Letter Sequence Other |
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MONTHYEARML20052E3951982-05-0404 May 1982 Revises 820414 Response to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Correction to Figure 14.3.4-1 Caused Error in Response to Items 3 & 4.Revised Figure Encl Project stage: Request ML20067D6311982-12-15015 December 1982 Comments on Technical Evaluation Rept Re Seismic Qualification of Auxiliary Feedwater Sys,Per 821112 Request. Recommendation to Acquire Complete SSE Level of Seismic Capacity Constitutes Unnecessary & Expensive Backfit Project stage: Other ML20064L8991983-02-11011 February 1983 Advises That Installation of Addl Supports for Auxiliary Feedwater Sys Piping & Components Rescheduled to June 1983, Due to Conflicts W/Other Plant Mods Project stage: Other ML20080B5531984-01-31031 January 1984 Provides Addl Info Re Status of Auxiliary Feedwater Sys Mods Implemented in Response to Generic Ltr 81-14.Last Remaining Mod Involves Replacement of Battery Rack Support Straps & Should Be Completed by Oct 1984 Project stage: Other ML20091J8581984-05-23023 May 1984 Emergency Operating Procedure Validation Procedure Project stage: Other ML20100J0891984-12-0404 December 1984 Provides Final Responses to Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys. Support Straps on Battery Racks Replaced as Scheduled in Project stage: Other ML20116D2981985-04-22022 April 1985 Notifies That Installation of Low Suction Pressure Automatic Trips on Auxiliary Feedwater Pumps Expected to Be Completed by 860131,in Response to NRC Request for Commitment Date Project stage: Request ML20206S7491986-05-31031 May 1986 Evaluation of Structural Aspects Re Point Beach Plant Project stage: Other ML20206S7091986-09-16016 September 1986 Safety Evaluation on Util 850426 Response to Open Items Re Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys (Afws). Reasonable Assurance Exists That Afws Will Perform Required Safety Function Following SSE Project stage: Approval ML20206S6861986-09-16016 September 1986 Forwards Safety Evaluation & Technical Evaluation Rept on Util 850426 Response to Open Items Re Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys. Addl Info Requested Re Diesel Generator Room Flooding Project stage: Approval ML20215N8401986-10-31031 October 1986 Advises of Features & Mods to Diesel Generator Room Air Exhaust Duct Louvers & Diesel Generator Voltage Regulator Cabinets in Response to Concerns Expressed in 860916 Safety Evaluation Re Util Compliance W/Generic Ltr 81-14 Project stage: Other ML20209H2971987-01-21021 January 1987 Advises That Mods to Protect Diesel Generator Voltage Regulator Cabinets from Fire Protection Sprinkler Operation Adequately Address NRC Concerns Identified in 860916 Safety Evaluation,Per Util Project stage: Approval 1984-05-23
[Table View] |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20212D6781999-03-31031 March 1999 Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20212D6411998-03-31031 March 1998 Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20078E0471994-10-0404 October 1994 TER on Front End IPE Submittal, Task 22,dtd 941004 ML20078E1221994-09-30030 September 1994 IPE Back-End TER Dtd Sept 1994 ML20141D3271994-08-31031 August 1994 Dispersion Estimates in Vicinity of Buildings ML20078E1501994-08-31031 August 1994 TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 ML20097A8281992-04-0606 April 1992 Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) ML20245E9371988-12-31031 December 1988 Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept ML20155G7521988-06-14014 June 1988 Review of Point Beach Nuclear Plant,Unit 1 & 2,Alternate Shutdown Capability ML20042D0531988-06-0707 June 1988 Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2. ML20154H5841988-05-12012 May 1988 App D,Evaluation of Offsite Dose Calculation Manual Rev 1 (Point Beach Nuclear Power Plant,Units 1 & 2) ML20235Y6591987-10-16016 October 1987 Technical Evaluation Rept for Wisconsin Electric Power Co Point Beach Nuclear Plant,Units 1 & 2 SPDS Sar ML20153D7671987-05-11011 May 1987 Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50, Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20206S7491986-05-31031 May 1986 Evaluation of Structural Aspects Re Point Beach Plant ML20198S9731986-04-30030 April 1986 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20133Q0961985-10-22022 October 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...for Point Beach Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML20127E7551985-02-28028 February 1985 Shutdown DHR Analysis,Point Beach Case Study, Draft Rept ML20108E0071984-12-31031 December 1984 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20108F3501984-11-0707 November 1984 Evaluation of Detailed Control Room Design Review Program Plan ML20086T8821984-03-0202 March 1984 Control of Heavy Loads (C-10) Wisconsin Electric Power Co Point Beach Nuclear Plant Units 1 & 2 ML20072K8201983-06-17017 June 