ML20140B7651982-07-31031 July 1982 Review of Operating Experience History of Oyster Creek Through 1981 for NRC SEP, Final Rept ML20027D2261982-07-31031 July 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20058B1171982-06-30030 June 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,September-November 1981 ML20054L4961982-06-0909 June 1982 Hydrological Considerations (SEP,II-3.A,B,B.1,3.C) Jcp&L, Oyster Creek Nuclear Power Plant, Revised Technical Evaluation Rept ML20054E4181982-06-0808 June 1982 Wind & Tornado Loadings (SEP III-2), Technical Evaluation Rept ML20063G7771982-05-31031 May 1982 SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads ML20062A4881982-04-30030 April 1982 Safety Evaluation Rept,Pump & Valve Inservice Testing Program,Oyster Creek Nuclear Generating Station, Interim Rept ML20052H4361982-04-30030 April 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20052B5811982-04-28028 April 1982 Design Codes,Design Criteria, & Loading Combinations (SEP III-7.B) Jersey Central Power & Light Co,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20053D2141982-04-27027 April 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20052D4851982-03-31031 March 1982 Draft SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads. ML20049H9691982-02-18018 February 1982 Comparison of Plant & Model Radiological Effluent Tech Specs,Gpu Nuclear Corp, Draft Radiological Effluent Tech Spec Implementation ML20064L0711982-01-27027 January 1982 Technical Evaluation Rept for BWR Scram Discharge Vol Long-Term Mods Oyster Creek Nuclear Generating Station ML19348A0541981-08-31031 August 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Power Station,Unit 1. ML20010D8041981-07-31031 July 1981 Preliminary Adequacy of Station Electric Distribution Sys Voltages,Oyster Creek Nuclear Power Station, Technical Evaluation Rept ML20009E0601981-07-17017 July 1981 Changes Report Number to NUREG/CR-1939,Volume 1, Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station ML20009F1651981-06-30030 June 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Station Unit 1, Technical Evaluation Rept ML20010B3911981-06-10010 June 1981 Draft Technical Evaluation:Sep Topic VI-4, Electrical, Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML20010A0171981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Oyster Creek Nuclear Power Plant. Setpoint Requirements Have Been Met ML20049J1871981-05-21021 May 1981 Containment Leakage Rate Testing, Technical Evaluation Rept ML20008F7661981-04-30030 April 1981 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station 1997-04-10
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20199G8601997-04-10010 April 1997 Rev 0 to Technical Evaluation of Oyster Creek Nuclear Generating Station Analysis of Cable Ampacity Limits 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 ML20205L0091988-07-31031 July 1988 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Oyster Creek, Technical Evaluation Rept ML20238D0211987-07-31031 July 1987 Conformance to Reg Guide 1.97:Oyster Creek, Interim Technical Evaluation Rept ML20215L7481987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety Related Components: Oyster Creek, Final Informal Rept ML20214R3841987-03-31031 March 1987 Followup SEP Evaluation of Part of Remaining Open Items for Oyster Creek Nuclear Power Plant ML20212C0721986-08-0404 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Oyster Creek Plant, Supplementary Technical Evaluation Rept ML20211N8751986-06-30030 June 1986 Draft Conformance to Reg Guide 1.97,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20210C3071986-03-19019 March 1986 Final Supplementary Rept,Review of Licensee Responses to SEP Topic III-7.B,Design Codes,Design Criteria & Loading Combinations,Oyster Creek ML20136G4791985-11-0404 November 1985 Masonary Wall Design, Technical Evaluation Rept ML20138L7171985-07-10010 July 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions...Atws Events),Item 1.2, 'Post-Trip Review:Data & Info Capabilities' for Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20151K8961985-05-20020 May 1985 Evaluation of Dcrdr Summary Rept for Oyster Creek Nuclear Generating Station, Supplemental Technical Evaluation Rept ML20115A4171985-01-11011 January 1985 Evaluation of Isolation Condenser Cracks at Oyster Creek Unit 1 ML20140C9991984-10-31031 October 1984 Review of Wind & Tornado Loading Responses,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20094L1551984-07-20020 July 1984 Evaluation of Detailed Control Room Design Review Summary Rept for Oyster Creek Nuclear Generating Station, Final Technical