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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
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EVALUATION OF THE , -
i .
OETAILED CONTROL ROOM DESIGN REVIEW
- . PROGRAM PLAN FOR VERMONT YANKEE NUCLEAR POWER CORPORATION'S VERMONT YANKEE NUCLEAR POWER PLANT August'9~, 1984-Prepared by Science Applications, Inc.
Under Contract to The United States Nuclear Regulatory Commission Contract NRC-03-82-096 f
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8411010296 841011 PDR ADOCK 05000271 F pg
i l
EVALUATION OF THE DETAILED CONTROL. ROOM DESIGN REVIEW PROGRAM PLAN FOR VERMONT YANKEE NUCLEAR POWER CORPORATION'S VERMONT-YANKEE NUCLEAR POWER PLANT Science Applications, Inc., (SAI) 'has evaluated the Program' Plan submitted by Vermont Yankee Nuclear Power. Corporation (VYNPC) for conduct of -a "
Detailed. Control . Room Design Review (DCROR) at the Vermont Yankee Nuclear _
Power Plant (VYNPP). The disciplines of human factors engineering and
~
mechanical engineering were represented on the evaluation team. All team members were familiar with nuclear power plant control rooms and experienced in evaluating DCRORs. The purpose of the evaluation was:
- 1. To determine whether the piann'ed program would result in a suc-
- cessful DCROR
- 2. To determine whether an in-progress audit was necessary
- 3. To provide an audit agenda where appropriate 4 To provide constructive feedback to the VYNPC l
Evaluation was against the requirements of Supplement 1 to NUREG-0737.
Additional guidance was provided by Generic Letter 83-18, NUREG-0700(draft NUREG-0801. This report provides the results of the evaluation. Comments of the NRC staff member responsible for evaluation of the VYNPP DCROR have been integrated into the report in order to represent the consolidated
! observations, conclusions, and recommendation; of the NRC staf f and its consultants (SAI).
DISCUSSIG, '
-Establishment of a qualified multidisciolinary review teain.
The Vermont Yankee Program Plan describes a two level hierarchy of personnel
' for conducting the OCROR. That hierarchy includes:
- 1. A management review team
- 2. A design review team The management review team is comprised of the engineering-services manager, simulator manager, and operations superintendent. . This team has the overall responsibility for the programs including implementation, resolution of findings and authorization for recommendations. The design review team
' includes a human factors consultant to VYNPC, a plant operator, an instru-ment and controls engineer, and the program manager. The design review team will evaluate all findings from previous control room efforts, conduct supplemental and additional reviews as needed,. conduct the task analysis, evaluate all findings, propose suitable modifications, and prepare the sumary report.
With the exception of a nuclear engineer, the disciplines represented on the design review team are those suggested in draft NUREG-0801. The Program Plan indicated that the design review team may be supplemented as necessary by personnel from disciplines including nuclear, mechanical, electrical, and civil engineering. Guidance in draft NUREG-0801 suggests that participation of supplemental personnel to provide the design review group with nuclear engineering expertise would be particularly beneficial during the operating experience review and .the function and task analyses. The remaining supplemental disciplines are among those suggested by draf t NUREG-0801.
Participation of personnel from those disciplines should contribute to the
! success of the OCRDR.
l Resumes for the design review team were provided. Personnel representing the disciplines of human factors, instrument and control engineering, and j
plant operations had education and experience consistent with guidance in l draft NUREG-0801. Resumes for the management review team and supplemental personnel were not provided.
l
. l VNCL did not s'pecify personnel assignments by task. Draft NUREG-0801 provides guidance for such assignments. Adherence to that guidance would contribute to the success of the DCRDR.
One cancern is the availability of.
human factors specialists. The success of a DCRDR depends heavily on the contribution of human factors specialists to accomplish the technical tasks.
Only one member of the design review team has training and experience in the human factors area. Given the number and magnitude of the technical tasks needing human factors expertise, increasing the number of human factors specialists .would increase the likelihood of a successful DCRDR at Vermont
. Yankee.
