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Category:CONTRACTED REPORT - RTA
MONTHYEARML20080B0921994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant ML20073S6481994-06-10010 June 1994 Technical Evaluation:Core Thermal Limit Protection Function Setpoint Methodology for Seabrook Station YAEC-1854P for Yankee Atomic Electric Co ML20091H8751991-12-17017 December 1991 Final Technical Evaluation Rept,Seabrook Station Unit 1 Station Blackout Evaluation ML20006F0351989-11-30030 November 1989 Technical Evaluation Rept on First 10-yr Interval Inservice Insp Program Plan:Public Svc of New Hampshire,Seabrook Station,Unit 1. ML20244A4701989-05-31031 May 1989 Rev 1 to Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Seabrook Nuclear Station - Units 1 & 2 ML20235L9811987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Seabrook 1 & 2, Informal Rept ML20235L8391987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Seabrook Units 1 & 2, Final Informal Rept ML20206B2451987-03-31031 March 1987 a Review of the Seabrook Station Probabilistic Safety Assessment.Containment Failure Modes and Radiological Source Terms ML20212P9341987-03-0303 March 1987 Technical Evaluation of EPZ Sensitivity Study for Seabrook, Technical Rept ML20207B6761986-12-0505 December 1986 Draft Technical Evaluation of Emergency Planning Zone Sensitivity Study for Seabrook ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20212Q1691986-08-27027 August 1986 NRC Region I Insp 50-443/86-27 Review of Seabrook,Unit 1, Tech Specs, Technical Review Report of Onsite Activities Conducted on 860505-16 ML20214H0601986-05-31031 May 1986 Conformance to Reg Guide 1.97,Seabrook Station,Units 1 & 2, Technical Evaluation Rept for May 1986 ML20214G1281986-03-18018 March 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1986 ML20140E0471986-02-28028 February 1986 Review of Seabrook Station Probabilistic Safety Assessment: Containment Failure Modes & Radiological Source Terms ML20199E0071986-02-28028 February 1986 Sqrt Visit Rept ML20199D9991986-02-28028 February 1986 Audit of Pump & Valve Operability Assurance Program for Seabrook Generating Station Unit 1 ML20214G1231986-02-20020 February 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1986 ML20214G0791986-01-20020 January 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1985 ML20214G0681985-12-18018 December 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1985 ML20210K6451985-11-30030 November 1985 PRA Insights ML20214G0651985-11-21021 November 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Oct 1985 ML20214F7661985-10-18018 October 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Progress Rept for Sept 1985 ML20214F7551985-09-20020 September 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Aug 1985 ML20211D2261985-08-26026 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 15 for Jul 1985 ML20211D2081985-08-0909 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 14 for June 1985 ML20214G2041985-07-31031 July 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jul 1985.Related Info,Including Transmittal of Vouchers for Svcs Rendered,Encl ML20214G1921985-06-30030 June 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for June 1985 ML20211D1981985-06-27027 June 1985 Review of Seabrook PRA, Monthly Mgt Ltr 13 for May 1985 ML20206F1821985-06-0606 June 1985 Marked-up Analysis of Station Blackout Transient W/Reactor Coolant Pump Seal Leakage for Seabrook Nuclear Plant ML20214G1881985-05-31031 May 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for May 1985 ML20211D1691985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 11 for Mar 1985 ML20211D1781985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 12 for Apr 1985 ML20214G1811985-04-30030 April 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Apr 1985 ML20214G1791985-03-31031 March 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Mar 1985 ML20209E2741985-03-29029 March 1985 Review of Seabrook PRA, Monthly Mgt Ltr 10 for Feb 1985 ML20214G1711985-02-28028 February 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1985 ML20211D1291985-02-20020 February 1985 Review of Seabrook PRA, Monthly Mgt Ltr 9 for Jan 1985 ML20214G0621985-02-19019 February 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1985 ML20211D0921985-02-0404 February 1985 Review of Seabrook PRA, Monthly Mgt Ltr 8 for Dec 1984 ML20211E0401985-01-31031 January 1985 Preliminary Review & Evaluation of Seabrook Probabilistic Safety Study ML20211D0681985-01-25025 January 1985 Review of Seabrook PRA, Monthly Mgt Ltr 7 for Nov 1984 ML20214G0571985-01-18018 January 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1984 ML20214G0411984-12-17017 December 1984 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1984 ML20113E5691984-12-12012 December 1984 Draft Review of Seabrook Station Probabilistic Safety Assessment ML20211C9041984-11-19019 November 1984 Review of Seabrook PRA, Monthly Mgt Ltr 6 for Oct 1984 ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20209D5471984-11-14014 November 1984 PRA Review & Recommended Approach for Completion of Project, Status Rept as of 841101 ML20214G1481984-10-19019 October 1984 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Sept 1984 ML20209D4791984-10-15015 October 1984 Review of Seabrook PRA, Monthly Mgt Ltr 5 for Sept 1984 1994-09-30
