Letter Sequence Other |
---|
|
|
MONTHYEARML20235M3941987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Vermont Yankee, Informal Rept Project stage: Other ML20246D7591989-08-21021 August 1989 Forwards SER Accepting Util Responses to Generic Ltr 83-28, Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events Project stage: Approval 1987-06-30
[Table View] |
|
---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20134D1931996-07-31031 July 1996 Review of Plant Implementation of Soultion I-D:Use of LAPUR-5 for Exclusion Region Calculations ML20100F0611995-11-30030 November 1995 TER on Ipe,Front End Analysis ML20100F0861995-11-30030 November 1995 TER of Vermont Yankee Ipe,Back End Submittal, Final Rept ML20100F0681995-11-20020 November 1995 TER of IPE Submittal,Human Reliability Analysis, Final Rept L-95-005, Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan1995-04-30030 April 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan ML20082A6391994-09-30030 September 1994 Review of Technical Issues Related to Long Term Solution I-D 'Regional Exclusion w/Flow-Biased APRM Scram.' ML20063H2711994-01-31031 January 1994 Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01: Vermont Yankee, Technical Evalution Rept ML20056D2711993-06-30030 June 1993 TER Pump & Valve Inservice Testing Program Vermont Yankee Nuclear Power Station ML20106B2891992-07-31031 July 1992 Technical Evaluation Rept of FROSSTEY-2 Fuel Performance Code ML20029A6391990-09-30030 September 1990 Review of Huxy Code for Determining Radiation View Factors for Vermont Yankee, Technical Evaluation Rept ML20065C8351990-05-31031 May 1990 Conformance to Reg Guide 1.97:Vermont Yankee, Technical Evaluation Rept ML20246P3281988-05-31031 May 1988 Technical Evaluation Rept for Evaluation of ODCM Updated Through Rev 4,Vermont Yankee Nuclear Power Station ML20148C6071988-01-31031 January 1988 Review of the Natural Circulation Effect in the Vermont Yankee SPENT-FUEL Pool.Docket No. 50-271.(Vermont Yankee Nuclear Power Corp) ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20235M3941987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Vermont Yankee, Informal Rept ML20235N4471987-06-30030 June 1987 Final Technical Evaluation Rept:Review & Evaluation of RELAP5YA Computer Code & Vermont Yankee LOCA Licensing Analysis Model for Use in Small & Large Break BWR Locas, Informal Rept ML20214H0941986-07-14014 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Vermont Yankee Nuclear Station, Supplemental Technical Evaluation Rept ML20138G7891985-10-15015 October 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic ...), Item 1.2 `Post-Trip Review:Data & Info Capabilities' for Vermont Yankee Nuclear Power Station ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20128F4131985-05-0303 May 1985 In-Progress Audit of Dcrdr for Vermont Yankee Nuclear Power Plant ML20106J6471984-08-0909 August 1984 Evaluation of Detailed Control Room Design Review Program Plan Vermont Yankee Nuclear Power Plant ML20092A7521984-06-15015 June 1984 Control of Heavy Loads (C-10),Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20090H6841984-03-16016 March 1984 Monitoring of Electric Power to Reactor Protection Sys for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20093C3821983-09-27027 September 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20093A5831983-07-31031 July 1983 Technical Evaluation of Integrity of Vermont Yankee Nuclear Power Station Reactor Coolant Boundary Piping Sys ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070T7321982-11-30030 November 1982 Control of Heavy Loads (C-10) VT Yankee Nuclear Power Station, Draft Technical Evaluation Rept.Request for Addl Info Encl ML20076B6231982-09-27027 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Vt Yankee Atomic Power Station, Technical Evaluation Rept ML20071N8301982-09-0303 September 1982 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20071J5661982-09-0202 September 1982 VT Yankee Nuclear Power Station Inservice Insp Program, Technical Evaluation Rept ML20197F8191982-08-25025 August 1982 Proposed Design Mods & Tech Specs Changes on Grid Voltage Degradation for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20064L4921982-06-30030 June 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Technical Evaluation Rept ML20042A9621982-02-11011 February 1982 Operating Reactor Power Operated Relief Valves & ECCS Repts, Request for Addl Info ML19331D9941980-07-21021 July 1980 Primary Coolant Sys Pressure Isolation Valves,Vt Yankee Unit 1, Technical Evaluation Rept ML19305D4041980-02-29029 February 1980 Safety Evaluation Rept,Inservice Testing Program. 1996-07-31