The Program Plan does not indicate an orientation program for the VYNPC DCRDR. Such a program could provide personnel at all levels with a basic understanding of the DCRDR process, the contribution of various professions to its accomplishment, and the roles of various levels of organization.
Function and task analyses to identify control room operator tasks and in-formation and control requirements during emergency operations. VYNPC has stated that information in tne FSAR on plant systems and subsystems in the control room will serve as a reference base for' the t'ask analysis and assessment phases. In addition, Emergency Operating Procedures (EOPM will be reviewed to select operating scenarios for walk-throughs during task '
analysis. On the assumption that E0Ps have been evaluated and approved for use, the VYNPC team will:
Identify discrete steps in the E0P in order of performance 1.
- 2. Describe the operators' tasks per step Determine operator decisions and/or actions linked to task i 3.
! performance 4 Identify information and control requirements
- 5. Identify instruments and controls to satisfy the information and control requirements w , ,
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I The process described by VYNPC is basically sound, but raises several cancerns. One concern is that, although the Procedures Generation Package (PGP) for VYNPP has been received by the Procedures and Systems Review That review may
-Branch,.it is not scheduled for review until late 1984 rasult in changes to the PGP and ultimately to the E0Ps. The task analysis-should be redone for. revised E0Ps in order to satisfy the OCRDR requirement in Supplement 1 to NUREG-0737. A second concern is that Supplement 1 to MUREG-0737 requires that E0P development be based on a process which identifies operator tasks, and information and control needs (i.e., a task analysis). VYNPC appears to propose the reverse process (i.e., a task analysis which follows E0P development). This situation may allow satisfaction of the Supplement 1 to NUREG-0737 DCRDR requirement if the E0Ps developed for VYNPP are at a high level (e.g., " operate specified system")
VYNPC typical of those generated from BWROG Emergency Procedure Guidelines.
should ensure that the identification of operator information and control requirements based on tasks needed to satisfy the functions identified in the generic guidelines is independent of 'the existing, control room in order to satisfy the requirements. The res' ult would be instrument and control needs based on information and control requirements, not on the existing controls and displays at VYNPP. Instrument and control needs thus identi fied would be appropriate input to the verification of task performance capabilities (i.e., comparison of function and task analysis
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results with a control room inventory). A final can'cern is the selection of operating scenarios for walk-through during the task analysis. The
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selection process should be such that all tasks involved in the E0Ps are analyzed. Analysis of all tasks will satisfy the DCRDR requirement in Supplement 1 to NUREG-0737.
A comoarison of display and control requirements eith a control room inven-tory. VYNPC stated that it would conduct a verification of task performance capabilities. That verification would confirm that instrumentation and controls identified in the task analysis as being required by the operator
- are
- 1. Present in the control room
- 2. Effectively designed to support correct procedure performance
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1 The procs.ss will generate HEDs when in:+rumentation or controls are l unavailable -or unsuitable. l The described process is consistent with NRC guidelines for the comparison However, of display and control requirements' with a control room inventory.
the success of the task depends heavily on the quality and content of the '
function and task analyses and the. control room inventory. . Previous comments were directed at ensuring suitable function and task analyses input to the verification task. VYMPC states that the function of a control room inventory will be performed as part of the task analysis effort and related verification and validation efforts. The specific form the control room inventory would take was not stated. However, there is a -major concern- that development of a control room inventory as part of the task analysis efforts will be a self-ful' filling exercise rather than a method for identifying unavailable or unsuitable instrumentation and controls. An adequate control room inventory would be separate from' the task analysis effort and would
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include the characteristics of existing- instruments and controls which will
! allow meaningful comparison with the characteristics of needed information and control capabilities determined from the function and task analysis.