[Table view] Category:QUICK LOOK
MONTHYEARML20080B0921994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant ML20073S6481994-06-10010 June 1994 Technical Evaluation:Core Thermal Limit Protection Function Setpoint Methodology for Seabrook Station YAEC-1854P for Yankee Atomic Electric Co ML20091H8751991-12-17017 December 1991 Final Technical Evaluation Rept,Seabrook Station Unit 1 Station Blackout Evaluation ML20006F0351989-11-30030 November 1989 Technical Evaluation Rept on First 10-yr Interval Inservice Insp Program Plan:Public Svc of New Hampshire,Seabrook Station,Unit 1. ML20244A4701989-05-31031 May 1989 Rev 1 to Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Seabrook Nuclear Station - Units 1 & 2 ML20235L9811987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Seabrook 1 & 2, Informal Rept ML20235L8391987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Seabrook Units 1 & 2, Final Informal Rept ML20206B2451987-03-31031 March 1987 a Review of the Seabrook Station Probabilistic Safety Assessment.Containment Failure Modes and Radiological Source Terms ML20212P9341987-03-0303 March 1987 Technical Evaluation of EPZ Sensitivity Study for Seabrook, Technical Rept ML20207B6761986-12-0505 December 1986 Draft Technical Evaluation of Emergency Planning Zone Sensitivity Study for Seabrook ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20212Q1691986-08-27027 August 1986 NRC Region I Insp 50-443/86-27 Review of Seabrook,Unit 1, Tech Specs, Technical Review Report of Onsite Activities Conducted on 860505-16 ML20214H0601986-05-31031 May 1986 Conformance to Reg Guide 1.97,Seabrook Station,Units 1 & 2, Technical Evaluation Rept for May 1986 ML20214G1281986-03-18018 March 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1986 ML20140E0471986-02-28028 February 1986 Review of Seabrook Station Probabilistic Safety Assessment: Containment Failure Modes & Radiological Source Terms ML20199E0071986-02-28028 February 1986 Sqrt Visit Rept ML20199D9991986-02-28028 February 1986 Audit of Pump & Valve Operability Assurance Program for Seabrook Generating Station Unit 1 ML20214G1231986-02-20020 February 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1986 ML20214G0791986-01-20020 January 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1985 ML20214G0681985-12-18018 December 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1985 ML20210K6451985-11-30030 November 1985 PRA Insights ML20214G0651985-11-21021 November 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Oct 1985 ML20214F7661985-10-18018 October 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Progress Rept for Sept 1985 ML20214F7551985-09-20020 September 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Aug 1985 ML20211D2261985-08-26026 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 15 for Jul 1985 ML20211D2081985-08-0909 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 14 for June 1985 ML20214G2041985-07-31031 July 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jul 1985.Related Info,Including Transmittal of Vouchers for Svcs Rendered,Encl ML20214G1921985-06-30030 June 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for June 1985 ML20211D1981985-06-27027 June 1985 Review of Seabrook PRA, Monthly Mgt Ltr 13 for May 1985 ML20206F1821985-06-0606 June 1985 Marked-up Analysis of Station Blackout Transient W/Reactor Coolant Pump Seal Leakage for Seabrook Nuclear Plant ML20214G1881985-05-31031 May 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for May 1985 ML20211D1691985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 11 for Mar 1985 ML20211D1781985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 12 for Apr 1985 ML20214G1811985-04-30030 April 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Apr 1985 ML20214G1791985-03-31031 March 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Mar 1985 ML20209E2741985-03-29029 March 1985 Review of Seabrook PRA, Monthly Mgt Ltr 10 for Feb 1985 ML20214G1711985-02-28028 February 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1985 ML20211D1291985-02-20020 February 1985 Review of Seabrook PRA, Monthly Mgt Ltr 9 for Jan 1985 ML20214G0621985-02-19019 February 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1985 ML20211D0921985-02-0404 February 1985 Review of Seabrook PRA, Monthly Mgt Ltr 8 for Dec 1984 ML20211E0401985-01-31031 January 1985 Preliminary Review & Evaluation of Seabrook Probabilistic Safety Study ML20211D0681985-01-25025 January 1985 Review of Seabrook PRA, Monthly Mgt Ltr 7 for Nov 1984 ML20214G0571985-01-18018 January 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1984 ML20214G0411984-12-17017 December 1984 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1984 ML20113E5691984-12-12012 December 1984 Draft Review of Seabrook Station Probabilistic Safety Assessment ML20211C9041984-11-19019 November 1984 Review of Seabrook PRA, Monthly Mgt Ltr 6 for Oct 1984 ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20209D5471984-11-14014 November 1984 PRA Review & Recommended Approach for Completion of Project, Status Rept as of 841101 ML20214G1481984-10-19019 October 1984 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Sept 1984 ML20209D4791984-10-15015 October 1984 Review of Seabrook PRA, Monthly Mgt Ltr 5 for Sept 1984 1994-09-30