[Table view] Category:QUICK LOOK
MONTHYEARML20134D1931996-07-31031 July 1996 Review of Plant Implementation of Soultion I-D:Use of LAPUR-5 for Exclusion Region Calculations ML20100F0611995-11-30030 November 1995 TER on Ipe,Front End Analysis ML20100F0861995-11-30030 November 1995 TER of Vermont Yankee Ipe,Back End Submittal, Final Rept ML20100F0681995-11-20020 November 1995 TER of IPE Submittal,Human Reliability Analysis, Final Rept L-95-005, Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan1995-04-30030 April 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan ML20082A6391994-09-30030 September 1994 Review of Technical Issues Related to Long Term Solution I-D 'Regional Exclusion w/Flow-Biased APRM Scram.' ML20063H2711994-01-31031 January 1994 Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01: Vermont Yankee, Technical Evalution Rept ML20056D2711993-06-30030 June 1993 TER Pump & Valve Inservice Testing Program Vermont Yankee Nuclear Power Station ML20106B2891992-07-31031 July 1992 Technical Evaluation Rept of FROSSTEY-2 Fuel Performance Code ML20029A6391990-09-30030 September 1990 Review of Huxy Code for Determining Radiation View Factors for Vermont Yankee, Technical Evaluation Rept ML20065C8351990-05-31031 May 1990 Conformance to Reg Guide 1.97:Vermont Yankee, Technical Evaluation Rept ML20246P3281988-05-31031 May 1988 Technical Evaluation Rept for Evaluation of ODCM Updated Through Rev 4,Vermont Yankee Nuclear Power Station ML20148C6071988-01-31031 January 1988 Review of the Natural Circulation Effect in the Vermont Yankee SPENT-FUEL Pool.Docket No. 50-271.(Vermont Yankee Nuclear Power Corp) ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20235M3941987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Vermont Yankee, Informal Rept ML20235N4471987-06-30030 June 1987 Final Technical Evaluation Rept:Review & Evaluation of RELAP5YA Computer Code & Vermont Yankee LOCA Licensing Analysis Model for Use in Small & Large Break BWR Locas, Informal Rept ML20214H0941986-07-14014 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Vermont Yankee Nuclear Station, Supplemental Technical Evaluation Rept ML20138G7891985-10-15015 October 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic ...), Item 1.2 `Post-Trip Review:Data & Info Capabilities' for Vermont Yankee Nuclear Power Station ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20128F4131985-05-0303 May 1985 In-Progress Audit of Dcrdr for Vermont Yankee Nuclear Power Plant ML20106J6471984-08-0909 August 1984 Evaluation of Detailed Control Room Design Review Program Plan Vermont Yankee Nuclear Power Plant ML20092A7521984-06-15015 June 1984 Control of Heavy Loads (C-10),Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20090H6841984-03-16016 March 1984 Monitoring of Electric Power to Reactor Protection Sys for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20093C3821983-09-27027 September 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20093A5831983-07-31031 July 1983 Technical Evaluation of Integrity of Vermont Yankee Nuclear Power Station Reactor Coolant Boundary Piping Sys ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070T7321982-11-30030 November 1982 Control of Heavy Loads (C-10) VT Yankee Nuclear Power Station, Draft Technical Evaluation Rept.Request for Addl Info Encl ML20076B6231982-09-27027 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Vt Yankee Atomic Power Station, Technical Evaluation Rept ML20071N8301982-09-0303 September 1982 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20071J5661982-09-0202 September 1982 VT Yankee Nuclear Power Station Inservice Insp Program, Technical Evaluation Rept ML20197F8191982-08-25025 August 1982 Proposed Design Mods & Tech Specs Changes on Grid Voltage Degradation for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20064L4921982-06-30030 June 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Technical Evaluation Rept ML20042A9621982-02-11011 February 1982 Operating Reactor Power Operated Relief Valves & ECCS Repts, Request for Addl Info ML19331D9941980-07-21021 July 1980 Primary Coolant Sys Pressure Isolation Valves,Vt Yankee Unit 1, Technical Evaluation Rept ML19305D4041980-02-29029 February 1980 Safety Evaluation Rept,Inservice Testing Program. 1996-07-31