A control room survey to identi fy deviations from accepted human factors princioles. A preliminary survey of the Vermont Yankee control room was performed by Wyle Laboratories in August 1980. In January 1982, the.BWROG conducted a control room survey at Vermont Yankee. In addition, the Program Plan indicates that VYNPC will:
- 1. Use the BWROG Control Room Survey Checklist Supplement to resurvey l areas of the control room surveyed previously e
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- 2. Use the original BWROG Control Room Survey Program checklists to survey modifications to the control board and control room since the BWROG survey. The effort will include the alternate shutdown panels l
VYNPC did not state that they intended to comply with the requirements of Generic Letter 83-18, but the above actions would satisfy those requirements with one exception. The BWROG Control Room Survey Checklist Supplement should also be used in surveying modifications to the control boards and
-ll control room. With that addition, the survey.should satisfy the require-ments of Generic t.etter 83-18 and Supplement 1 to NUREG-0737.
Assessment of human engineering discrecancies to determine __which HEDs are l
significant and should be corrected. Vermont Yankee has stated that the DCRDR review team will assess and categorize all HEDs identified during the DCRDR process. Four categories are described. Those categories are based on judgments about the likelihood an HED will result in an operator error and-on the potential consequences of such an error. Consideration of cumulative and interactive effects with other HEDs is included in the assessment. The Program Plan implied that all HEDs, regardless of category, could enter the process for selection of design improvements. If that is 2he intent, the assessment process should satisfy the Supplement 1 to NUREG-0737 requirement. If that is not the intent, satisfaction of the Supplement 1 to NUREG-0737 requirement would appear to require that all but Category IV HEDs (i.e., those judged not to increase the potential for causing or contributing to a significant operating crew error, to have adverse safety consequences, or to have cumulative or interactive effects) should enter the selection of design improvements process.
Selection of design imorovements. Recommendations for HED resolution correction will .be made by the review team for each identified HED. VYNPC states that highest priority (reviewer's note: prioiity system not defined)
HEDs will be evaluated first and that Category IV HEDs will be documented but it is likely that no corrective action will be taken. Proposed correc-tive techniques will include enhancement, design changes, and training.
Enhancement techniques will be mocked-up on drawings to allow the review l
2eam to evaluate their effectiveness. Design changes will be evaluated by having operators walk through portions of E0Ps involving affected compo-nents.
As described, the process for selection of design improvements is consistent l
with NRC guidance. There is, however, some concern that the HED-by-HED approach will result in piecemeal corrections. There are several means for reducing the above concern. One is development of design conventions (e.g.,
a labeling convention or control room-wide color convention) which will be applied throughout the control room, remote shutdown panel, and other opera-tor stations (if desired). A second is to take the fullest advantage of
Coc up techniques to assure that the - total correction package provides a consisten t, cbherent, and integrated interface b'e' tween operators and the control room. It is recommended that VYNPC add means for resolving the concern abo,ut piecemeal correction of HEDs to the process for selection of ;
design improvements.
Verification that selected design improvements will provide the necessary
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correction and verification that improvements will not introduce new HEDs.
VYNP.C has indicated that the above verification requirements will be
- satisfied during the selection of design improvements. After arriving at a recommended solution for each HED, the following two steps will be per-formed
- 1. Verification that the recommended solution adequately addresses i- the HED, is feasible, cost effective, and adheres to accepted human factors principles
- 2. Validation that this solutio'n does not introduce another HED J
The mechanism for accomplishing the two steps was not described.
The intent to satisfy the requirements to verify that HEDs are corrected and Use'of mock-up techniques, no new HEDs are introduced was indicated.
particularly for the verification that no new HEDs are introduced, is recommended.
from other orograms Coordination of control room improvements with changes such as the SPDS, operator training, Reg. Guide 1.97 instrumentation and uograded emarqency operating crocedures. VYNPC addressed coordination of control room improvements with changes from other programs as follows:
- 1. No device specifically identified as an SPDS is planned for VYNPP.