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20080B0921994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant ML20073S6481994-06-10010 June 1994 Technical Evaluation:Core Thermal Limit Protection Function Setpoint Methodology for Seabrook Station YAEC-1854P for Yankee Atomic Electric Co ML20091H8751991-12-17017 December 1991 Final Technical Evaluation Rept,Seabrook Station Unit 1 Station Blackout Evaluation ML20006F0351989-11-30030 November 1989 Technical Evaluation Rept on First 10-yr Interval Inservice Insp Program Plan:Public Svc of New Hampshire,Seabrook Station,Unit 1. ML20244A4701989-05-31031 May 1989 Rev 1 to Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Seabrook Nuclear Station - Units 1 & 2 ML20235L9811987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Seabrook 1 & 2, Informal Rept ML20235L8391987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Seabrook Units 1 & 2, Final Informal Rept ML20206B2451987-03-31031 March 1987 a Review of the Seabrook Station Probabilistic Safety Assessment.Containment Failure Modes and Radiological Source Terms ML20212P9341987-03-0303 March 1987 Technical Evaluation of EPZ Sensitivity Study for Seabrook, Technical Rept ML20207B6761986-12-0505 December 1986 Draft Technical Evaluation of Emergency Planning Zone Sensitivity Study for Seabrook ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20212Q1691986-08-27027 August 1986 NRC Region I Insp 50-443/86-27 Review of Seabrook,Unit 1, Tech Specs, Technical Review Report of Onsite Activities Conducted on 860505-16 ML20214H0601986-05-31031 May 1986 Conformance to Reg Guide 1.97,Seabrook Station,Units 1 & 2, Technical Evaluation Rept for May 1986 ML20214G1281986-03-18018 March 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1986 ML20140E0471986-02-28028 February 1986 Review of Seabrook Station Probabilistic Safety Assessment: Containment Failure Modes & Radiological Source Terms ML20199E0071986-02-28028 February 1986 Sqrt Visit Rept ML20199D9991986-02-28028 February 1986 Audit of Pump & Valve Operability Assurance Program for Seabrook Generating Station Unit 1 ML20214G1231986-02-20020 February 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1986 ML20214G0791986-01-20020 January 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1985 ML20214G0681985-12-18018 December 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1985 ML20210K6451985-11-30030 November 1985 PRA Insights ML20214G0651985-11-21021 November 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Oct 1985 ML20214F7661985-10-18018 October 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Progress Rept for Sept 1985 ML20214F7551985-09-20020 September 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Aug 1985 ML20211D2261985-08-26026 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 15 for Jul 1985 ML20211D2081985-08-0909 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 14 for June 1985 ML20214G2041985-07-31031 July 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jul 1985.Related Info,Including Transmittal of Vouchers for Svcs Rendered,Encl ML20214G1921985-06-30030 June 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for June 1985 ML20211D1981985-06-27027 June 1985 Review of Seabrook PRA, Monthly Mgt Ltr 13 for May 1985 ML20206F1821985-06-0606 June 1985 Marked-up Analysis of Station Blackout Transient W/Reactor Coolant Pump Seal Leakage for Seabrook Nuclear Plant ML20214G1881985-05-31031 May 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for May 1985 ML20211D1691985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 11 for Mar 1985 ML20211D1781985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 12 for Apr 1985 ML20214G1811985-04-30030 April 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Apr 1985 ML20214G1791985-03-31031 March 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Mar 1985 ML20209E2741985-03-29029 March 1985 Review of Seabrook PRA, Monthly Mgt Ltr 10 for Feb 1985 ML20214G1711985-02-28028 February 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1985 ML20211D1291985-02-20020 February 1985 Review of Seabrook PRA, Monthly Mgt Ltr 9 for Jan 1985 ML20214G0621985-02-19019 February 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1985 ML20211D0921985-02-0404 February 1985 Review of Seabrook PRA, Monthly Mgt Ltr 8 for Dec 1984 ML20211E0401985-01-31031 January 1985 Preliminary Review & Evaluation of Seabrook Probabilistic Safety Study ML20211D0681985-01-25025 January 1985 Review of Seabrook PRA, Monthly Mgt Ltr 7 for Nov 1984 ML20214G0571985-01-18018 January 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1984 ML20214G0411984-12-17017 December 1984 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1984 ML20113E5691984-12-12012 December 1984 Draft Review of Seabrook Station Probabilistic Safety Assessment ML20211C9041984-11-19019 November 1984 Review of Seabrook PRA, Monthly Mgt Ltr 6 for Oct 1984 ML20214F8171984-11-16016 November 1984 Safety Evaluation of Core-Melt Accidents:CESSAR-FDA, Westinghouse Std Plant-FDA, Safety Evaluation of Core-Melt Accidents:Indian Point...& Zion-Operating Reactor & Review of PRA for Seabrook..., Monthly Repts for Oct 1984 ML20209D5471984-11-14014 November 1984 PRA Review & Recommended Approach for Completion of Project, Status Rept as of 841101 ML20214G1481984-10-19019 October 1984 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Sept 1984 ML20209D4791984-10-15015 October 1984 Review of Seabrook PRA, Monthly Mgt Ltr 5 for Sept 1984 1994-09-30