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20134D1931996-07-31031 July 1996 Review of Plant Implementation of Soultion I-D:Use of LAPUR-5 for Exclusion Region Calculations ML20100F0611995-11-30030 November 1995 TER on Ipe,Front End Analysis ML20100F0861995-11-30030 November 1995 TER of Vermont Yankee Ipe,Back End Submittal, Final Rept ML20100F0681995-11-20020 November 1995 TER of IPE Submittal,Human Reliability Analysis, Final Rept L-95-005, Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan1995-04-30030 April 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan ML20082A6391994-09-30030 September 1994 Review of Technical Issues Related to Long Term Solution I-D 'Regional Exclusion w/Flow-Biased APRM Scram.' ML20063H2711994-01-31031 January 1994 Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01: Vermont Yankee, Technical Evalution Rept ML20056D2711993-06-30030 June 1993 TER Pump & Valve Inservice Testing Program Vermont Yankee Nuclear Power Station ML20106B2891992-07-31031 July 1992 Technical Evaluation Rept of FROSSTEY-2 Fuel Performance Code ML20029A6391990-09-30030 September 1990 Review of Huxy Code for Determining Radiation View Factors for Vermont Yankee, Technical Evaluation Rept ML20065C8351990-05-31031 May 1990 Conformance to Reg Guide 1.97:Vermont Yankee, Technical Evaluation Rept ML20246P3281988-05-31031 May 1988 Technical Evaluation Rept for Evaluation of ODCM Updated Through Rev 4,Vermont Yankee Nuclear Power Station ML20148C6071988-01-31031 January 1988 Review of the Natural Circulation Effect in the Vermont Yankee SPENT-FUEL Pool.Docket No. 50-271.(Vermont Yankee Nuclear Power Corp) ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20235M3941987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Vermont Yankee, Informal Rept ML20235N4471987-06-30030 June 1987 Final Technical Evaluation Rept:Review & Evaluation of RELAP5YA Computer Code & Vermont Yankee LOCA Licensing Analysis Model for Use in Small & Large Break BWR Locas, Informal Rept ML20214H0941986-07-14014 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Vermont Yankee Nuclear Station, Supplemental Technical Evaluation Rept ML20138G7891985-10-15015 October 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic ...), Item 1.2 `Post-Trip Review:Data & Info Capabilities' for Vermont Yankee Nuclear Power Station ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20128F4131985-05-0303 May 1985 In-Progress Audit of Dcrdr for Vermont Yankee Nuclear Power Plant ML20106J6471984-08-0909 August 1984 Evaluation of Detailed Control Room Design Review Program Plan Vermont Yankee Nuclear Power Plant ML20092A7521984-06-15015 June 1984 Control of Heavy Loads (C-10),Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20090H6841984-03-16016 March 1984 Monitoring of Electric Power to Reactor Protection Sys for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20093C3821983-09-27027 September 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20093A5831983-07-31031 July 1983 Technical Evaluation of Integrity of Vermont Yankee Nuclear Power Station Reactor Coolant Boundary Piping Sys ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070T7321982-11-30030 November 1982 Control of Heavy Loads (C-10) VT Yankee Nuclear Power Station, Draft Technical Evaluation Rept.Request for Addl Info Encl ML20076B6231982-09-27027 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Vt Yankee Atomic Power Station, Technical Evaluation Rept ML20071N8301982-09-0303 September 1982 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20071J5661982-09-0202 September 1982 VT Yankee Nuclear Power Station Inservice Insp Program, Technical Evaluation Rept ML20197F8191982-08-25025 August 1982 Proposed Design Mods & Tech Specs Changes on Grid Voltage Degradation for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20064L4921982-06-30030 June 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Technical Evaluation Rept ML20042A9621982-02-11011 February 1982 Operating Reactor Power Operated Relief Valves & ECCS Repts, Request for Addl Info ML19331D9941980-07-21021 July 1980 Primary Coolant Sys Pressure Isolation Valves,Vt Yankee Unit 1, Technical Evaluation Rept ML19305D4041980-02-29029 February 1980 Safety Evaluation Rept,Inservice Testing Program. 