IE-116-B, Rept of Evaluation of Stresses in Recirculation Inlet Nozzle Safe-End at Brunswick Steam Electric Plant Units 1 & 2, Final Rept by Parameter,Inc.Recommends Continued Inservice SurveillanceML19210E036 |
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Site: |
Brunswick, Duane Arnold ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
11/15/1979 |
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From: |
Dean R, Vlies L PARAMETER, INC. |
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Shared Package |
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ML19210E032 |
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References |
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IE-116-B, NUDOCS 7911290189 |
Download: ML19210E036 (27) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20202B3891997-09-15015 September 1997 Rev 1 to, Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barriers Clad Power Cables ML20149L6491995-08-31031 August 1995 Plant TER on IPE Front End Analysis ML20149L6541995-08-31031 August 1995 Plant TER on IPE Back-End Submittal ML20094P1881995-05-31031 May 1995 TER, Duane Arnold Energy Ctr Pump & Valve Inservice Testing Program,Rev 13,Third 10-Yr Interval ML20063E9061993-12-30030 December 1993 Parametric Study of Potential for BWR ECCS Blockage Due to LOCA Generated Debris, Vol 2,Parts 1 & 2 ML1123805161993-11-12012 November 1993 TER to Request for TS Change,Ielp,Cipc & Cbpc,Daec. ML20118C0951992-08-0101 August 1992 Technical Evaluation of Duane Arnold Energy Ctr Emergency Svc Water ML20101Q3431992-06-30030 June 1992 Metallurgical Evaluation of Weld Overlaid Pipe Sections from Brunswick Unit 2 Nuclear Power Station ML20065C9611990-08-24024 August 1990 Rev 2 to Technical Evaluation Rept Brunswick Steam Electric Plant Units 1 & 2 Station Blackout Evaluation, Final Rept ML20011D9151989-11-30030 November 1989 Review of the Brunswick Steam Electric Plant Probabilistic Risk Assessment ML20071P7151989-11-30030 November 1989 Rev 1 to Brunswick Steam Electric Plant Unit 2 Risk-Based Insp Guide, Final Version ML20005E9971989-11-30030 November 1989 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1451989-07-10010 July 1989 Technical Evaluation Rept for Dcrdr at CP&L Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1471989-07-0707 July 1989 Post-Implementation Audit Rept for CP&L Brunswick Steam Electric Plant Units 1 & 2 SPDS 890515-18. ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20070Q5251989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Brunswick 1 & 2 ML20196D8781988-02-18018 February 1988 Technical Evaluation Rept of Dcrdr for Iowa Electric Light & Power Co Duane Arnold Energy Ctr ML20246B7221988-01-31031 January 1988 Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Relief Requests:Cp&L,Brunswick Steam Electric Plant, Units 1 & 2 ML20246P9671988-01-31031 January 1988 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan,Brunswick Steam Electric Plant Unit 1 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20215L8821987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Brunswick 1 & 2, Informal Rept ML20215M0881987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Duane Arnold, Informal Rept ML20215L8631987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Brunswick 1 & 2, Informal Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML20211P0681986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Duane Arnond Energy Ctr, Supplementary Technical Evaluation Rept ML20211P0781986-07-16016 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Brunswick Steam Electric Plant Units 1 & 2, Supplementary Technical Evaluation Rept ML20203P9991986-03-0707 March 1986 Site Survey of Brunswick Steam Electric Plant Units 1 & 2 Maint Program & Practices, Technical Ltr Rept ML20127P3631985-06-30030 June 1985 IN-PLANT Source Term Measurements at Brunswick Steam Electric Station ML20132D6281985-06-28028 June 1985 Masonry Wall Design,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20128N6481985-05-31031 May 1985 Adequacy of Station Electric Distribution Sys Voltages, Brunswick Steam Electric Station,Units 1 & 2, Informal