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20080B0921994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant ML20073S6481994-06-10010 June 1994 Technical Evaluation:Core Thermal Limit Protection Function Setpoint Methodology for Seabrook Station YAEC-1854P for Yankee Atomic Electric Co ML20091H8751991-12-17017 December 1991 Final Technical Evaluation Rept,Seabrook Station Unit 1 Station Blackout Evaluation ML20006F0351989-11-30030 November 1989 Technical Evaluation Rept on First 10-yr Interval Inservice Insp Program Plan:Public Svc of New Hampshire,Seabrook Station,Unit 1. ML20244A4701989-05-31031 May 1989 Rev 1 to Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Seabrook Nuclear Station - Units 1 & 2 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 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 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 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 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 ML20235L9811987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Seabrook 1 & 2, Informal Rept ML20235L8391987-06-30030 June 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Seabrook Units 1 & 2, Final 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 ML20206B2451987-03-31031 March 1987 a Review of the Seabrook Station Probabilistic Safety Assessment.Containment Failure Modes and Radiological Source Terms ML20212P9341987-03-0303 March 1987 Technical Evaluation of EPZ Sensitivity Study for Seabrook, Technical Rept 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 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 ML20207B6761986-12-0505 December 1986 Draft Technical Evaluation of Emergency Planning Zone Sensitivity Study for Seabrook ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20210G2141986-09-0303 September 1986 Mod 3,deobligating Funds,To Review of Tornado Missile PRA- Limerick Generating Station & Seabrook Nuclear Power Plant ML20210G1751986-09-0303 September 1986 Notification of Contract Execution,Mod 3,to Review of Tornado Missile PRA-Limerick Generating Station & Seabrook Nuclear Power Plant. Contractor:Nbs ML20212Q1691986-08-27027 August 1986 NRC Region I Insp 50-443/86-27 Review of Seabrook,Unit 1, Tech Specs, Technical Review Report of Onsite Activities Conducted on 860505-16 ML20209H6651986-08-11011 August 1986 Project & Budget Proposal for NRC Work: Review of Emergency Planning Sensitivity Study for Seabrook. Related Documentation Encl ML20214H0601986-05-31031 May 1986 Conformance to Reg Guide 1.97,Seabrook Station,Units 1 & 2, Technical Evaluation Rept for May 1986 ML20214G1281986-03-18018 March 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Feb 1986 ML20199D9991986-02-28028 February 1986 Audit of Pump & Valve Operability Assurance Program for Seabrook Generating Station Unit 1 ML20199E0071986-02-28028 February 1986 Sqrt Visit Rept ML20140E0471986-02-28028 February 1986 Review of Seabrook Station Probabilistic Safety Assessment: Containment Failure Modes & Radiological Source Terms 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 ML20214G1231986-02-20020 February 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jan 1986 ML20214G0791986-01-20020 January 1986 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Dec 1985 ML20214G0681985-12-18018 December 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Nov 1985 ML20210K6451985-11-30030 November 1985 PRA Insights ML20214G0651985-11-21021 November 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Oct 1985 ML20214F7661985-10-18018 October 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Progress Rept for Sept 1985 ML20214F7551985-09-20020 September 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Aug 1985 ML20211D2261985-08-26026 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 15 for Jul 1985 ML20211D2081985-08-0909 August 1985 Review of Seabrook PRA, Monthly Mgt Ltr 14 for June 1985 ML20214G2041985-07-31031 July 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for Jul 1985.Related Info,Including Transmittal of Vouchers for Svcs Rendered,Encl ML20214G1921985-06-30030 June 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for June 1985 ML20211D1981985-06-27027 June 1985 Review of Seabrook PRA, Monthly Mgt Ltr 13 for May 1985 ML20206F1821985-06-0606 June 1985 Marked-up Analysis of Station Blackout Transient W/Reactor Coolant Pump Seal Leakage for Seabrook Nuclear Plant ML20214G1881985-05-31031 May 1985 Review of PRA for Seabrook Nuclear Power Plant, Monthly Highlights for May 1985 ML20211D1781985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 12 for Apr 1985 ML20211D1691985-05-0101 May 1985 Review of Seabrook PRA, Monthly Mgt Ltr 11 for Mar 1985 1994-09-30
[Table view] |
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l EGG-DNSP-ll488 TECHNICAL EVALUATION REPORT Evaluation of Utility Response to Supplement I to NRC Bulletin 90-01: Seabrook Docket No. 50-443 I l
LeRoy C. Meyer Alan C. Udy Published September 1994 i
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l EG&G Idaho, Inc.
Idaho National Engineering Laboratory j Idaho Falls, Idaho 83415 I l
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l Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-761D01570 l FIN No. Ll695, Task No. 11a !
i TAC 'lo. M63441 I
9411250047 941117 ENCLOSURE 2 PDR ADOCK 05000443 l P pop l
SUMMARY
This report documents the EG&G Idaho, Inc., review of the North Atlantic Energy Service Corporation submittals responding to Supplement I to NRC Bulletin 90-01 for the Seabrook Station. This NRC Bulletin provides informat:an on the loss of fill-oil in certain pressure and differential presst.e transmitters manufactured by Rosemount, Ir. . inis report finds the licensee complies to the requested actions and the reporting requirements of the Supplement.
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FIN No. Ll695, Task No. lla l B&R No. 320-19-15-05-0 l Docket No. 50-443 l TAC No. M85441 ii ,
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PREFACE ;
This report is supplied as part of the " Technical Assistance in Support of the Instrumentation and Controis Systems Branch." It is being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reacter Regulation, Division of Reactor Controls and Human Factors, by EG&G Idaho, Inc., DOE /NRC Support Programs Unit.
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CONTENTS
SUMMARY
.................................................................. ii PREFACE .................................................................. iii
- 1. INTRODUCTION ........................................................ 1
- 2. NRC SPECIFIED REQUESTED ACTI0NS...................................... 4 l
l 3. EVALUATION .......................................................... 7 l 3.1 Evaluation of Licensee Response to Reporting Requirements ..... 7 l 3.2 Evaluation of Licensee Response to Requested Actions .......... 7
- 4. CONCLUSIONS ........................................................ 13
- 5. REFERENCES ........................... ............................ 14 i
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Evaluation of-Utility Response to Supolement I to NRC Bulletin 90-01: Seabrook
- 1. INTRODUCTION The NRC issued Bulletin 90-01 on March 9, 1990 (Reference 1). That Bulletin discussed certain Rosemount pressure and differential pressure transmitter models identified by the manufacturer as prone to fill-oil leakage. The Bulletin requested licensees to identify whether these transmitters were or may later be installed in safety-related systems.
Actions were detailed for licensee implementation for certain identified transmitters installad in a safety-related system. These same actions apply to those identified transmitters presently held in inventory for later installation in a safety-related system.
With the cradual leakage of fill-oil, the transmitter would not have the long term accuracy, time response, and reliability needed for its intended safety function. Further, this condition could go undetected over a long period. Redundant instrument channels are subject to the same degradation mechanism. This increases the potential for a common mode failure. Thus, ,
this potential failure mechanism raised concern for the reliability of reactor protection systems (RPS), engineered safety features (ESF) actuation systems, and anticipated transient-without scram (ATWS) mitigating systems. To achieve high functional reliability, there must be a low probability of component failure while operating, with any failures readily detectable.
Supplement 1 to NRC Bulletin 90-01 (Reference 2) was issued on December 22, 1992. The Supplement informed licensees of NRC staff activities regarding the subject transmitters, and noted continuing reports of transmitter failures. The NRC requested licensee action to resolve the issue.
The Supplement also updated the information contained in the original bulletin. The licensee was requested to review the information and determine if it was applicable at their facility. Further, ~ a licensee was requested ;
to modify their actions and enhanced surveillance monitoring programs to conform wlth the dic.. tion given. rinally, the licensee was 'nstructed to 1
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respond to the NRC. The Reauested Actions in Supplement I to NRC Bulletin 90-01 supersede the original NRC Bulletin 90-01 Reauested Actions.
In responding to Supplement I to NRC Bulletin 90-01, the licensee is directed to address three items.
- 1. A statement either committing the licensee to take the NRC Bulletin 90-01, Supplement 1, Reauested Actions or taking exception to those actions.
- 2. Addressing the actions committed to in the above statement, provide:
- a. a list of the specific actions, including any justifications, to be taken to complete the commitment,
- b. a schedule for completion, and
- c. after completion, a statement confirming the actions committed to are complete.
- 3. A statement identifying the NRC Bulletin 90-01, Supplement 1, Reauested Actions not taken, along with :n evaluation providing the basis for exemption.
In implementing the replacement option of the NRC Reauested Actions, plant shutdown exclusively for replacing the transmitters is not required. l This allowance infers that replacements can be scheduled. With replacement in a timely manner, enhanced surveillance monitoring for interim operation is not required.
The North Atlantic Energy Service Corporation, the licensee for the Seabrook Station, responded to Supplement 1 of NRC Bulletin 90-01 with a letter dated March 3, 1993 (Reference 3). That response referred to a previous response to the Bulletin dated July 17, 1990 (Reference 4). The licensee provided additional information in a letter dated July 15, 1994 (Reference 5). This technical evaluation report evaluates the completeness of 2
those submittals. It also determines whether proposed surveillance methods are adequate to determine fill-oil loss-caused degradation of the transmitter.
Finally, this report addresses the interval of surveillance proposed by the licensee for any transmitters included in the enhanced surveillance monitoring program.
Many Rosemount transmitter failures have been attributed to the use of stainless steel "0"-rings between the sensing module and the process flanges.
Rosemount improved the manufacturing process for transmitters manufactured after July 11, 1989. Those improvements included a limit of the torque applied to the flange bolts. This limits the stress caused in the sensing module by the "0"-ring. Post-production screening, including pressure testing of the sensing module for this potential latent defect, was also implemented at that time. Therefore, as described in Supplement 1 of NRC Bulletin 90-01, those ..asemount transmitters manufactured after July 11, 19es, are not subject to this review.
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- 2. NRC SPECIFIED REQUESTED ACTIONS The NRC staff specified the following Reauested Actions of licensees of operating reactors.
- 1. Review plant records and identify the following Rosemount transmitters (if manufactured before July 11,1989) that either are used in or may be used in either safety-related or ATWS mitigating systems.
- Rosemount Model 1153, Series B
- Rosemount Model 1153, Series D
- Rosemount Model 1154 Following identification, the licensee is to establish the following:
- a. For those identified transmitters having a norinal operating pressure greater than 1500 psi, and are installed as part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter in an expedited manner, or monitor monthly, for the life of the transmitter, using an enhanced surveillance program.
If the identified transmitter exceeds the 60,000 psi-month or the 130,000 psi-month criterion (depending on the range code of the transmitter) established by Rosemount, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be based on the service record and the specific safety function of the transmitter. That justification can be based on high functional reliability provided by redundancy or diversity.
- b. For those identified transmitters having a normal operating pressure greater than 1500 psi, and are installed as part of a safety-related system other than reactor protection trip systems, ESF actuation, or ATWS mitigating systems, either replace the transmitter or monitor quarterly, for the life of the transmitter, using an enhanced surveillance program.
If the identified transmitter exceeds the 60,000 psi-month or the 130,000 psi-month criterion (depending on the range code of the transmitter) established by Rosemount, enhanced surveillance on a refueling (not exceeding 24 months) basis is acceptable. Under this option, justification must be Nsed on the service record and tha specific safety function of t % transmitter. That 4
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justification can be based on high functional reliability provided ,
by redundancy or diversity. '
- c. For boiling water reactors (BWR)--
For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to ,
1500 psi, and are installed as part of reactor protection -
trip systems, ESF actuation systems, or ATWS mitigating >
systems, either replace the transmitter, or monitor monthly with an enhanced surveillance monitoring program, until the ,
transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000* psi-month, depending on the transmitter range code).
For transmitters that provide signals to the RPS or ATWS ,
trips for high pressure or low water level, the enhanced surveillance must be monthly. For other transmitters in ;
this classification, enhanced surveillance on a refueling ,
(not exceeding 24 months) basis is acceptable. Under this '
option, justification must be based on the service record >
and the specific safety function of the transmitter. That -
justification can be based on high functional reliability provided by redundancy or diversity. ,
For pressurized water reactors (PWR)--
For those identified transmitters having a normal operating pressure greater than 500 psi and less than or equal to.
1500 psi, and are installed as part of reactor protection trip systems, ESF actuation systems, or ATWS mitigating systems, either replace the transmitter, or monitor with an enhanced surveillance monitoring program, until the ,
transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code) on a refueling (not exceeding 24 months) basis,
- d. For those identified transmitters having a normal operating '
pressure greater than 500 psi and less than or equal to 1500 psi, and are installed as part of a safety-related system other than reactor protection trip systems, ESF actuation, or ATWS mitigating systems, either replace the transmitter or monitor with an enhanced surveillance monitoring program, until the transmitter reaches the designated (by Rosemount) psi-month criterion (60,000 psi-month or 130,000 psi-month, depending on the transmitter range code) on a refueling (not exceeding 24 months) basis.
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- e. Those transmitters having a normal operating pressure greater than 500 psi and less than or equal to 1500 psi, and have accumulated sufficient psi-month operating history to exceed the criterion established by Rosemount, may be excluded from the enhanced surveillance monitoring program at the discretion of the licensee.
However, the licensee should retain a high level of confidence that a high level of reliability is maintained and that transmitter failure due to loss of fill-oil is detectable.
- f. Those transmitters having a normal operating pressure less than or
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equal to 500 psi may be excluded from the enhanced surveillance monitoring program at the discretion of the licensee. However, the licensee should retain a high level of confidence that a high level of reliability is maintained and that transmitter failure due to loss of fill-oil is detectable.
- 2. Evaluate the enhanced surveillance monitoring program. The evaluation is to ensure the measurement data has an accuracy commensurate with the accuracy needed to compare the data to the manufacturers drift data criteria. It is this comparison that determines toe degradation threshold for loss of fill-oil failures of the subject transmitters.
The Supplement also states the NRC may conduct audits or inspections in the future to verify compliance with the established requirements.
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- 3. EVALUATION The licensee responded to Supplement 1 of NRC Bulletin 90-01 on March 3, 1993. That response incorporated information from a July 17, 1990, letter.
The licensee provided additional information on July 15, 1994. Those responses were compared to the Bulletin Reportina Reauirements and Reauested Actions as described below. The licensee reported starting an enhanced surveillance monitoring program for Rosemount transmitters that are subject to the Requested Actions of the Supplement in May 1990. The licensee states their enhanced surveillance monitoring program satisfies the Reauested Actions of the Supplement. Other Rosemount transmitters are outside the scope of the Supplement due to replacement, refurbishment, or use in non-safety applications. >
3.1 Evaluation of Licensee Response to Reoortina Reauirements The licensee states the actions taken in response to the original NRC Bulletin 90-01 satisfy the Reauested Actions detailed in Supplement 1 of NRC Bulletin 90-01. Included with that statement is clarification, interpretation, and the limits placed on their actions. The licensee described the specific steps taken to comply to the Reauested Actions of the Supplement in References 3, 4, and 5. Reference 3 includes a commitment to include any subject Rosemount transmitters installed in the future (presently held as spares) in the enhanced surveillance monitoring program.
The licensee submittals conform to the Reportino Reauirements of Supplement 1 of NRC Bulletin 90-01.
l 3.2 Evaluation of Licensee Response to Reauested Actions l l
Supplement 1 of NRC Bulletin 90-01 requested licensee action to resolve the issue of fill-oil leakage in Rosemount transmitters. This Technical Evaluation Report summarizes the Reauested Actions and th. !ssociated l 7
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s transmitter criteria in Section 2. The licensee states they are not replacing any Rosemount Model 1153, Series B and D, or Model 1154 transmitter, either installed or held as spare stock, in response to the Supplement. Instead, an enhanced surveillance program operates at the Seabrook Station. The licensee states that the enhanced surveillance program covers the 61 Rosemount transmitters that are included in the scope of this review. The following sections discuss the licensee response to the Supplement.
3.2.1 Licensee Response to Reauested Action 1.a The licensee states they will systematically monitor all Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters in this transmitter classification for the installed life of each transmitter. The nionitoring includes trending of calibration and operational data, and performance of monthly (or more frequent) channel checks. The program specifies corrective actions should a transmitter display behavior indicative of sensor oil-loss. The licensee description of their enhanced surveillance program for this transmitter classification satisfies this requested action and is acceptable.
3.2.2 Licensee Response to Reauested Action 1.b The licensee states they will systematically monitor all Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters in this transmitter classification for the instslied life of each transmitter. The monitoring includes trending of calibration and operational data, and performance of channel checks at least quarterly. The program specifies corrective actions should a transmitter display behavior indicative of sensor oil-loss. The licensee description of their enhanced surveillance program for this transmitter classification satisfies this requested action and is acceptable.
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o 3.2.3 Licensee Response to Reouested Action 1.c l l
1 The licensee states they will systematically monitor all Rosemount Model l 1153 Series B, Model 1153 Series D, and Model 1154 transmitters in this transmitter classification for the installed life of each transmitter or until the transmitter reaches the appropriate psi-month maturity threshold recommended by Rosemount and endorsed by the NRC. The monitoring includes trending of calibration and operational data, and performance of channel checks. The licensee will monitor these transmitters at least once every refueling cycle, with a maximum interval not exceeding 24 months. The program '
specifies corrective actions should a transmitter display behavior indicative l of sensor oil-loss. The licensee description of their enhanced surveillance j program for this transmitter classification satisfies this requested action and is acceptable.
3.2.4 Licensee Response to Reouested Action 1.d ;
The licensee states they will systematically monitor all Rosemount Model )
1153 Series B, Model 1153 Series D, and Model 1154 transmitters in this !
transmitter classification for the installed life of each transmitter or until the transmitter reaches the appropriate psi-month maturity threshold recommended by Rosemount and endorsed by the NRC. The monitoring includes trending of calibration and operational data, and performance of channel checks. The licensee will monitor these transmitters at least once every refueling cycle, with a maximum interval not exceeding 24 months. The program -
specifies corrective actions should a transmitter display behavior indicative of sensor oil-loss. The licensee description of their enhanced surveillance program for this transmitter classification satisfies this requested action and is acceptable.
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3.2.5 Licensee Response to Reouested Action 1,e The licensee states they will systematically monitor all Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters in this transmitter classification for the installed life of each transmitter. The monitoring includes trending of calibration and operational data, and performing channel checks. The licensee will monitor these transmitters at least once every refueling cycle, with a maximum interval not exceeding 24 months. The program specifies corrective actions should a transmitter display behavior indicative of sensor oil-loss. The licensee description of their enhanced surveillance program for this transmitter classification satisfies this requested action and is acceptable.
3.2.6 Licensee Response to Reouested Action 1.f The licensee states they will systematically monitor all Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters in this transmitter classification for the installed life of each transmitter. The monitoring includes trending of calibration and operational data, and performing channel checks. The licensee will monitor these transmitters least once every refueling cycle, with a maximum interval not exceeding .
months. The program specifies corrective actions should a transmitter display behavior indicative of sensor oil-loss. The licensee description of their enhanced surveillance program for this transmitter classification satisfies this requested action and is acceptable.
The licensee notes that after demonstrating stable transmitter performance through six monthly channel checks and six quarterly channel checks, the licensee will discontinue the channel checks for this transmitter classification. Drift trending of calibration data will continue.
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a 3.2.7 Enhanced Surveillance Monitorina Proaram The licensee reviewed their enhanced surveillance program for Rosemount transmitters in response to the Supplement. The licensee concluded the enhanced surveillance program satisfies the requested actions of the Supplement. Further, the licensee states the calibration accuracy and the repeatability of measurements taken on-line are adequate to compare to the Rosemount drift limits.
The licensee described their enhanced surveillance program in Referenca 4. The program uses the guidelines of Rosemount Technical Bulletin No. 4 and consists of the following.
- 1. Training instrument and controls engineering, maintenance, and technical cupport personnel on the Rosemount fill-oil loss 'ist- y, symptoms, and the need for prompt identification of failed transmitters.
- 2. Channel checks using data from the plant computer for redundant channels are performed weekly. Channel checks using test instruments are performed monthly. The monthly channel checks are on low pressure transmitters and transmitters in standby service, such as the emergency feedwater flow transmitters. The licensee trends this data to look for possible signs of fill-oil loss.
- 3. Trending zero and span shift using calibration data.
- 4. Scheduling additional transmitter calibrations in response to noted drift that does not exceed the Rosemount drift limits.
- 5. Review of plant computer post-mortem reports following unit transients that result in reactor trips or safety injection actuations. This compares the response times for:
2 charging pump discharge flow transmitters 4 pressurizer pressure transmitters 3 pressurizer level transmitters 12 steam generator level transmitters
- 6. Technicians look at transmitter response time when calibrating the transmitters.
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- 7. A quantitative response time test is performed on suspect transmitters to verify the loss of fill-cil. This test incorporates the guidelines of Rosemount Technical Bulletin No. 4.
The licensee description of their enhanced surveillance program meets the reporting requirements of the Supplement and is acceptable The licensee states, in Reference 3, that the enhanced surveillance program identified three Rosemount transmitters which had experienced loss of sensor fill-oil. The licensee later confirmed these transmitters had failed due to loss of fill-oil.
Based on the surveillance program described by the licensee, the enhanced surveillance program is acceptable.
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- 4. CONCLUSIONS Based on our review, we find the licensee has completed the reporting requirements of Supplement 1 of NRC Bulletin 90-01. Further, the licensee conforms to the requested actions of Supplement I to NRC Bulletin 90-01.
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- 5. REFERENCES
- 1. NRC Bulletin No. 90-01: " Loss of Fill-oil-in Transmitters Manufactured by Rosemount," March 9, 1990, OMB No. 3150-0011.
- 2. NRC Bulletin No. 90-01, Supplement 1: " Loss of Fill-oil in Transmitters Manufactured by Rosemount," December 22, 1992, OMB No. 3150-0011,
- 3. Letter, North Atlantic Energy Service Corporation (T. C. Feigenbaum) to NRC, " Response to NRC Bulletin 90-01, Supplement 1, (TAC M85441),"
March 3, 1993, NYH-93037.
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- 4. Letter, New Hampshire Yankee Division of Public Service Company of New Hampshire, " Response to NRC Bulletin No. 90-01, ' Loss of Fill-oil in Transmitters Manufactured by Rosemount'," July 17, 1990, NYH-90139. ,
- 5. Letter, North Atlantic Energy Service Corporation (T. C. Feigenbaum) to NRC, " Response to Request for Additional Information (TAC M85441),"
July 15, 1994, NYH-94076.
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