1996-07-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20134D1931996-07-31031 July 1996 Review of Plant Implementation of Soultion I-D:Use of LAPUR-5 for Exclusion Region Calculations ML20100F0611995-11-30030 November 1995 TER on Ipe,Front End Analysis ML20100F0861995-11-30030 November 1995 TER of Vermont Yankee Ipe,Back End Submittal, Final Rept ML20100F0681995-11-20020 November 1995 TER of IPE Submittal,Human Reliability Analysis, Final Rept L-95-005, Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan1995-04-30030 April 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan ML20082A6391994-09-30030 September 1994 Review of Technical Issues Related to Long Term Solution I-D 'Regional Exclusion w/Flow-Biased APRM Scram.' ML20063H2711994-01-31031 January 1994 Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01: Vermont Yankee, Technical Evalution Rept ML20056D2711993-06-30030 June 1993 TER Pump & Valve Inservice Testing Program Vermont Yankee Nuclear Power Station ML20106B2891992-07-31031 July 1992 Technical Evaluation Rept of FROSSTEY-2 Fuel Performance Code ML20029A6391990-09-30030 September 1990 Review of Huxy Code for Determining Radiation View Factors for Vermont Yankee, Technical Evaluation Rept ML20065C8351990-05-31031 May 1990 Conformance to Reg Guide 1.97:Vermont Yankee, Technical Evaluation Rept ML20155B7391988-06-0101 June 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20155B7531988-06-0101 June 1988 Corrected Mod 1,restoring Funds That Was Deobligated & Providing Final Increment of Funding to Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee, Pilgrim & Seabrook Resident Sites ML20246P3281988-05-31031 May 1988 Technical Evaluation Rept for Evaluation of ODCM Updated Through Rev 4,Vermont Yankee Nuclear Power Station ML20150D9001988-03-17017 March 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20150D9091988-03-17017 March 1988 Mod 1,deobligating Funds from Total Obligated Amount of Contract & to Correct FIN Number,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites ML20148C6071988-01-31031 January 1988 Review of the Natural Circulation Effect in the Vermont Yankee SPENT-FUEL Pool.Docket No. 50-271.(Vermont Yankee Nuclear Power Corp) ML20149F1311988-01-11011 January 1988 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee & Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20149F1691988-01-11011 January 1988 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20236P2051987-08-10010 August 1987 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Bell Telephone Co ML20236P2181987-08-10010 August 1987 Mod 1,increasing Total Amount of Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee, Pilgrim & Seabrook Resident Sites ML20235M3941987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Vermont Yankee, Informal Rept ML20235N4471987-06-30030 June 1987 Final Technical Evaluation Rept:Review & Evaluation of RELAP5YA Computer Code & Vermont Yankee LOCA Licensing Analysis Model for Use in Small & Large Break BWR Locas, Informal Rept ML20206S7131987-04-0808 April 1987 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Bell Telephone Co ML20206S7871987-04-0808 April 1987 Mod 1,changing Billing Address as Result of NRC Reorganization,To Local Telephone Svc for Yankee Rowe, Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites ML20211N4261987-02-23023 February 1987 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20211N3981987-02-23023 February 1987 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20214H0941986-07-14014 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Vermont Yankee Nuclear Station, Supplemental Technical Evaluation Rept ML20153H0851986-02-20020 February 1986 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Company ML20153H0471986-02-20020 February 1986 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20138G7891985-10-15015 October 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic ...), Item 1.2 `Post-Trip Review:Data & Info Capabilities' for Vermont Yankee Nuclear Power Station ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20128F4131985-05-0303 