VYNPC indicated that the DCRDR may result in additional methods of displaying safety parameters
- 2. Coordination with training was not specifically addressed by VYNPC except as potential resolutions for some HEDs i
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- 3. 'With respect to . Reg'. Guide 1.97, the verification of task performance capabilities will be used to give insight into the monitoring instrumentation .that.is available, and to whether indi-cation is required but missing
- 4. Upgraded E0Ps will- serve as the starting point for the task-analysis used to identify operator tasks and information and control needs -
' Saveral concerns are raised by the proposed coordination activities. One concern is t' hat submission of-the SAR for the VYMPP SPOS is not scheduled intil February 1,1985. NRC review of the SAR may indicate that existing instrumentation and controls do not satisfy the SPDS requirements of Supplement 1 to NUREG--0737. In that case, satisfaction of the DCRCR coordination requirement would mean revi.ew of any added SPDS equipment for human factors suitability and for consistency with the rema.inder of the control room. A second concern is th' a t.while training is viewed as a means for resolving HEDs, training to familiarize operators with changes to the control room was not mentioned. Such' traini'ng appears necessary for
. satisfaction of the Supplement I to NUREG-0737 coordination requirement.
Simulator upgrade which precedes control room upgrade might enhance this i
process and aid in evaluation of corrections. A third concern is that all
! Reg. Guide 1.97 instrumentation may not fall within the scope of the E0Ps.
! Satisfaction of the coordination requirement appears to require that all
! Rng. Guide 1.97 instrumentation added to the control room be compared with accepted human factors principles and reviewed for consistency with the rest of the control room. Final concerns, related to coordination with the E0Ps, are discussed in the paragraph on function and task analysis.
Other. The VYNPC program plan indicated that an operating experience review has been conducted as a part of the 1982 BWROG control room survey. In addition they intend to update the operating experience review to cover the approximately two years of elapsed time since that review. Consistent with guidelines in NUREG-0700 both a review of operating history and operator interviews will be included. An operating experience review is not required by Supplement 1 to NUREG-0737, but it is expected to contribute to the success of the DCROR. Development of a plan for keeping the operating
l experience review current after completion of the DCRDR 1. recommended.
Such a plan may leave value throughout the life of the plant.
The VYMPC Program Plan also indicated that a validation of control room Walk-throughs will be performed to identify functions would be conducted.
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dynamic performance problems.
HEDs will be documented for input to the assessment process. As described, the validation process should contribute 20 the success of the DCRDR. ,
The VYNPC control room survey will also include the alternate or remote shutdown panels. The review of the remote shutdown panel in the OCRDR should enhance operability of VYNPP.
CONCLUSION The Vermont Yankee program plan addressed all of the DCROR requirements stated in Supplement 1 to NUREG-d7-37.. Information in the program plan
. indicated understanding and intent to' satisfy most of the requirements. The review did, however, identify some concerns. Those concerns were:
- 1. Amount of human factors expertise available for accomplishment of technical tasks is limited .
- 2. Lack of specific personnel assignments
- 3. Apparent lack of an orientation program for those involved in the OCRDR 4 The possibility that E0Ps used in the task analysis will suose-quently require revision based on NRC review of VYNPP's PGP
- 5. The possibility that identification of operator information and control requirements will not be independent of the existing control room
- 6. The possibility that all tasks in the E0Ps will not be subjecced to task analysis
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- 7. Inclusion of appropriate equipment characteristics in the control room inventory
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- 8. The. indication that modifications to the control room and control boards will be compared only with the '8WROG Control Room Survey Program checklist and not +.he supplement to that checklist
- 9. The possibility that HED-by-HED solution of design improvements will result in piecemeal correction
- 10. Gaps in the efforts to coordinate control room improvements with changes from other programs Resolution of the above concerns would increase the benefits of the DCRDR.
Several recommendations also resulted from the program plan review. The 3-recommendations are not intended as . additional requirements. They are intended to encourage the fullest possible benefit from the DCRDR. They do not appear to require major changes to the current organization and process
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of the DC'RDR. These recommendations are:
- 1. Development of a plan to keep the operating experience review current after completion of the OCRDR -
- 2. Use of a control room mock-up to assess the integrated effect of J
the fullest possible range of design i mprovements and enhancements
- 3. Simulator upgrade which precedes control room upgrade to aid coordination with training, and if practicable, evaluation of corrections
- 4. Development of control room design conventions i
Based on the review of the program plan, an in-progress audit of the 'lermont Yankee OCROR is recommended.
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