Rept ML20128A5741985-03-25025 March 1985 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Informal Rept ML20127D6251985-03-15015 March 1985 Evaluation of Detailed Control Room Design Review Program Plan for Brunswick Steam Electric Plant,Units 1 & 2 ML20106G0091984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Technical Evaluation Rept ML20115A3821984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Interim Technical Evaluation Rept ML20100R7141984-10-30030 October 1984 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Interim Rept Covering Emergency Response Capability ML20091G1011984-05-30030 May 1984 Control of Heavy Loads (C-10),Iowa Electric Light & Power Co,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20090H7121984-04-23023 April 1984 Control of Heavy Loads,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J3181983-10-0707 October 1983 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J0541983-09-30030 September 1983 Technical Evaluation of Brunswick Units 1 & 2,Plant-Unique Analysis Rept ML20091D6541983-07-31031 July 1983 Integrity of Brunswick Steam Electric Plant,Units 1 & 2 Reactor Coolant Boundary Piping Sys, Technical Evaluation ML20079Q7261983-06-13013 June 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Brunswick Steam Electric Plant,Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065R2451982-07-15015 July 1982 Operating Reactors - TMI Lessons Learned,NUREG-0737 Response Evaluations (Program Ii);Project 1,RCS Vents for Brunswick 1 & 2, Final Technical Evaluation Rept ML20078Q6001982-07-0909 July 1982 Control of Heavy Loads,Brunswick Units 1 & 2, Draft Technical Evaluation Rept ML20069E1781982-06-30030 June 1982 Investigation of Raychem Cable Installed in Brunswick Plant,Phase 2-Evaluation & Test Recommendation ML20069E4381982-04-26026 April 1982 Technical Evaluation Rept on Monitoring of Electric Power to Reactor Protection Sys for Brunswick Steam Electric Plant,Units 1 & 2 ML20039A1151981-12-10010 December 1981 Masonry Wall Design:Ia Electric Light & Power Co,Duane Arnold Energy Ctr, Interim Technical Evaluation Rept ML20039A9471981-11-30030 November 1981 Aquatic Impacts from Operation of Three Midwestern Nuclear Power Stations.Duane Arnold Energy Center,Unit No. 1 Environmental Appraisal Report 1997-09-15
[Table view] Category:QUICK LOOK
MONTHYEARML20202B3891997-09-15015 September 1997 Rev 1 to, Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barriers Clad Power Cables ML20149L6491995-08-31031 August 1995 Plant TER on IPE Front End Analysis ML20149L6541995-08-31031 August 1995 Plant TER on IPE Back-End Submittal ML20094P1881995-05-31031 May 1995 TER, Duane Arnold Energy Ctr Pump & Valve Inservice Testing Program,Rev 13,Third 10-Yr Interval ML20063E9061993-12-30030 December 1993 Parametric Study of Potential for BWR ECCS Blockage Due to LOCA Generated Debris, Vol 2,Parts 1 & 2 ML1123805161993-11-12012 November 1993 TER to Request for TS Change,Ielp,Cipc & Cbpc,Daec. ML20118C0951992-08-0101 August 1992 Technical Evaluation of Duane Arnold Energy Ctr Emergency Svc Water ML20101Q3431992-06-30030 June 1992 Metallurgical Evaluation of Weld Overlaid Pipe Sections from Brunswick Unit 2 Nuclear Power Station ML20065C9611990-08-24024 August 1990 Rev 2 to Technical Evaluation Rept Brunswick Steam Electric Plant Units 1 & 2 Station Blackout Evaluation, Final Rept ML20011D9151989-11-30030 November 1989 Review of the Brunswick Steam Electric Plant Probabilistic Risk Assessment ML20071P7151989-11-30030 November 1989 Rev 1 to Brunswick Steam Electric Plant Unit 2 Risk-Based Insp Guide, Final Version ML20005E9971989-11-30030 November 1989 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1451989-07-10010 July 1989 Technical Evaluation Rept for Dcrdr at CP&L Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1471989-07-0707 July 1989 Post-Implementation Audit Rept for CP&L Brunswick Steam Electric Plant Units 1 & 2 SPDS 890515-18. ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20070Q5251989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Brunswick 1 & 2 ML20196D8781988-02-18018 February 1988 Technical Evaluation Rept of Dcrdr for Iowa Electric Light & Power Co Duane Arnold Energy Ctr ML20246B7221988-01-31031 January 1988 Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Relief Requests:Cp&L,Brunswick Steam Electric Plant, Units 1 & 2 ML20246P9671988-01-31031 January 1988 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan,Brunswick Steam Electric Plant Unit 1 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20215L8821987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Brunswick 1 & 2, Informal Rept ML20215M0881987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Duane Arnold, Informal Rept ML20215L8631987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Brunswick 1 & 2, Informal Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML20211P0681986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Duane Arnond Energy Ctr, Supplementary Technical Evaluation Rept ML20211P0781986-07-16016 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Brunswick Steam Electric Plant Units 1 & 2, Supplementary Technical Evaluation Rept ML20203P9991986-03-0707 March 1986 Site Survey of Brunswick Steam Electric Plant Units 1 & 2 Maint Program & Practices, Technical Ltr Rept ML20127P3631985-06-30030 June 1985 IN-PLANT Source Term Measurements at Brunswick Steam Electric Station ML20132D6281985-06-28028 June 1985 Masonry Wall Design,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20128N6481985-05-31031 May 1985 Adequacy of Station Electric Distribution Sys Voltages, Brunswick Steam Electric Station,Units 1 & 2, Informal Rept ML20128A5741985-03-25025 March 1985 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Informal Rept ML20127D6251985-03-15015 March 1985 Evaluation of Detailed Control Room Design Review Program Plan for Brunswick Steam Electric Plant,Units 1 & 2 ML20106G0091984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Technical Evaluation Rept ML20115A3821984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Interim Technical Evaluation Rept ML20100R7141984-10-30030 October 1984 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Interim Rept Covering Emergency Response Capability ML20091G1011984-05-30030 May 1984 Control of Heavy Loads (C-10),Iowa Electric Light & Power Co,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20090H7121984-04-23023 April 1984 Control of Heavy Loads,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J3181983-10-0707 October 1983 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J0541983-09-30030 September 1983 Technical Evaluation of Brunswick Units 1 & 2,Plant-Unique Analysis Rept ML20091D6541983-07-31031 July 1983 Integrity of Brunswick Steam Electric Plant,Units 1 & 2 Reactor Coolant Boundary Piping Sys, Technical Evaluation ML20079Q7261983-06-13013 June 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Brunswick Steam Electric Plant,Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065R2451982-07-15015 July 1982 Operating Reactors - TMI Lessons Learned,NUREG-0737 Response Evaluations (Program Ii);Project 1,RCS Vents for Brunswick 1 & 2, Final Technical Evaluation Rept ML20078Q6001982-07-0909 July 1982 Control of Heavy Loads,Brunswick Units 1 & 2, Draft Technical Evaluation Rept ML20069E1781982-06-30030 June 1982 Investigation of Raychem Cable Installed in Brunswick Plant,Phase 2-Evaluation & Test Recommendation ML20069E4381982-04-26026 April 1982 Technical Evaluation Rept on Monitoring of Electric Power to Reactor Protection Sys for Brunswick Steam Electric Plant,Units 1 & 2 ML20039A1151981-12-10010 December 1981 Masonry Wall Design:Ia Electric Light & Power Co,Duane Arnold Energy Ctr, Interim Technical Evaluation Rept ML20039A9471981-11-30030 November 1981 Aquatic Impacts from Operation of Three Midwestern Nuclear Power Stations.Duane Arnold Energy Center,Unit No. 1 Environmental Appraisal Report 1997-09-15