May 1985 In-Progress Audit of Dcrdr for Vermont Yankee Nuclear Power Plant ML20106J6471984-08-0909 August 1984 Evaluation of Detailed Control Room Design Review Program Plan Vermont Yankee Nuclear Power Plant ML20092A7521984-06-15015 June 1984 Control of Heavy Loads (C-10),Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20090H6841984-03-16016 March 1984 Monitoring of Electric Power to Reactor Protection Sys for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20093C3821983-09-27027 September 1983 Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20093A5831983-07-31031 July 1983 Technical Evaluation of Integrity of Vermont Yankee Nuclear Power Station Reactor Coolant Boundary Piping Sys ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070T7321982-11-30030 November 1982 Control of Heavy Loads (C-10) VT Yankee Nuclear Power Station, Draft Technical Evaluation Rept.Request for Addl Info Encl ML20076B6231982-09-27027 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Vt Yankee Atomic Power Station, Technical Evaluation Rept ML20071N8301982-09-0303 September 1982 Adequacy of Station Electric Distribution Sys Voltages, Technical Evaluation Rept ML20071J5661982-09-0202 September 1982 VT Yankee Nuclear Power Station Inservice Insp Program, Technical Evaluation Rept ML20197F8191982-08-25025 August 1982 Proposed Design Mods & Tech Specs Changes on Grid Voltage Degradation for Vermont Yankee Nuclear Power Station, Technical Evaluation Rept ML20064L4921982-06-30030 June 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Technical Evaluation Rept ML20042A9621982-02-11011 February 1982 Operating Reactor Power Operated Relief Valves & ECCS Repts, Request for Addl Info ML19331D9941980-07-21021 July 1980 Primary Coolant Sys Pressure Isolation Valves,Vt Yankee Unit 1, Technical Evaluation Rept ML19305D4041980-02-29029 February 1980 Safety Evaluation Rept,Inservice Testing Program. 1996-07-31
[Table view] |
Text
sm n; - - - - - - - - - - - - - -
u t 1 m N -' ' qug ' j c .
^
l A , ':
EGG-NTA-7665
+ ,
June 1987 1
INFORMAL REPORT
- +.
l
@ Idaho; National.' 4 CONFORMANCE TO GENERIC LETTER 83-28. ITEM 2.2.2--
VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-Enp neering - RELATED COMPONENTS: VERMONT YANKEE Laboratory ,
Managed,
' by the U.S. Alan C. Udy Depanment
.ofEnergy l~
jfEGaGw.u.
Prepared for the
- o""* ""*': U.S. NUCLEAR REGULATORY COMMISSION DOE Contract
, No. DE-AC07-76/D01570 '
B7071701og 0-jo ^
DR ADC,cy opoo$g,j opy; PDR i4 L
l l
d o l
l l
l A
DISCLAIMER This book was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their amployaes, makes any warranty, express or implied, or assumes any legal hability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not ininnge pnvately owned nghts. References herein to any specific commercial product, process, or service by trace name, trademark, manufacturer, or otherwise, does not necess6nly constitute or imply its endorsement, recommendation, or favoring by the United States Government or sny agency inerect. The views and opinions of authors exoressed herein do not necessanly state or reflect those of the United States Government or any agency thereof.
1 e
l l
l
3 l
i j
EGG-NTA-7665 I
, TECHNICAL EVALUATION REPORT !
l i
CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2--
VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:
VERMONT YANKEE l
Docket No. 50-271 l
i Alan C. Udy l
l l
Published June 1987 ,
Idaho National Engineering Laboratory EG&G Idaho, Inc.
Idaho Falls, Idaho 83415 I
Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Uncer DOE Contract No. DE-AC07-76ID01570 FIN No. D6001 l
l u__________________.___________________.___._..__________.__.______. ____.___ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _
__ .j
i 1
- l ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the Vermont Yankee Nuclear Power Corporation regarding confornance to Generic Letter 83-28, Item 2.2.2, for Vermont Yankee.
Docket No. 50-271 TAC No. 53728 ii
FOREWORD This report is supplied 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 being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Divisien of Engineering and System Technology, by EG&G Idaho, Inc., NRR and I&E Support Branch.
The U.S. Nuclear Regulatory Commission funded this work under the authorization B&R No. 20-19-10-11-3, FIN No. D6001.