Rept ML20093C7781984-07-0505 July 1984 Evaluation of Spent Fuel Racks Structural Analysis,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20082C0881983-10-31031 October 1983 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Final Report: September 1,1976 - December 31,1982 ML20083J3231983-09-30030 September 1983 Technical Evaluation of Oyster Creek Plant Unique Analysis Repts ML20092N6501983-08-31031 August 1983 Technical Evaluation of Integrity of Oyster Creek Reactor Coolant Boundary Piping Sys ML20080E2641983-08-30030 August 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20079Q7121983-06-10010 June 1983 Control of Heavy Loads (C-10),JCP&L Oyster Creek Nuclear Power Plant, Technical Evaluation Rept ML20076J4031983-04-0606 April 1983 RCS Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20076C4231983-01-27027 January 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Jcp&L, Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20070L7311982-12-31031 December 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Docket No. 50-219.(General Public Utilities) ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070J3311982-11-30030 November 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,March - May 1982 ML20071N2601982-09-30030 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A9061982-08-31031 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20065B8501982-08-31031 August 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,December 1981-Februaury 1982 ML20140B7651982-07-31031 July 1982 Review of Operating Experience History of Oyster Creek Through 1981 for NRC SEP, Final Rept ML20027D2261982-07-31031 July 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20058B1171982-06-30030 June 1982 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station.Progress Report,September-November 1981 ML20054L4961982-06-0909 June 1982 Hydrological Considerations (SEP,II-3.A,B,B.1,3.C) Jcp&L, Oyster Creek Nuclear Power Plant, Revised Technical Evaluation Rept ML20054E4181982-06-0808 June 1982 Wind & Tornado Loadings (SEP III-2), Technical Evaluation Rept ML20063G7771982-05-31031 May 1982 SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads ML20062A4881982-04-30030 April 1982 Safety Evaluation Rept,Pump & Valve Inservice Testing Program,Oyster Creek Nuclear Generating Station, Interim Rept ML20052H4361982-04-30030 April 1982 Restart of Core Spray & Low Pressure Coolant Injection Sys, NUREG-0737,Item II.K.3.21,Oyster Creek Nuclear Generating Station. ML20052B5811982-04-28028 April 1982 Design Codes,Design Criteria, & Loading Combinations (SEP III-7.B) Jersey Central Power & Light Co,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept ML20053D2141982-04-27027 April 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20052D4851982-03-31031 March 1982 Draft SEP Structural Review of Oyster Creek Nuclear Power Plant Drywell Containment Structure Under Combined Loads. ML20049H9691982-02-18018 February 1982 Comparison of Plant & Model Radiological Effluent Tech Specs,Gpu Nuclear Corp, Draft Radiological Effluent Tech Spec Implementation ML20064L0711982-01-27027 January 1982 Technical Evaluation Rept for BWR Scram Discharge Vol Long-Term Mods Oyster Creek Nuclear Generating Station ML19348A0541981-08-31031 August 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Power Station,Unit 1. ML20010D8041981-07-31031 July 1981 Preliminary Adequacy of Station Electric Distribution Sys Voltages,Oyster Creek Nuclear Power Station, Technical Evaluation Rept ML20009E0601981-07-17017 July 1981 Changes Report Number to NUREG/CR-1939,Volume 1, Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station ML20009F1651981-06-30030 June 1981 Degraded Grid Protection for Class IE Power Sys,Oyster Creek Nuclear Station Unit 1, Technical Evaluation Rept ML20010B3911981-06-10010 June 1981 Draft Technical Evaluation:Sep Topic VI-4, Electrical, Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML20010A0171981-05-31031 May 1981 Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Oyster Creek Nuclear Power Plant. Setpoint Requirements Have Been Met ML20049J1871981-05-21021 May 1981 Containment Leakage Rate Testing, Technical Evaluation Rept ML20008F7661981-04-30030 April 1981 Ecological Studies of WOOD-BORING Bivalves in the Vicinity of the Oyster Creek Nuclear Generating Station 1997-04-10
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t SAIC-85/1526 REVIEW 0F LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2
" POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR OYSTER CREEK NUCLEAR POWER PLANT (50-219)
DRAFT i
l July 10, 1985 j ~ .