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20202B3891997-09-15015 September 1997 Rev 1 to, Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barriers Clad Power Cables ML20149L6491995-08-31031 August 1995 Plant TER on IPE Front End Analysis ML20149L6541995-08-31031 August 1995 Plant TER on IPE Back-End Submittal ML20094P1881995-05-31031 May 1995 TER, Duane Arnold Energy Ctr Pump & Valve Inservice Testing Program,Rev 13,Third 10-Yr Interval ML20063E9061993-12-30030 December 1993 Parametric Study of Potential for BWR ECCS Blockage Due to LOCA Generated Debris, Vol 2,Parts 1 & 2 ML1123805161993-11-12012 November 1993 TER to Request for TS Change,Ielp,Cipc & Cbpc,Daec. ML20118C0951992-08-0101 August 1992 Technical Evaluation of Duane Arnold Energy Ctr Emergency Svc Water ML20101Q3431992-06-30030 June 1992 Metallurgical Evaluation of Weld Overlaid Pipe Sections from Brunswick Unit 2 Nuclear Power Station ML20065C9611990-08-24024 August 1990 Rev 2 to Technical Evaluation Rept Brunswick Steam Electric Plant Units 1 & 2 Station Blackout Evaluation, Final Rept ML20011D9151989-11-30030 November 1989 Review of the Brunswick Steam Electric Plant Probabilistic Risk Assessment ML20071P7151989-11-30030 November 1989 Rev 1 to Brunswick Steam Electric Plant Unit 2 Risk-Based Insp Guide, Final Version ML20005E9971989-11-30030 November 1989 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1451989-07-10010 July 1989 Technical Evaluation Rept for Dcrdr at CP&L Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1471989-07-0707 July 1989 Post-Implementation Audit Rept for CP&L Brunswick Steam Electric Plant Units 1 & 2 SPDS 890515-18. ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20070Q5251989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Brunswick 1 & 2 ML20196D8781988-02-18018 February 1988 Technical Evaluation Rept of Dcrdr for Iowa Electric Light & Power Co Duane Arnold Energy Ctr ML20246B7221988-01-31031 January 1988 Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Relief Requests:Cp&L,Brunswick Steam Electric Plant, Units 1 & 2 ML20246P9671988-01-31031 January 1988 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan,Brunswick Steam Electric Plant Unit 1 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20215L8821987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Brunswick 1 & 2, Informal Rept ML20215M0881987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Duane Arnold, Informal Rept ML20215L8631987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Brunswick 1 & 2, Informal Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML20211P0681986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Duane Arnond Energy Ctr, Supplementary Technical Evaluation Rept ML20211P0781986-07-16016 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Brunswick Steam Electric Plant Units 1 & 2, Supplementary Technical Evaluation Rept ML20203P9991986-03-0707 March 1986 Site Survey of Brunswick Steam Electric Plant Units 1 & 2 Maint Program & Practices, Technical Ltr Rept ML20127P3631985-06-30030 June 1985 IN-PLANT Source Term Measurements at Brunswick Steam Electric Station ML20132D6281985-06-28028 June 1985 Masonry Wall Design,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20128N6481985-05-31031 May 1985 Adequacy of Station Electric Distribution Sys Voltages, Brunswick Steam Electric Station,Units 1 & 2, Informal Rept ML20128A5741985-03-25025 March 1985 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Informal Rept ML20127D6251985-03-15015 March 1985 Evaluation of Detailed Control Room Design Review Program Plan for Brunswick Steam Electric Plant,Units 1 & 2 ML20106G0091984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Technical Evaluation Rept ML20115A3821984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Interim Technical Evaluation Rept ML20100R7141984-10-30030 October 1984 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Interim Rept Covering Emergency Response Capability ML20091G1011984-05-30030 May 1984 Control of Heavy Loads (C-10),Iowa Electric Light & Power Co,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20090H7121984-04-23023 April 1984 Control of Heavy Loads,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J3181983-10-0707 October 1983 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J0541983-09-30030 September 1983 Technical Evaluation of Brunswick Units 1 & 2,Plant-Unique Analysis Rept ML20091D6541983-07-31031 July 1983 Integrity of Brunswick Steam Electric Plant,Units 1 & 2 Reactor Coolant Boundary Piping Sys, Technical Evaluation ML20079Q7261983-06-13013 June 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Brunswick Steam Electric Plant,Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065R2451982-07-15015 July 1982 Operating Reactors - TMI Lessons Learned,NUREG-0737 Response Evaluations (Program Ii);Project 1,RCS Vents for Brunswick 1 & 2, Final Technical Evaluation Rept ML20078Q6001982-07-0909 July 1982 Control of Heavy Loads,Brunswick Units 1 & 2, Draft Technical Evaluation Rept ML20069E1781982-06-30030 June 1982 Investigation of Raychem Cable Installed in Brunswick Plant,Phase 2-Evaluation & Test Recommendation ML20069E4381982-04-26026 April 1982 Technical Evaluation Rept on Monitoring of Electric Power to Reactor Protection Sys for Brunswick Steam Electric Plant,Units 1 & 2 ML20039A1151981-12-10010 December 1981 Masonry Wall Design:Ia Electric Light & Power Co,Duane Arnold Energy Ctr, Interim Technical Evaluation Rept ML20039A9471981-11-30030 November 1981 Aquatic Impacts from Operation of Three Midwestern Nuclear Power Stations.Duane Arnold Energy Center,Unit No. 1 Environmental Appraisal Report 1997-09-15
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20202B3891997-09-15015 September 1997 Rev 1 to, Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barriers Clad Power Cables ML20149L6491995-08-31031 August 1995 Plant TER on IPE Front End Analysis ML20149L6541995-08-31031 August 1995 Plant TER on IPE Back-End Submittal ML20094P1881995-05-31031 May 1995 TER, Duane Arnold Energy Ctr Pump & Valve Inservice Testing Program,Rev 13,Third 10-Yr Interval ML20063E9061993-12-30030 December 1993 Parametric Study of Potential for BWR ECCS Blockage Due to LOCA Generated Debris, Vol 2,Parts 1 & 2 ML1123805161993-11-12012 November 1993 TER to Request for TS Change,Ielp,Cipc & Cbpc,Daec. ML20118C0951992-08-0101 August 1992 Technical Evaluation of Duane Arnold Energy Ctr Emergency Svc Water ML20101Q3431992-06-30030 June 1992 Metallurgical Evaluation of Weld Overlaid Pipe Sections from Brunswick Unit 2 Nuclear Power Station ML20058A1131990-09-27027 September 1990 Notification of Contract Execution,Awarding Task Order 3, NDE Support at Brunswick 1 Nuclear Power Plant. Contractor:Tet,Inc ML20065C9611990-08-24024 August 1990 Rev 2 to Technical Evaluation Rept Brunswick Steam Electric Plant Units 1 & 2 Station Blackout Evaluation, Final Rept ML20071P7151989-11-30030 November 1989 Rev 1 to Brunswick Steam Electric Plant Unit 2 Risk-Based Insp Guide, Final Version ML20011D9151989-11-30030 November 1989 Review of the Brunswick Steam Electric Plant Probabilistic Risk Assessment ML20005E9971989-11-30030 November 1989 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1451989-07-10010 July 1989 Technical Evaluation Rept for Dcrdr at CP&L Brunswick Steam Electric Plant,Units 1 & 2. ML19325C1471989-07-0707 July 1989 Post-Implementation Audit Rept for CP&L Brunswick Steam Electric Plant Units 1 & 2 SPDS 890515-18. ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20070Q5251989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Brunswick 1 & 2 ML20196D8781988-02-18018 February 1988 Technical Evaluation Rept of Dcrdr for Iowa Electric Light & Power Co Duane Arnold Energy Ctr ML20246B7221988-01-31031 January 1988 Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Relief Requests:Cp&L,Brunswick Steam Electric Plant, Units 1 & 2 ML20246P9671988-01-31031 January 1988 Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan,Brunswick Steam Electric Plant Unit 1 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20215M0881987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Duane Arnold, Informal Rept ML20215L8821987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Brunswick 1 & 2, Informal Rept ML20215L8631987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Brunswick 1 & 2, Informal Rept ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML20211P0681986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Duane Arnond Energy Ctr, Supplementary Technical Evaluation Rept ML20211P0781986-07-16016 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Brunswick Steam Electric Plant Units 1 & 2, Supplementary Technical Evaluation Rept ML20203P9991986-03-0707 March 1986 Site Survey of Brunswick Steam Electric Plant Units 1 & 2 Maint Program & Practices, Technical Ltr Rept ML20127P3631985-06-30030 June 1985 IN-PLANT Source Term Measurements at Brunswick Steam Electric Station ML20132D6281985-06-28028 June 1985 Masonry Wall Design,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20128N6481985-05-31031 May 1985 Adequacy of Station Electric Distribution Sys Voltages, Brunswick Steam Electric Station,Units 1 & 2, Informal Rept ML20128A5741985-03-25025 March 1985 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Informal Rept ML20127D6251985-03-15015 March 1985 Evaluation of Detailed Control Room Design Review Program Plan for Brunswick Steam Electric Plant,Units 1 & 2 ML20115A3821984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Interim Technical Evaluation Rept ML20106G0091984-11-16016 November 1984 Masonry Wall Design,Brunswick Steam Electric Plant Units 1 & 2, Technical Evaluation Rept ML20100R7141984-10-30030 October 1984 Conformance to Reg Guide 1.97,Brunswick Steam Electric Plant Units 1 & 2, Interim Rept Covering Emergency Response Capability ML20091G1011984-05-30030 May 1984 Control of Heavy Loads (C-10),Iowa Electric Light & Power Co,Duane Arnold Energy Ctr, Technical Evaluation Rept ML20090H7121984-04-23023 April 1984 Control of Heavy Loads,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J3181983-10-0707 October 1983 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors,Brunswick Units 1 & 2, Technical Evaluation Rept ML20085J0541983-09-30030 September 1983 Technical Evaluation of Brunswick Units 1 & 2,Plant-Unique Analysis Rept ML20091D6541983-07-31031 July 1983 Integrity of Brunswick Steam Electric Plant,Units 1 & 2 Reactor Coolant Boundary Piping Sys, Technical Evaluation ML20079Q7261983-06-13013 June 1983 ECCS Repts (F-47) TMI Action Plan Requirements,Brunswick Steam Electric Plant,Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20065R2451982-07-15015 July 1982 Operating Reactors - TMI Lessons Learned,NUREG-0737 Response Evaluations (Program Ii);Project 1,RCS Vents for Brunswick 1 & 2, Final Technical Evaluation Rept ML20078Q6001982-07-0909 July 1982 Control of Heavy Loads,Brunswick Units 1 & 2, Draft Technical Evaluation Rept ML20069E1781982-06-30030 June 1982 Investigation of Raychem Cable Installed in Brunswick Plant,Phase 2-Evaluation & Test Recommendation ML20069E4381982-04-26026 April 1982 Technical Evaluation Rept on Monitoring of Electric Power to Reactor Protection Sys for Brunswick Steam Electric Plant,Units 1 & 2 ML20039A1151981-12-10010 December 1981 Masonry Wall Design:Ia Electric Light & Power Co,Duane Arnold Energy Ctr, Interim Technical Evaluation Rept 1997-09-15
[Table view] |
Text
e (i)
Report No, IE-116-B Evaluation of Stresses in Recirculation Inlet Nozzle Safe-End at Brunswick Steam Electric Plant Units 1 and 2 of Carolina Power and Light Co.
R. S. Dean L. E. Vlies PARAMETER, Irac .
Prepared for 4[h' 7
U. S. Nuclear Regulatory Commission 7911290 Iff!
e
4
. (ii)
NorICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or re-sponsibility for any third party's use, or the results of such use, of any in-formation, apparatus, product or process disclosed in this report, or represents that its use by such third party c:culd not infringe privately owned rights.
The views expressed in this report are not necessarily those of the U. S.
Nuclear Regulatory Commission.
Available from U.S. Nuclear Regulatory Commission Washington, D. C. 20555 1435 078
. . . (iii)
IE-116-8 Distribution Cor.ies Nuclear Regulatory Commission Technical Assistance Branch Office of Inspection 40 and Enforcement PARAMETER, Inc.
File Copy 1 1435 179
Report of Evaluation of Stresses in Recirculation Inlet Nozzle Safe-End at Brunswick Steam Blectric Plant Units 1 and 2 of Carolina Power and Light Co.
Report No. IE-116-B, Prepared for: United States Nuclear Regulatory Commission Office of Inspection & Enforcement NRC Contract 05-77-186 PAR: NRC-IE-78/79, Task 03
$ gottsiteers,,,o GOhlg r
[c / ROBERT S. A ?.
- I DEAN 5 By:
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PARAMETER, Inc.
Consulting Engineers Elm Grcve, Wisconsin ghj '
- - Page 2 SECTION I Abstract A review is made of safe-end stresses at the safe-end/ thermal sleeve weld location for comparison to s tresses at the corres-ponding location at the Duane Arnold Energy Center of Iowa Electric Power and Light Company, where safe-end cracks oc-curred. The purpose is to evaluate the possibility of crack-ing occurring in the future at Brunswick. Stress figures are extracted from the original design analysis report of the Brunswick plant. These are then compared to Duane Arnold stress figures taken from the original design stress report, but adjusted to be on the same analysis basis as the Brunswick figures. Results show stress levels at Brunswick to be enough lower than at Duane Arnold to substantially reduce the prob-ability of cracking. The crevice-like sleeve / safe-end weld joint is similar, however, which leaves the potential for crack-ing present. Continued in-service inspection surveillance of this section is recommended.
\
s
- Page 3 CONTENTS Page Abstract 2 Contents 3 Introduction 4 Summary 5 Comments and Conclusion 6 References 7 Fig. 1: Detail of Safe End, Brunswick 8 Fig. 2: Detail of Safe End, Duane Arnold 9 Differences and Similarities of Brunswick and Duane Arnold Designs 10 Piping Loa ds and Stresses, Duane Arnold 11 to 13 Calculation and Comparison of Primary Stresses 14 & 15 Primary plus Secondary Stresses, Brunswick 16 Primary plus Secondary Stresses, Duane Arnold 17 Peak Stress Comparison 20 Fatigue Life Comparison 21 .
)hbE, Plot of Axial Stress Cycling, Duane Arnold 23 Plot of Axial Stress Cycling, Brunswick 24
- Page 4 Introduction A review of recirculation inlet pipe stresses at the thermal sleeve to safe end weld joint crevice location is made of the Brunswick Steam Electric Plant (BSEP). Camparisons are made to stresses at the corresponding location of the Duane Arnold Energy Center (DAEC).
The main purpose of the review is to evaluate the stresso, relative to probability of cracking occurring at Brunswick in a similar manner to the cracking which did occur at Duane Arnold.
The design at Brunswick is similar to that at Duane Arnold, with the crevice at the sleeve / safe end joint (see pp. 8 & 9).
The essential similarities and differences of the two designs are tabulated on page 10.
Stresses for Brunswick are from the stress summary sections of the original Chicago Bridge and Iron stress analysis report (Ref.1). These are recalculated as required to avoid non-code assumptions (e.g., addition of stress intensities, rather than stresses, for superimposing stresses from piping loads onto those from pressure and thermal loading; ref.1, pp. S8-21, 31,
& 33) . The stresses for Duane Arnold are recalculated on the same analytical basi.s for proper comparison, taking data from the original DAEC report by CB&I (ref.2).
A plot of primary plus secondary axial stress is made (p.24) using an assumed cycling sequence for Brunswick (since none is given in ref.1). This is for comparison to a similar plot made for Duane Arnold for ref.3, which is reproduced and included in this report (p.23).
Fatigue analyses are made for both Duane Arnold and Brunwick, using the same cyclic requirements for Brunswick as for Duane Arnold, since none are given in reference 1 This also gives a more direct comparison of the two designs from fatigue analysis.
I, 4 k h. h
Page 5 Summary 1 Primary stress intensity for the Brunswick safe er.d c.t the crevice is 60% of that for Duane Arnold.
- 2. Primary plus secondary stress for Brunswick is 53% of that for Duane Arnold.
- 3. Peak stress for Brunswick is 305 to 50% of that for Duane Arnold.
- 4. The fatigue usage factor for Brunswick is less than 2%
of that for Duane Arnold, using the same load cycling for direct comparison.
I435 084
Page 6 Comments ,
- 1. It can be seen frc= the summary (pg.5) that Brunswick stresses at the thermal sleeve / safe end joint location are well below those of Duane Arnold. The safe end machining configuration of Duane Arnold made the safe end wall tl.ichness least at this location, which is not the case for the Brunswick design, where propor-tionately greater wall thickness remains at this section.
- 2. For both designs, stress levels of all Code stress cate-gories (general primary membrane, local primary membrane, primary plus secondary, and peak) are within Code limits.
- 3. The presence of the crevice formed by the weld joint creates the potential for cracking. The probability cracking will occur at Brunswick is much reduced from Duane Arnold, due to the lower stresses and proportion-ally thicker wall. However, a threshold of stress below which stress corrosion cracking will never occur with the presence of a crack-like crevice has not been established definitely. However it is currently fairly well agreed that for stress corrosion cracking to occur, at least yield stress level is required, along with a corrosive environ-ment and a susceptible material. The safe-end primary-plus-secondary stress level at the crevice of the Brunswick design is approximately equal to yield strength. At Duane Arnold, it was approximately twice yield strength.
- 4. The assumed residual stress from welding of yield stress magnitude is shown to shake down by load cycling (see plot, pg.24). This is a similar situation to that for Duane Arnold, where it was empnasized that load stresses werr high enough to cause cracking with or without initial residual stress (ref.3,pg. 16).
- 5. The wider annulus between the thermal sleeve and the nozzle I.D. (.50 radial width vs. .125 for Duane Arnold) should promote better circulation and reduce rate of contamination buildup at the crevice.
1435 185 Conclusion Brunswick stresses are considerably lower than those at Duane Arnold, but the potential for cracking is present because of the weld joint crevice. Crack propagation, should a crack occur, would be expected to be at a much slower rate than at Duane Arnold. Continued in-service inspection surveillance of this section is recommended.
1
~
Page 7 REFERENCES :
1 Stress Analysis, Section S8, Nozzle N2A/K, Recirculation Inlet, Brunswick Steam Electric Plant, Chicago Bridge &
Iron Company, Oak Brook Engineering, 1969.
- 2. Stress Analysis Report of Original Recirculation Inlet Nozzle N2, Section T8, S8, and F8, Duane Arnold Energy Center, Chicago Bridge & Iron Compa.ny, Rev. 1, Nov., 1971
- 3. Metallurgical E,xamination and Stress Evaluation of Recirculation Inlet Nozzle Safe-End Cracking at Duane Arnold Energy Center, Parameter, Inc., Report No. IE-116, for United States Nuclear Regulatory Commission, NRC Contract 05-77-186, March, 1979.
- 4. ASME Boiler and Pressure Vessel Code,Section III, Nuclear Vessels, 1968, with Summer 1968 Addenda.
- 5. Drawing, Duane Arnold Design, Thermal Sleeves for Recircu-lation Inlet No zzles Mark N2 A/H, Chicago Bridge and Iron Company, Contract 68-2967, Drawing No. 32, Sheet 7, Pur-chaser's No. 205H1289.
- 6. Rodabaugh, E. C., Task 8: Pipe Configuration and Stress Levels , Eattelle Columbus Laboratories for U.S.N.R.C. ,
Draft Copy, Nov. 30, 1978.
- 7. General Electric Drawing 921D217, Sheet 8, Rev. 10, Jet Pump Secondary Loads, Reactor Vessel, Duane Arnold.
- 8. Roark, R. J. , Formulas for Stress and Strain, 4th Edition, McGraw-Hill Book Company, 1965.
143S 186
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Differences and Similarities of Brunswick and Duane Arnold Designs From study of figures 1 and 2, the significant similarities and differences of the Brunswick safe end design to the de-sign at Duane Arnold are as follows:
Feature Brunswick Duane Arnold Nominal Inlet Pipe Size 12" sched tc 10" sched 80 Nominal Thermal Sleeve Size 12" sched 40S 10" sched 40 Safe End Wall Thickness at Thermal Sleeve Weld 1.125 .575 Crevice Length .50 .50 Annulus Width (betw Thermal Shield and Nozzle I.D.) .50 12 The safe end design at Duane Arnold had the thinnest wall section right at the sleeve / safe end weld joint, whereas, the design at Brunswick is thicker at this location than the pipe wall or the nozzle wall at forming the safe end. This produces lower stresses at the crevice section, as compared on the following pages.
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