~
Docket No. 50-271 TAC No. 53728 iii
CONTENTS ABSTRACT .. ..... ... ....... .... .. ............. ................. ii FOREWORD ............... .. .. .............. . ...................... iii
- 1. INTRODUCTION ........... ....... ................................. 1 o
- 2. REVIEW CONTENT AND FORMAT . .... ....... . .. .... ............. 2
- 3. ITEM 2.2.2 - PROGRAM DESCRIPTION ................................. 3 3.1 Guideline ...... ..... . ..... ....................... 3 3.2 Evaluation .. ............ . ....... ............. ....... 3 3.3 Conclusion ... .......... . ...... .............. ..... .... 4
- 4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE ESTABLISHED .. ....... ........................................... 5 4.1 Guideline .... .............. ................... ....... .. 5 4.2 Evaluation ..... .... ....... .............................. 5 4.3 Conclusion ....... ......................................... 6
- 5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDORS THAT PROVIDE SERVICE ON SAFETY-RELATED EQUIPMENT .............................. 7 5.1 Guideline ..................................... ............ 7 5.2 Evaluation ............................... ................. 7 5.3 Conclusion .. ......... ... ........... ................... 7
- 6. CONCLUSION ...... . . .... .. ........... ... ................. 8 (
- 7. REFERENCES .................... ................................. 9 iv
~_
CONFORMANCE TO GENERIC LETTER 83-28', ITEM 2.2.2-- l 1
V.NDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS: 1 VERMONT YANKEE l 1
4
- 1. INTRODUCTION i
e On February 25, 1983, both of the scram circuit breakers at Unit 1 of I the Salem Nuclear Power Plant failed to open upon an automatic reactor trip f signal from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the initiation of the
' automatic trip signal. The failure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam d generator low-low level during plant startup. In this case, the reactor was tripped manually by the operator almost coincidentally with the j l
automatic trip.
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the NRC staff to investigate and report on the generic implications of these occurrences at Unit 1 of the l Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Events at the Salem Nuclear !
Power Plant." As a result of this investigation, the Commission (NRC) 3 requested (by Generic Letter 83-28 dated July 8,1983 ) all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to the generic issues raised by the analyses of these two ATWS events.
This report is an evaluation of the responses submitted by the Vermont Yankee Nuclear Power Corporation, the licensee for Vermont Yankee, for Item 2.2.2 of Generic Letter 83-28. The documents reviewed as a part of this evaluation are listed in the references at the end of this report.
1 i
j
- 2. REVIEW CONTENT AND FORMAT Item 2.2.2 of Generic Letter 83-28 requests the licensee or applicant to submit, for the staff review, a description of their programs for interfacing with the vendors of all safety-related components including supporting information, in considerable detail, as indicated in the ,
guideline section for each case within this report.
These guidelines treat cases where direct vendor contact programs are pursued, treat cases where such contact cannot practically be established, l
and establish responsibilities of licensees / applicants and vendors that provide service on safety-related components or equipment.
l As previously indicated, the cases of Item 2.2.2 are evaluated in a separate section in which the guideline is presented; an evaluation of the licensee's/ applicant's response is made; and conclusions about the programs of the licensee or applicant for their vendor interface program for safety-related components and equipment are drawn.
2
- 3. ITEM 2.2.2 - PROGRAM DESCRIPTION 3.1 Guideline i
The licensee or applicant response should describe their program for establishing and maintaining interfaces with vendors of safety-related
. components which ensures that vendors are contacted on a periodic basis and i
that receipt of vendor equipment technical information (ETI) is acknowledged or otherwise verified. j 1
This program description should establish that such interfaces are j established with their NSSS vendor, as well as with the vendors of key safety-related components such as diesel generators, electrical switchgear, auxiliary feedpumps, emergency core cooling system (ECCS) pumps, batteries, battery chargers, and valve operators, to facilitate the exchange of current technical information. The description should verify that controlled procedures exist for handling this vendor technical information which ensure that it is kept current and complete and that it is incorporated into plant operating, maintenance and test procedures as is appropriate.
3.2 Evaluation The licensee for Vermon: Yankee responded to these requirements with submittals dated November 7, 1983,2 March 23, 1984,3 June 26, 19844 and July 3, 1985.5 These submittals include information that describes their past and current vendor interface programs. In the review of the licensee's ,
i response to this item, it was assumed that the information and documentation i supporting this program is available for audit upon request. We have reviewed the information submitted and note the following.