O R A P'r Technical Evaluation Report Prepared by Science Applications International Corporation 1710 Goodridge Drive McLean, Virginia 22102 i
Prepared for U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i
Contract No. NRC-03-82-096 '
8510310390 851024 PDR ADOCK 05000219 l P pg
FOREWORD This report contains the technical evaluation of the Oyster Creek Nuclear Power Plant response to Generic Letter 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2 " Post Trip Review:
Data and Information Capabilities."
For the purposes of this evaluation, the review criteria, presented in part 2 of this report, were divided into five separate categories. These are:
- 1. The parameters monitored by the sequence of events and the time history recorders,
- 2. The performance characteristics of the sequence of events recorders,
- 3. The performance characteristics of the time history recorders,
- 4. The data output format, and
- 5. The long-term data retention capability for post-trip review material.
All available responses to Generic Letter 83-28 were evaluated. The i plant for which this report is applicable was found to have adequately responded to, and met, category 3.
The report describes the specific methods used to determine the cate-gorization of the responses to Generic Letter 83-28. Since this evaluation report was intended to apply to more than one nuclear power plant specifics regarding how each plant met (or failed to meet) the review criteria are not presented. Instead, the evaluation presents a categorization of the responses according to which categories of review criteria are satisfied and which are not. The evaluations are based on specific criteria (Section 2) derived from the requirements as stated in the generic letter.
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! TABLE OF CONTENTS
, Section Page Introduction. . . . . . . . . . . . . . . . . . . . . . . . . I t
l 1. Background. . . . . . . . . . . . . . . . . . . . . . . . . . 2
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- 2. Review Criteria . . . . . . . . . . . . . . . . . . . . . . . 3
, 3. Evaluation. . . . . . . . . . . . . . . . . . . . . . . . . . 8 4 Co n cl u s i o n . . . . . . . . . . . . . . . . . . . . . . . . . . 9 1
- 5. References. . . . . . . . . . . . . . . . . . . . . . . . . . 10 (o. S U A *a s T z A V #0suMef Pot Telecon? - - - -
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INTRODUCTION I
SAIC has ! viewed the utility's response to Generic Letter 83-28, item 1.2 " Post-Trip Review: Data and Information Capability." The response (see references) contained sufficient information to determine that the data and
. information capabilities at this plant are acceptable in the following area.
e The time history recorder (s) performance characteris-tics.
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However, the data and information capabilities, as described in the submittal, either fail to meet the review criteria or provide insufficient information to allow determination of the adequacy of the data and information capabilities in the following areas.
.e The pas ameters monitored by both the sequence-of-events and time history recorders.
e The sequence-of-events recorder (s) performance charac-teristics.
4 e The output format of the recorded data.
e The long-term data retention, record keeping, capa-bility.
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DRAFT i
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- 1. Background A
'I n On February 25, 1984, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during the plant startup and the reactor was tripped manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the under voltage trip attachment. Prior to this incident; on February 22, 1933; at Unit 1 of the Salem Nuclear Power Plant an automatic trip signal was generated based on steam generator low-low level during plant startup.
In this case the reactor was tripped manually by the operator almost coinci-2 dentally with the automatic trip. At that time, because the utility did not have a requirement for the systematic evaluation of the reactor trip, no investigation was cerformed to determine whether the reactor was tripped automatically as expected or manually. The utilities' written procedures 4
required only that the cause of the trip be determined and identified the responsible personnel that could authorize a restart if the cause of the i trip is known. Following the second trip which clearly indicated the q problem with the trip breakers, the question was raised on whether the i circuit breakers had functioned properly during the earlier incident. Thr most useful source of information in this case, namely the sequence r f events printout which would have indicated whether the reactor was tripped automatically or manually during the February 22 incident, was not retained after the incident. Thus, no judgment on the proper functioning of the trip system during the earlier incident could be made.
Following these incidents; on February 28, 1983; the NRC Executive Director for Operations (E00), directed the staff to investigate and report
, on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staf f's inquiry into the generic 1
implications of the Salem Unit incidents is reported in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." Based on the results of this study, a set of required actions were developed and included in Generic Letter 83-28 which was issued on July 8,1983 and sent to all licensees of operating reactors, applicants for operating license, and j construction permit holders. The required actions in this generic letter consist of four categories. These are: (1) Post-Trip Review, (2) Equipment l A l
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DRAFI Classification and Vender Interface, (3) Post Maintenance Testing, and (4)
Reactor Trip System Reliability Improvements.
The first required action of the generic letter, Post-Trip Review, is the subject of this TER and consists of action item 1.1 " Program Description and Procedure" and action item 1.2 " Data and Information Capability." In the next section the review criteria used to assess the adequacy of the utilities' responses to the requirements of action item 1.2 will be i
discussed.
- 2. Review Criteria j The intent of the Post Trip Review requirements of Generic Letter 83-28 is to ensure that the licensee has adequate procedures and data and information sources to understand the cause(s) and progression of a reactor trip. This understanding should go beyond a simple identification of the course of the event. I,t should include the capability to determine the root cause of the reactor trip and to determine whether safety limits have been exceeded and if so to what extent. Sufficient information about the reactor trip event should be available so that a decision on the acceptability of a reactor restart can be made.
The following are the review criteria developed for the requirements of Generic Letter 83-28, action item 1.2:
I The equipment that provides the digital. sequence of events (SOE) record and the analog time history records of an unscheduled shutdown should pro-vide a reliable source of the necessary information to be used in the post j trip review. Each plant variable which is necessary to determine the l cause(s) and progression of the event (s) following a plant trip should be monitored by at least one recorder [such as a sequence-of-events recorder or a plant process computer for digital parameters; and strip charts, a plant
! process computer or analog recorder for analog (time history) variables].
l Each device used to record an analog or digital plant variable should be l
described in sufficient detail so that a determination can be made as to whether the following performance characteristics are met:
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DRAFT e Each sequence-of-events recorder should be capable of detecting and recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses asso-ciated with each monitored safety-related system can be ascer-tained, and that a determination can be made as to whether the time response is within acceptable limits based c,n FSAR Chapter 15 Accident Analyses. The recommended guideline for the SOE time discrimination is approximately 100 msec. If current SOE recorders do not have this time discrimination capability the licensee or applicant should show that the current time discrimi-nation capability is sufficient for an adequate reconstruction of the course of the reactor trip. As a minimum this should include the ability to adequately reconstruct the accident scenarios pre-sented in Chapter 15 of the plant FSAR.
e Each analog time history data recorder should have a sample inter-
. . val small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the licensee or applicant should be able to reconstruct the course of the accident sequences evaluated in the accident analysis of the plant FSAR (Chapter 15). The recommended guideline for the sample interval is 10 sec. If the time history equipment does not meet this guideline, the licensee or applicant should show that the current time history capability is sufficient to accurately recon-struct the accident sequences presented in Chapter 15 of the FSAR.
e To support the post trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should be capable of updating and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
e The information gathered by the sequence-of-events and time history data collectors should be stored in a manner that will j
allow for retrieval and analysis. The data may be retained in either hardcopy (computer printout, strip chart output, etc.) or in an accessible memory (magnetic disc or tape). This information should be presented in a readable and meaningful format, taking 4
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i DRAFT into consideration good human factors practices (such as those outlined in NUREG-0700).
e All equipment used to record sequence of events and tis,1e history information should be powered from a reliable and non-interruptible power source. The power source used need not be safety related.
The sequence of events and time history recording equipment should monitor sufficient digital and ar.alog parameters, respectively, to assure that the course of the reactor trip can be reconstructed. The parameters 4
monitored should provide sufficient information to determine the root cause of the reactor trip, the progression of the reactor trip, and the response of the plant parameters and systems to the reactor trip. Specifically, all input parameters associated with reactor trips, safety injections and other
- safety-related systems as well as output parametcrs sufficient to record the proper functioning of these systems should be recorded for use in the post trip review. The parameters deemed necessary, as a minimum, to perform a post-trip review (one that would determine if the plant remained within its design envelope) are presented on Tables 1.2-1 and 1.2-2. If the appli-cants' or licensees' SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables the applicant or licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope for the appro-priate accident conditions; such as those analyzed in Chapter 15 of the i plant Safety Analysis Report. ,
Information gathered during the post trip review is required input for future post trip reviews. Data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to future unscneduled shut-downs. It is therefore necessary that information gathered during all post trip reviews be maintained in an accessible manner for the life of the plant. )
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DRAFT Table 1.2-1. PWR Parameter List SOE Time History Recorder Recorder Parameter / Signal x Reactor Trip (1) x Safety Injection x Containment Isolation (1) x Turbine Trip x Control Rod Position (1) x x Neutron Flux, Power x x Containment Pressure (2) Containment Radiation x Containment Sump Level (1) x x Primary System Pressure (1) x x Primary System Temperature (1) x Pressurizer Level (1) x Reactor Coolant Pump Status (1) x x Primary System Flow (3) Safety Inj.; Flow, Pump / Valve Status x MSIV Position x x Steam Generator Pressure (1) x x Steam Generator Level (1) x x Feedwater Flow (1) x x Steam Flow (3) Auxiliary Feedwater System; Flow.
Pump /Value Status x AC and DC System Status (Bus Voltage) x Diesel Generator Status (Start /Stop, On/0ff) x DORV Position (1): Trip parameters (2): Parameter may be monitored by either an SOE or time history reconder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
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DRAFT Table 1.2-2. BWR Parameter List SOE Time History Recorder Recorder Parameter / Signal x Reactor Trip x Safety Injection x Containment Isolation x Turbine Trip x Control Rod Position x (1) x Neutron Flux, Power x '1) Main Steam Radiation
(. ) Containment (Dry Well) Radiation x (1 x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x (1) x Primary System Pressure x (1) x Primaiy System level x MSIV Position x.(1) Turbine Stop Valve / Control Valve Position x Turbine Bypass Valve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow, Pump Status
- x (1) Scram Discharge Level x(1) ,
Condenser Vacuum x AC and DC System Status (Bus Voltage)
(3)(4) Safety Injection; Flow. Pump / Valve Status x Diesel Generator Status (On/Off, Start /Stop)
(1): Trip pasamete-s.
(2): Parameter may be recorded by either an SOE or time history recorder.
.(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c)equipmentstatusrecordedonanSOErecorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
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- 3. Evaluation DMR J
The parameters identified in part 2 of this report as a part of the review criteria are those deemed necessary to perform an adequate post-trip
- review. The recording of these parameters on equipment that meets the guidelines of the review criteria will result in a source of information that can be used to determine the cause of the reactor trip and the plant response to the trip, including the responses of important plant systems.
The parameters identified in this submittal as being recorded by the sequence of events and time history recorders do not correspond to the parameters specified in part 2 of this report.
The review criteria require that the equipment being used to record the I
sequence of events and time history data needed for a post-trip review meet certain performance characteristics. These characteristics are intended to ensure that, if the proper parameters are recorded, the recording equipment
- will provide an adequate source of information for an effective post-trip review. The information provided in this submittal does not indicate that the SOE equipment used would meet the intent of the performance criteria outlined in part 2 of this report. Information supplied in the submittal does indicate that the time history equipment meets the performance criteria specified in part 2 of this report.
The data and information recorded for use in the post-trip review should be output in a format that allows for ease of identification and use -
of the data to meet the review criterion that calls for information in a readable and meaningful format. The information contained in this submittal does not indicate that this criterion is met.
The data and information used during a post-trip review should be
- retained as part of the plant files. This information could prove useful during future post-trip reviews. Therefore, one criterion is that infor-mation used during a post-trip review be maintained in an accessible manner for the life of the plant. The information contained within this submittal does not indicate that this criterion will be met.
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- 4. Conclusion sun The information supplied in response to Generic Letter 83-28 indicates that the current post-trip review data and information capabilities are adequate in the following areas:
- 1. The time history recorders meet the minimum performance require-ments.
The information supplied in response to Generic Letter 83-28 does not indicate that the post-trip review data and information capabilities are adequate in the following areas.
'1. Based upon the information contained in the submittal, all of the parameters specified in part 2 of this report that should be recorded for use in a post-trip review are not recorded.
l 2. SOE recorders, as described in the submittal, do not r..eet the minimum performance characteristics.
- 3. As described in the submittal, the recorded data may not be output in a readable and meaningful format.
- 4. The data retention procedures, as described in the submittal, may not ensure that the information recorded for the post-trip review is maintained in an accessible manner for the life of the plant.
It is possible that the current data and information capabilities at this
- nuclear power plant are adequate to meet the intent of these review l criteria, but were not completely described. Under these circumstances, the licensee should provide an updated, more complete, description to show in more detail the data and information capabilities at this nuclear power I
plant. If the information provided accurately represents all current data and information capabilties, then the licensee should show that the existing data and information capabilities are sufficient to meet the intent of the i evaluation criteria in part 2 of this report, or detail future modifications that would enable the licensee to meet the intent of the evaluation criteria.
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REFERENCES NRC Generic Letter 83-28. " Letter to all licensees of operating reactors, applicants for operating license, and holders of construction permits regarding Required Actions Based on Generic Implications of Salem ATWS Events." July 8, 1983.
NUREG-1000 Generic Implications of ATWS Events at the Salem Nuclear Power Plant April 1983.
Letter from P.B. Fiedler, GPU Nuclear Corporation, to USNRC, dated November 14, 1983, Accession Number 8311280529 in response to Generic Letter 83-28 of July 8,1983, with attachment.
Letter from J. Knubel, GPU Nuclear Corporation, to J. Lombardo, USNRC, dated February 22, 1984, Accession Number 8402280286, providing a corrected page for the attachment to their November 14, 1983 letter.
Letter from P.B. Fiedler, GPU Nuclear Corporation, to USNRC, dated August 16, 1984 Accession Number 8408220356 providing information relative to the schedule for Item 4.5.3 of Generic Letter 83-28.
Letter from P.B. Fiedler, GPU Nuclear Corporation, to USNRC, dated November 20, 1984, Accession Number 8411270262 providing further information ir. response to Generic Letter 83-28, with attachment.
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11 RAFT Oyster Creek
- 1. Parameters recorded: Unsatisfactory See attached table for discrepancies.
- 2. SOE recorders performance characteristics: Unsatis factory Sequence of events recorder: non-interruptible power supply but time discrimination is approximately 500 milliseconds
- 3. Time history recorders performance characteristics: Satisfactory Plant process computer: 1 sec sample interval for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> post-trip; powered through interruptible power supply Strip charts: non-interruptible power supply (Process computer does not record any additional parameters not recorded by strip charts; therefore, strip charts were considered primary analog record and continuous output meets the intent of analog performance characteristics.)
4 Data output format: Unsatisfactory Sequence of event format was not described.
Analog data format is probably acceptable.
- 5. Data retention capability: Unsatisfactory The length of time the data is to be retained is not specified.
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Desirable BWR Parameters for Post-Trip Review (circled parameters are not recorded)
SOE Time History Recorder Recorder Parameter / Signal Reactor Trip Safety Injection Containment Isolation Turbine Trip
@ Control Rod Position x (1) x Neutron Flux, Power x (1) Main Steam Radiation
@ Containment (Dry Well) Radiation x (1) x Drywell Pressure (Containment Pressure)
@ Suppression Pool Temperature x (1) x Primary System Pressure x (1) x Primary System level x
MSIV Position
@(1) Turbine Stop Valve / Control Valve Position
@ Turbine Bypass Valve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow Pump Status x (1) Scram Discharge Level x (1) Condenser Vacuum AC and DC System Status (Bus Voltage)
@ @ (4) Safety Injection; Flow. Pump / Valve Status
@ Diesel Generator Status (On/Off, Start /Stop)
(1): Trip parameters.
(2): Parameter may be recorded by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder. (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
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