1983 Control of Heavy Loads (C-10),Point Beach Nuclear Plants Units 1 & 2, Draft Final Technical Evaluation Rept ML20079Q6801983-02-23023 February 1983 Selected Operating Reactor Issues Program II RCS Sys Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K6701983-02-0909 February 1983 Adequacy of Electric Distribution Sys Voltages for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20076C3781982-12-10010 December 1982 ECCS Repts (F 47),TMI Action Plan Requirements,Point Beach Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G6741982-09-28028 September 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),Point Beach Nuclear Plant,Unit 1, Technical Evaluation Rept ML20079G6831982-09-28028 September 1982 Nonproprietary Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60),Point Beach Nuclear Plant Unit 2, Final Technical Evaluation Rept ML20028A7341982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items 1.A.2.1 & II.B.4 for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D2131982-07-31031 July 1982 Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2. ML20052C9371982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Point Beach,Units 1 & 2, Preliminary Technical Evaluation Rept ML20009B5961981-05-31031 May 1981 Technical Evaluation of Licensee Responses to IE Bulletin 80-06,re Engineered Safety Feature Reset Controls for Point Beach Nuclear Power Station,Units 1 & 2 ML19341B0861980-12-31031 December 1980 Instrument Bus Mods,Point Beach Nuclear Plant,Units 1 & 2. ML19323H4811979-09-30030 September 1979 Technical Evaluation of Electrical Instrumentation & Control Design Aspects of Override Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Point Beach Nuclear Power Station,Units 1 & 2. ML19225C4531979-04-27027 April 1979 Fire Protection in Operating Nuclear Power Stations:Point Beach Units 1 & 2 SER Review, Interim Rept 1999-03-31
[Table view] Category:QUICK LOOK
MONTHYEARML20212D6781999-03-31031 March 1999 Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20212D6411998-03-31031 March 1998 Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20078E0471994-10-0404 October 1994 TER on Front End IPE Submittal, Task 22,dtd 941004 ML20078E1221994-09-30030 September 1994 IPE Back-End TER Dtd Sept 1994 ML20141D3271994-08-31031 August 1994 Dispersion Estimates in Vicinity of Buildings ML20078E1501994-08-31031 August 1994 TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 ML20097A8281992-04-0606 April 1992 Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) ML20245E9371988-12-31031 December 1988 Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept ML20155G7521988-06-14014 June 1988 Review of Point Beach Nuclear Plant,Unit 1 & 2,Alternate Shutdown Capability ML20042D0531988-06-0707 June 1988 Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2. ML20154H5841988-05-12012 May 1988 App D,Evaluation of Offsite Dose Calculation Manual Rev 1 (Point Beach Nuclear Power Plant,Units 1 & 2) ML20235Y6591987-10-16016 October 1987 Technical Evaluation Rept for Wisconsin Electric Power Co Point Beach Nuclear Plant,Units 1 & 2 SPDS Sar ML20153D7671987-05-11011 May 1987 Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50, Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20206S7491986-05-31031 May 1986 Evaluation of Structural Aspects Re Point Beach Plant ML20198S9731986-04-30030 April 1986 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20133Q0961985-10-22022 October 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...for Point Beach Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML20127E7551985-02-28028 February 1985 Shutdown DHR Analysis,Point Beach Case Study, Draft Rept ML20108E0071984-12-31031 December 1984 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20108F3501984-11-0707 November 1984 Evaluation of Detailed Control Room Design Review Program Plan ML20086T8821984-03-0202 March 1984 Control of Heavy Loads (C-10) Wisconsin Electric Power Co Point Beach Nuclear Plant Units 1 & 2 ML20072K8201983-06-17017 June 1983 Control of Heavy Loads (C-10),Point Beach Nuclear Plants Units 1 & 2, Draft Final Technical Evaluation Rept ML20079Q6801983-02-23023 February 1983 Selected Operating Reactor Issues Program II RCS Sys Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K6701983-02-0909 February 1983 Adequacy of Electric Distribution Sys Voltages for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20076C3781982-12-10010 December 1982 ECCS Repts (F 47),TMI Action Plan Requirements,Point Beach Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G6741982-09-28028 September 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),Point Beach Nuclear Plant,Unit 1, Technical Evaluation Rept ML20079G6831982-09-28028 September 1982 Nonproprietary Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60),Point Beach Nuclear Plant Unit 2, Final Technical Evaluation Rept ML20028A7341982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items 1.A.2.1 & II.B.4 for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D2131982-07-31031 July 1982 Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2. ML20052C9371982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Point Beach,Units 1 & 2, Preliminary Technical Evaluation Rept ML20009B5961981-05-31031 May 1981 Technical Evaluation of Licensee Responses to IE Bulletin 80-06,re Engineered Safety Feature Reset Controls for Point Beach Nuclear Power Station,Units 1 & 2 ML19341B0861980-12-31031 December 1980 Instrument Bus Mods,Point Beach Nuclear Plant,Units 1 & 2. ML19323H4811979-09-30030 September 1979 Technical Evaluation of Electrical Instrumentation & Control Design Aspects of Override Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Point Beach Nuclear Power Station,Units 1 & 2. ML19225C4531979-04-27027 April 1979 Fire Protection in Operating Nuclear Power Stations:Point Beach Units 1 & 2 SER Review, Interim Rept 1999-03-31
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20212D6781999-03-31031 March 1999 Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20212D6411998-03-31031 March 1998 Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20078E0471994-10-0404 October 1994 TER on Front End IPE Submittal, Task 22,dtd 941004 ML20078E1221994-09-30030 September 1994 IPE Back-End TER Dtd Sept 1994 ML20141D3271994-08-31031 August 1994 Dispersion Estimates in Vicinity of Buildings ML20078E1501994-08-31031 August 1994 TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 ML20097A8281992-04-0606 April 1992 Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) ML20245E9371988-12-31031 December 1988 Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept ML20155G7521988-06-14014 June 1988 Review of Point Beach Nuclear Plant,Unit 1 & 2,Alternate Shutdown Capability ML20042D0531988-06-0707 June 1988 Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2. ML20154H5841988-05-12012 May 1988 App D,Evaluation of Offsite Dose Calculation Manual Rev 1 (Point Beach Nuclear Power Plant,Units 1 & 2) ML20235Y6591987-10-16016 October 1987 Technical Evaluation Rept for Wisconsin Electric Power Co Point Beach Nuclear Plant,Units 1 & 2 SPDS Sar ML20153D7671987-05-11011 May 1987 Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50, Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20206S7491986-05-31031 May 1986 Evaluation of Structural Aspects Re Point Beach Plant ML20198S9731986-04-30030 April 1986 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20133Q0961985-10-22022 October 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...for Point Beach Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML20127E7551985-02-28028 February 1985 Shutdown DHR Analysis,Point Beach Case Study, Draft Rept ML20108E0071984-12-31031 December 1984 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20108F3501984-11-0707 November 1984 Evaluation of Detailed Control Room Design Review Program Plan ML20086T8821984-03-0202 March 1984 Control of Heavy Loads (C-10) Wisconsin Electric Power Co Point Beach Nuclear Plant Units 1 & 2 ML20072K8201983-06-17017 June 1983 Control of Heavy Loads (C-10),Point Beach Nuclear Plants Units 1 & 2, Draft Final Technical Evaluation Rept ML20079Q6801983-02-23023 February 1983 Selected Operating Reactor Issues Program II RCS Sys Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K6701983-02-0909 February 1983 Adequacy of Electric Distribution Sys Voltages for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20076C3781982-12-10010 December 1982 ECCS Repts (F 47),TMI Action Plan Requirements,Point Beach Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G6741982-09-28028 September 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),Point Beach Nuclear Plant,Unit 1, Technical Evaluation Rept ML20079G6831982-09-28028 September 1982 Nonproprietary Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60),Point Beach Nuclear Plant Unit 2, Final Technical Evaluation Rept ML20028A7341982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items 1.A.2.1 & II.B.4 for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D2131982-07-31031 July 1982 Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2. ML20052C9371982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Point Beach,Units 1 & 2, Preliminary Technical Evaluation Rept ML20009B5961981-05-31031 May 1981 Technical Evaluation of Licensee Responses to IE Bulletin 80-06,re Engineered Safety Feature Reset Controls for Point Beach Nuclear Power Station,Units 1 & 2 ML19341B0861980-12-31031 December 1980 Instrument Bus Mods,Point Beach Nuclear Plant,Units 1 & 2. ML19323H4811979-09-30030 September 1979 Technical Evaluation of Electrical Instrumentation & Control Design Aspects of Override Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Point Beach Nuclear Power Station,Units 1 & 2. ML19225C4531979-04-27027 April 1979 Fire Protection in Operating Nuclear Power Stations:Point Beach Units 1 & 2 SER Review, Interim Rept 1999-03-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20212D6781999-03-31031 March 1999 Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20212D6411998-03-31031 March 1998 Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept ML20078E0471994-10-0404 October 1994 TER on Front End IPE Submittal, Task 22,dtd 941004 ML20078E1221994-09-30030 September 1994 IPE Back-End TER Dtd Sept 1994 ML20078E1501994-08-31031 August 1994 TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 ML20141D3271994-08-31031 August 1994 Dispersion Estimates in Vicinity of Buildings ML20097A8281992-04-0606 April 1992 Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) ML20245E9371988-12-31031 December 1988 Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept ML20155G7521988-06-14014 June 1988 Review of Point Beach Nuclear Plant,Unit 1 & 2,Alternate Shutdown Capability ML20042D0531988-06-0707 June 1988 Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2. ML20154H5841988-05-12012 May 1988 App D,Evaluation of Offsite Dose Calculation Manual Rev 1 (Point Beach Nuclear Power Plant,Units 1 & 2) 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 ML20235Y6591987-10-16016 October 1987 Technical Evaluation Rept for Wisconsin Electric Power Co Point Beach Nuclear Plant,Units 1 & 2 SPDS Sar ML20153D7671987-05-11011 May 1987 Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50, Technical Evaluation Rept ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20206S7491986-05-31031 May 1986 Evaluation of Structural Aspects Re Point Beach Plant ML20198S9731986-04-30030 April 1986 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20133Q0961985-10-22022 October 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...for Point Beach Nuclear Plant, Units 1 & 2, Technical Evaluation Rept ML20127E7551985-02-28028 February 1985 Shutdown DHR Analysis,Point Beach Case Study, Draft Rept ML20108E0071984-12-31031 December 1984 Conformance to Reg Guide 1.97,Point Beach Nuclear Plant, Units 1 & 2 ML20108F3501984-11-0707 November 1984 Evaluation of Detailed Control Room Design Review Program Plan ML20086T8821984-03-0202 March 1984 Control of Heavy Loads (C-10) Wisconsin Electric Power Co Point Beach Nuclear Plant Units 1 & 2 ML20072K8201983-06-17017 June 1983 Control of Heavy Loads (C-10),Point Beach Nuclear Plants Units 1 & 2, Draft Final Technical Evaluation Rept ML20079Q6801983-02-23023 February 1983 Selected Operating Reactor Issues Program II RCS Sys Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20077K6701983-02-0909 February 1983 Adequacy of Electric Distribution Sys Voltages for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20076C3781982-12-10010 December 1982 ECCS Repts (F 47),TMI Action Plan Requirements,Point Beach Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G6741982-09-28028 September 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),Point Beach Nuclear Plant,Unit 1, Technical Evaluation Rept ML20079G6831982-09-28028 September 1982 Nonproprietary Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60),Point Beach Nuclear Plant Unit 2, Final Technical Evaluation Rept ML20028A7341982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items 1.A.2.1 & II.B.4 for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20027D2131982-07-31031 July 1982 Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2. ML20052C9371982-02-28028 February 1982 Tech Specs for Redundant Decay Heat Removal Capability, Point Beach,Units 1 & 2, Preliminary Technical Evaluation Rept ML20009B5961981-05-31031 May 1981 Technical Evaluation of Licensee Responses to IE Bulletin 80-06,re Engineered Safety Feature Reset Controls for Point Beach Nuclear Power Station,Units 1 & 2 ML19341B0861980-12-31031 December 1980 Instrument Bus Mods,Point Beach Nuclear Plant,Units 1 & 2. ML19323H4811979-09-30030 September 1979 Technical Evaluation of Electrical Instrumentation & Control Design Aspects of Override Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Point Beach Nuclear Power Station,Units 1 & 2. ML19225C4531979-04-27027 April 1979 Fire Protection in Operating Nuclear Power Stations:Point Beach Units 1 & 2 SER Review, Interim Rept 1999-03-31
[Table view] |
Text
. ._. - - - - -
2 Evaluation of Structural Aspects Related i to the Point Beach Nuclear Plant by
^
C.A. Miller, Q. Liu, A.J. Philippacopoulos and C.J. Costantino 1
Structural Analysis Division Department of Nuclear Energy Brookhaven National Laboratory Upton, NY 11973 May 1986 l
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ABSTRACT This report describes an investigation which was c'arried out for the Point Beach Nuclear Plant. The purpose of this investigation was to evaluate structural aspects related to the condensate storge tanks and the facade strucure. This work was performed by the Structural Analysis i- Division of the Brookhaven National Laboratory for the Nuclear Regulatory Comission under FIN A-3826: " Indian Point Unit 2 and Point Beach Wind
! - Vulnerability Analysis".
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TABLE OF CONTENTS Page
~ ABSTRACT ...................................................... 11 LIST OF FIGURES
. . . . . . . . . . . . ................................... iv
1.0 INTRODUCTION
. . . . . ................................... 1 2.0 CONDENSATE STORAGE TANKS . . . . . . . . . . . . . . . . . . . . .. . . . . . . 1 3.0 : FACADE STRUCTURE . ................................... 2
4.0 CONCLUSION
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LIST OF FIGURES Figure Page 1 Condensate Storage Tanks .............................. 5 2 P1 ant Layout .......................................... 6 3 Finite Element Model of Facade Structure .............. 7 4 Deformed Shape of Facade Structure. Case 1 ........... 8 5 Deformed Shape of Facade Structure. Case 2 ........... 9 6- Deformed Shape of Facade Structure. Case 3 ........... 10 7 Deformed Shape of Facade Structure. Case 4 ........... 11 e
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s-y POINT BEACH REVIEW .
1.0 INTRODUCTION
'Several questions were raised regarding' the safety of. the Point Beach
. Nuclear Power Plant in Generic Lettr 81-14 " Seismic- Qualification of Auxiliary Feedwater System Point Beach Nuclear Plant, Units 1 and 2".-
Wisconsin Electric responsed to these; questions in a letter to NRC dated April 26,-1985.- This report describes the work perfonned by Brookhaven
. National Laboratory (BNL) to audit Wisconsin Electric's ' response to two of the questions. The first question dealt with the potential hazard of -
failure of the condensate storage tanks due to seismic loads. The second
. question concerns! the consequences of failure of the facade structure due
, to seismic loading. Neither of these . structures- are safety _ related. The
. concern.therefore is whether failure of these structures would cause damage to nearby safety related equipment. .
BNL first reviewed documents describing the concerns. An audit of the pertinent calculations was performed during a visit to the Wisconsin Electric offices on November 20, 1985. The plant was inspected at the same time. BNL staff participating in this visit were: C.J._ Costantino, C. A. !
Miller and A.J. Philippacopoulos. H. Polk of NRC was also on the audit team. Additional calculations were perfonned at BNL after the audit. The results for each of the concerns are discussed in the following two -
. sections of the report.
2.0 CONDENSATE STORAGE TANKS The concern was stated as follows:
"The licensee stated that each condensate storage tank with approximately 180 tons of water was mounted to the diesel generator building roof with 4 eight 3/4-inch diameter anchor bolts. Since these tanks are non-seismic,
- the consequence of these tanks breaking loose from their mounts and
, impacting the control building roof should be analyzed, including the
. effects of flooding".
The applicant responsded that the steel = and concrete structure surrounding the tanks precludes the possibility of their impacting the control room
'_ roof if they should fail during a seismic event. An inspection of the area :
{ during the site visit confirmed this.
l The second part of the concern is related to flooding of safety related
, areas or equipment if the tanks ruptured during a seismic event. The tanks >
, are mounted on the reinforced concrete roof of the diesel generator i building (see Fig. 1). Concrete walls surround three sides of the area in '
! which the tanks could be contained on the roof. The water would flow from i
the fourth side of the roof to Elev 8' and into a sump. The site inspec-
- tion confirmed that there is no safety related equipent located in areas which would be exposed to the water.
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~-
One area of concern, howeve. , is the air intake to the diesel generator building. Louvered air intakes to the diesel generator building are located on the roof of the diesel generator building close to the condensate tanks. The. louvers are mounted vertically into a concrete >
structure. There is adequate' freeboard below the louvers so that the water would not enter. However, it may be possible for the tanks to collapse.
onto the. louver structure so that water from a rupture higher up in the tank could spill into the louvers. A . failure in the tank could also result 1 in a stream of water directed at the louvers. The control panels for the diesel generators are located directly below the louvers and would be exposed to any water coming through the louvers. The applicant should be directed to consider the consequences of this event.
. 3.0 FACADE STRUCTURE The concern was stated as follows:
"In order for the design of the structures housing the AFWS to be acceptable, the licensee should demonstrate that all of these structures are capable of withstanding a safe shutdown experience".
One AFW pump steam supply line for each unit branches off a main ~ steam line at the containment structure exterior and is routed through the facade into the auxiliary building. The other steam supply line is routed from the facade through the north or south wing before entering the auxiliary.
building (see Fig. -2). The facade is not a Category I structure and the concern is whether failure of the facade during'a seismic event might cause failure of the safty.related steam lines.
The facade is a steel frame structure which encloses the containment. It is vertically supported on columns which are part of the facade structure with horizontal support provided by attachments to either the containment or the auxiliary building. Metal siding forms the skin of the facade ;
structure.
The facade structure was originally designed for a 360 mph wind loading assuming that one third of the siding remained intact. A study was performed to show that the SSE loading resulted in smaller shears than would occur for the design wind loading. The licensee therefore concluded that the structure could withstand the SSE loading. These calculations were reviewed during the audit and were judged to be acceptable.
. The facade structure is supported horizontally from both the containment and the auxiliary buildings. The licensee's analysis loaded the facade structure with inertial loadings consistent with the design response
, spectra, and then performed a static analysis. No consideration was given i to the stresses which could develop in the facade if the containment and i
auxiliary buildings moved out of phase during a seismic event.
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l BNL performed a study with the objective of establishing the consequences of such relative motion. A three dimensional model of the facade structure was developed for solution with the SAP V computer program. Beam and truss elements were used to model the structure. A sketch of the computer model is shown on Figure 3. The structure was then loaded by imposing the seismic displacements of the containment and auxiliary structure at the points of attachment to the facade. The displacements which were used are listed in.-Table 1 and were determined from the licensee's seismic analyses.
Table 1 SEISMIC DISPLACEMENT IMPOSED ON FACADE Structure Elevation Displacement (inches)
Containment 67 0.533 108 0.629 142 0.750 Auxiliary 85 0.27 108 0.54 Four computer solutions were found for the following cases:
Run 1 Only Containment Displacements Run 2 Only Auxiliary Displacements Run 3 Containment and Auxiliary Displacements in Phase Run 4 Containment and Auxiliary Displacements out of Phase o The deformation patterns for these four load cases are shown on Figures 4 through 7.
The resultant peak stresses in the bracing members are:
Run 1 10.0 ksi Run 2 17.3 ksi Run 3 17.3 ksi Run 4 17.3 ksi o
I
l The resultant . peak stresses in the beam members (beams and columns) are:
Run 1 4.0 ksi Run 2 7.4 ksi Run 3 7.4 ksi Run 4 7.4~ksi It is concluded that these stresses are sufficiently small so that the facade structure will not collapse during the SSE event and damage the piping.
4.0 CONCLUSION
'wo concerns regarding the potential of non Category I equipment failing
'aring an earthquake and damaging safety related equipment are investi-jated. The first investigation concerned failure of the condensate tanks.
It is concluded that failure of these tanks will not effect safety related equipment unless they fail in such a manner that water from the tanks will spill through the diesel exhaust structures onto the diesel control panels. It is recommended that the licensee be asked to address this issue.
The seismic response of the facade structure was investigated in detail.
It is concluded that the facade structure will not collapse during the SSE event and therefore presents no safeaty hazard to equipment located near the facade.
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