The licensee's respense states that they actively participate in the l Nuclear Utility Task Action Committee (NUTAC) program. The Vendor Equipment Technical Information program (VETIP) was developed by NUTAC. VETIP includes q interaction with the NSSS vendor and with other electric utilities. Typical I
3 l
1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _ .__ _ _ _ _ _ . __ ___________b
NSSS vendor (General Electric) contact with the licensee includes Service Advice and Service Information Letters, 10 CFR 21 reports, urgent communication and Turbine Information Letters. The licensee states that their program of vendor / utility interface goes beyond that recommended in paragraph 4.1.1 of the NUTAC report. They state that their interface is not limited to General Electric, but includes "all vendors." The licensee also states that new or revised procedures, utilizing an assessment coordinator to implement the NUTAC/VETIp program, are being used. .
The licensee reports that controls and procedures which require the review of safety-related equipment technical information to verify that it is referenced by and incorporated into plant procedures and instructions have been established.
3.3 Conclusion i
i We conclude that the licensee's response regarding program description is complete and, therefore, acceptable. d l
)
1 Y
F 4
ll
- 4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE ESTABLISHED 4.1 Guideline ;
i i
The licensee / applicant response should describe their program for l
compensating for the lack of a formal vendor interface where such an interface cannot be practicably established. This program may reference L
the NUTAC/VETIP program, as described in INPO 84-010, issued in l March 1984. If the NUTAC/VETIP program is referenced, the response should I describe how procedures were revised to properly control and implement this l
program and to incorporate the program enhancements described in Section 3.2 of the NUTAC/VETIP report. The use of the NUTAC/VETIP program, instead of either a formal interface with each vendor of safety-related equipment or a program to periodically contact each vendor of j i
safety-related eqdipment, will not relieve the licensee / applicant of his j i
responsibility to obtain appropriate vendor instructions and information where necessary to provide adequate confidence that a structure, system or component will perform satisfactorily in service and to ensure adequate quality assurance in accordance with Appendix B to 10 CFR Part 50 l l
4.2 Evaluation !
I l
The licensee provided a brief description of the vendor interface program. Their description references the NUTAC/VETIP program. The licensee states that plant instructions and procedures are being used to assure that the VETIP program is properly controlled and implemented.
l VETIP is comprised of two basic elements related to vendor equipment problems; the Nuclear Plant Reliability Data System (NPROS) and the Significant Event Evaluation and Information Network (SEE-IN) programs.
VETIP is designed to ensure that vendor equipment problems are recognized, evaluated and corrective action taken.
5
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ ________ ~
Through participation in the NPRDS program, the licensee submits engineering information, failure reports and operating histories for review under the SEE-IN program. Through the SEE-IN program, the Institute of Nuclear Power Operations (INPO) reviews nuclear plant events that have been reported through the NPRDS programs, Nuclear Network and NRC reports.
Based on the significance of the event, as determined by the screening review, INPO issues a report to all utilities outlining the cause of the event, related problems and recommends practical corrective actions. These . .
reports are issued in Significant Event Reports, in Significant Operating ]
Experience Reports and as Operations and Maintenance Reminders. Upon receipt of these documents, the licensee's assessment coordinator tracks ;
the licensee's evaluation of the information which determines applicability to the facility. This evaluation is then documented and corrective actions taken as determined necessary. Periodic internal audits assure that this l
review process operates correctly.
l The licensee's response states that procedures to review and evaluate incoming equipment technical information and to incorporate it into existing procedures are being followed.
4.3 Conclusion We find that the licensee's response to this concern is adequate and acceptable. This finding is based on the understanding that the licensee's commitment to implement the VETIP program includes the implementation of the enhancements described in Section 3.2 of the NUTAC/VETIP program to the extent that the licensee can control or influence the implementation of these recommendations.
. 1 i
l l
i i
6 I
(
{
1 I
- 5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDOR THAT PROVIDE SERVICE ON SAFETY-RELATED EQUIPMENT 5.1 Guideline 3 The licensee / applicant response should verify that the
, responsibilities of the licensee or applicant and vendors'that provide )
service on safety-related equipment are defined such that control of applicable instructions for maintenance work on safety-related equipment are provided.
5.2 Evaluation ,
The licensee's response commits to implement the NUTAC/VETIP program.
They further state that their present and revised programs and procedures adequately implement this program. The VETIP guidelines include
]
implementation procedures for the internal handling of vendor services.
5.3 Conclusion 1
We find the licensee's commitment to implement the VETIP recommendations acceptable, with the understanding that the licensee's commitment includes the objective for " Internal Handling of Vendor ]
Services" described on page 23 of the March 1984 NUTAC report. I I
1 l ;
1 l
e l
l 7 ,
- 6. CONCLUSION Based en our review of the licensee's response to the specific requirements of item 2.2.2 for Vermont Yankee, w,e find that the licensee's interface program with its NSSS supplier and with vendors of other ,
safety-related equipment, along with the licensee's commitment to implement the NUTAC/VETIP program, is acceptable. This is based on the understanding .
that the= licensee's commitment to implement the NUTAC/VETIP program includes the objective for " Internal Handling of Vendor Services" described on page 23 of the March 1984 report and includes the enhancements described in Section 3.2 of the report to the extent that the licensee can control or influence such enhancements.
l l
e 8
- 7. REFERENCES
- 1. Letter, NRC (D. G. Eisenhut), to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
- 2. Letter, Vermont Yankee Nuclear Power Corporation (W. P. Murphy) to NRC (D. B. Vassallo), " Generic Letter 83-28, Generic Implications of the Salem ATWS Events," November 7, 1983, 2.C.2.1, FVY 83-117.
- 3. Letter, Vermont Yankee Nuclear Power Corporation (W. P. Murphy) to NRC (D. B. Vassallo), " Generic Letter 83-28, Generic Implications of Salem ATWS Events," March 23, 1984, FVY 84-25.
~
- 4. Letter, Vermont Yankee Nuclear Power Corporation (W. P. Murphy) to NRC-(D. .B. Vassallo), " Response to Generic Letter 83-28, Section 2.2.2,"
l June 26, 1984, FVY 84-73. f l
- 5. Letter, Vermont Yankee Nuclear Power Corporation (R. W. Capstick) to NRC (D. B. Vassallo), " Response to Request for Additional Information Following Preliminary Staff Review and Licensee Response to Generic Letter 83-28," July 3, 1985, FVY 85-63.
- 6. Vendor Eouipment Technical Information Procram, Nuclear Utility Task Action Committee on Generic Letter 83-28, Section 2.2.2, March 1984, INP0 84-010.
)
l l
l
$ l I
9 1
L---_______________ _ _ _ _ _ _ _ _ _
Nec,o M m v s. =uct Aa a.outAvoav coMMI loN , .oa s -uM. a <=- ., r,oc. ,- v., .. . , ~, i 12 Sal EC" "7- T BIBLIOGRAPHIC DATA SHEET EGG-NTA-7665
$tt IN$1RUCTlONS oN 7 t aEVI8tSE 2 f tTLE Amo sue tlTLE aggaygggANg CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2- .
VEND 0R INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMP 0NENTS: VERMONT YANKEE
- oa aoa' co",o MoNr- .Aa l
- . Aur oa'5' June 1987 Alan C. Udy
MoNrN veAa
' g June 1987 F PERFoAMING ORGANIZAlsoN NAME ANo MatLING AoDatSS,severt. Coos 8 PROJECT /T ASK' WORE UNIT NUMSta EG&G Idaho, Inc.
P. 0. Box 1625 Idaho Falls, ID 83415 D6001 l
l ,o .,oNso ,~o o.o AN,4 ArioN NAME A~o MA.6,No Aooaiss u ,.e. c , n. Tv*e o* anaoa1 Division of Engineering and System Technology Office of Nuclear Reactor Regulation """'*'""'"~~~~~'
U.S. Nuclear Regulatory Commission Washington, DC 20555 12 StJPPLEMtNT ARY NOTis tJ A05T A ACT (200 weren er 'ess, This EG&G Idaho, Inc., report provides a review of the submittals from the Vermont Yankee Nuclear Power Corporation regarding conformance to Generic Letter 83-28 Item 2.2.2, for Vermont Yankee.
l 1
)
I e to DOCUMt NT AN AL
- Sil e EE *WonoE DE SCR'PTOMS 15 A vasL A.iLsT V
% $7ATEMENT Unlimited Di stribution .
56 SECuntTV CLAS$1FICAf ton f rMs 0 009
. .oeNr . ..s,onN ~oso 'eaMs
.. Unclassified
< rn, .,s, Unclassified 17 NUM$tR Q6 paQgg
, 18 FReLt 1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ .