Letter Sequence RAI |
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MONTHYEARML20118B2831992-09-22022 September 1992 Responds to Suppl 1 to GL 87-02 Re SQUG Resolution of USI A-46.Util Commits to Utilize Methodology in Rev 2 to Generic Implementation Procedure for median-centered & Conservative Design in-structure Response Spectra Project stage: Other ML20127P1871992-11-20020 November 1992 Forwards Safety Evaluation Accepting Util Proposed Implementation Schedule to Use SQUG Commitments & Implementation Guidance Described in GIP-2 Project stage: Approval ML20097C8181996-01-31031 January 1996 Forwards USI A-46 Seismic Evaluation Rept for BVPS Unit 1 & USI A-46 Relay Evaluation Rept for BVPS Unit 1 for Resolution of USI A-46,in Response to GL 87-02 Project stage: Other ML20133G1641997-01-10010 January 1997 Forwards RAI Re NRC Review of Util plant-specific Summary Rept in Response to USI A-46 Program at Plant Project stage: RAI ML20141F2631997-05-16016 May 1997 Forwards Response to 970110 RAI Re Unresolved Safety Issue A-46 for Beaver Valley Unit 1.Calculations,also Encl Project stage: Other ML20216B2521998-03-0404 March 1998 Forwards RAI Re Summary Rept Concerning Verification of Seismic Adequacy of Mechanical & Electrical Equipment for Plant,Unit 1.Response Requested within 90 Days of Receipt of Ltr Project stage: RAI L-98-109, Forwards Response to NRC 980304 RAI Re USI A-46 for Unit 1. Schedule for Completion of Future Actions Described in Encl Is by Completion of Unit 1 13th Refueling Outage,As Indicated in Util to NRC1998-06-0202 June 1998 Forwards Response to NRC 980304 RAI Re USI A-46 for Unit 1. Schedule for Completion of Future Actions Described in Encl Is by Completion of Unit 1 13th Refueling Outage,As Indicated in Util to NRC Project stage: Other ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position Project stage: RAI ML20198A1301998-12-0909 December 1998 Forwards SE Re USI A-46 Program Implentation for Plant Unit 1.Staff Concludes Program Implementation Met Purpose & Intent of Criteria in Generic Implementation Procedure 2 & Suppl SER 2 for Resolution of USI A-46 Project stage: Approval 1997-05-16
[Table View] |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20206H3921999-05-0606 May 1999 Notification of 990518 Meeting with Util in Rockville,Md to Discuss Util Presentation of Technical Evaluation Performed in Support of License Amend Request Which Would Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20199J0641998-12-30030 December 1998 Notification of 990119 Meeting with Duquesne Light Co in Rockville,Md to Discuss Status of Licensing Actions/ Activities Currently Being Reviewed by NRC & of License Amend Requests Expected to Be Submitted in Near Future ML20198G9941998-12-22022 December 1998 Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor Operated Valves Program ML20196H1391998-12-0404 December 1998 Informs That Encl RAI Was Transmitted on 981204 to F Ferri of Dl.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20195G4501998-11-10010 November 1998 Rev 1 to Notification of Significant Licensee Meeting 98-87 with Util on 981116 to Discuss NRC Presentation of Osti Exit Followed by Util Presentation on Unit Restart Plant Performance ML20155K3451998-11-0505 November 1998 Notification of Significant Licensee Meeting 98-87 with Util on 981116 in Beaver Valley Power Station,Emergency Response Facility Conference Room A,For NRC Presentation of Osti Exit & Dl Presentation on Unit Restart Plan Performance ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154D4481998-10-0505 October 1998 Forwards Exam Rept with as Given Written Exam for Test Administered on 980817-21 at Unit 2,for Processing Through Nudocs & Distribution to NRC Staff ML20154D5611998-10-0505 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980817-21 ML20237B8081998-08-17017 August 1998 Forwards NRC Operator Licensing Exam Rept 50-334/98-300OL for Exam Administered on 980420-24 & 0518 ML20236X5981998-08-0404 August 1998 Notification of 980820 Meeting W/Util in Rockville,Md to Discuss Proposed Submittal of Improved Std TS ML20236K9051998-07-0101 July 1998 Notification of Significant Licensee Meeting 98-65 W/Util on 980716 to Discuss Plant Status & Preparations for Plant Restart IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples1998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20236N6351998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20247D1541998-05-0505 May 1998 Notification of 980519 Meeting W/Duquesne Light Co in Shippingport,Pennsylvania to Discuss NRC SALP of Beaver Valley Power Station for Period of 960929-980321 ML20248L6081998-03-0505 March 1998 Forwards Exam Rept W/As Given Written Exam for Test Administered on 971215-18 at Facility ML20248L6621998-03-0505 March 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility ML20212G4791997-10-28028 October 1997 Forwards SER Accepting Licensee 970213 Request Re Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20149G3261997-07-18018 July 1997 Notification of 970805 Meeting W/Util in North Bethesda,Md to Discuss Plans & Schedules for Resolution of 10CFR50.61 Updated Info for Pressurized Thermal Shock Evaluation ML20149D2891997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317 IR 05000334/19970031997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam Repts 50-334/97-03OL & 50-412/97-03OL (Including Completed & Graded Tests) for Tests Administered on 970317-21 & 970428- 0502 ML20149D2851997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317-21 ML20148E1881997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-60 W/Util on 970623 to Discuss Surveillance Test Program Apparent Violations ML20138Q1171997-02-27027 February 1997 Rev 1 to Notification of Significant Licensee Meeting 97-20 W/Util on 970307 in King of Prussia,Pa to Discuss Plant Configuration Control Issues Related to Component Mispositionings ML20135D1271997-02-20020 February 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970304 to Discuss Plant Configuration Control Issues Re Component Mispositionings ML20133D6221997-01-0202 January 1997 Rev 3 to Notification of Significant Licensee Meeting 96-128 W/Util in King of Prussia,Pa Re Predecisional EC to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20132E7361996-12-17017 December 1996 Notification of Significant Licensee Meeting 96-462 Rev 2 W/Util on 961230 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4601996-12-0606 December 1996 Notification of Significant Licensee Meeting W/Util on 961219 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4921996-12-0404 December 1996 Notification of 961219 Significant Licensee Meeting 128 W/Util in King of Prussia,Pa to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review1996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20141M6491996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20129E7161996-09-30030 September 1996 Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484 ML20059K7871994-01-0606 January 1994 Notification of Enforcement Conference 94-06 W/Util on 940118 to Discuss EDGs Solid State ATC Timer/Relays ML20059C3261993-12-28028 December 1993 Discusses Suggestion for More Efficient Use of NRC & Licensee Resources ML20058E4201993-11-26026 November 1993 Notification of Significant Licensee Meeting 93-157 W/Util on 931202 to Discuss AIT Exit Meeting ML20059K5501993-11-0808 November 1993 Notification of Significant Licensee Meeting 93-146 W/Util on 931115 in King of Prussia,Pa to Discuss Training Program Improvement Following Initial Exam Results from May 1993 ML20059K2711993-11-0303 November 1993 Discusses 931027 Operating Reactors Events Briefing Conducted to Inform Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931020. List of Attendees Encl ML20059H1381993-11-0202 November 1993 Notification of 931110 Meeting W/Util in Rockville,Md to Discuss Dlc Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059J4471993-11-0202 November 1993 Notification of Cancellation of 931110 Meeting W/Util in Rockville,Md to Discuss Util Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059G1271993-11-0202 November 1993 Notification of Significant Licensee Meeting 93-139 W/Util on 931119 in King of Prussia,Pa to Discuss Enforcement Conference Re Open Containment Penetration During Refueling ML20056G8161993-08-23023 August 1993 Notification of Significant Licensee Meeting 93-111 W/Util on 930902 to Discuss Plant Operator Training Program ML20202H7351993-07-22022 July 1993 Informs That Investigation Re Potential Wrongdoing Initiated by OI on 930223,under Case 1-93-008 Being Closed.Evaluation of Facts & Circumstances Surrounding Issues Indicate That No Underlying of Regulatory Requirements Exist ML20126F4161992-12-18018 December 1992 Notification of 930107 Meeting W/Util in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in Highhead Pressure Safety Injection Sys ML20128D2701992-11-25025 November 1992 Notification of 921210 Meeting W/Dl in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in High Pressure SIS ML20125C9761992-11-25025 November 1992 Notification of Canceled Meeting on 921210 in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in high-pressure Safety Injection Sys 1999-07-12
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20212F5401999-09-24024 September 1999 Staff Requirements Memo Re 990924 Affirmation Session Concerning SECY-99-236, Firstenergy Nuclear Operating Co, Local 29 Petition to Waive Time Limits in 10CFR2.1305 & Suppl Comments ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20206H3921999-05-0606 May 1999 Notification of 990518 Meeting with Util in Rockville,Md to Discuss Util Presentation of Technical Evaluation Performed in Support of License Amend Request Which Would Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20199J0641998-12-30030 December 1998 Notification of 990119 Meeting with Duquesne Light Co in Rockville,Md to Discuss Status of Licensing Actions/ Activities Currently Being Reviewed by NRC & of License Amend Requests Expected to Be Submitted in Near Future ML20198G9941998-12-22022 December 1998 Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor Operated Valves Program ML20196H1391998-12-0404 December 1998 Informs That Encl RAI Was Transmitted on 981204 to F Ferri of Dl.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20195G4501998-11-10010 November 1998 Rev 1 to Notification of Significant Licensee Meeting 98-87 with Util on 981116 to Discuss NRC Presentation of Osti Exit Followed by Util Presentation on Unit Restart Plant Performance ML20155K3451998-11-0505 November 1998 Notification of Significant Licensee Meeting 98-87 with Util on 981116 in Beaver Valley Power Station,Emergency Response Facility Conference Room A,For NRC Presentation of Osti Exit & Dl Presentation on Unit Restart Plan Performance ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154D5611998-10-0505 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980817-21 ML20154D4481998-10-0505 October 1998 Forwards Exam Rept with as Given Written Exam for Test Administered on 980817-21 at Unit 2,for Processing Through Nudocs & Distribution to NRC Staff ML20237B8081998-08-17017 August 1998 Forwards NRC Operator Licensing Exam Rept 50-334/98-300OL for Exam Administered on 980420-24 & 0518 ML20236X5981998-08-0404 August 1998 Notification of 980820 Meeting W/Util in Rockville,Md to Discuss Proposed Submittal of Improved Std TS ML20236K9051998-07-0101 July 1998 Notification of Significant Licensee Meeting 98-65 W/Util on 980716 to Discuss Plant Status & Preparations for Plant Restart ML20236N6351998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples1998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20247D1541998-05-0505 May 1998 Notification of 980519 Meeting W/Duquesne Light Co in Shippingport,Pennsylvania to Discuss NRC SALP of Beaver Valley Power Station for Period of 960929-980321 ML20248L6621998-03-0505 March 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility ML20248L6081998-03-0505 March 1998 Forwards Exam Rept W/As Given Written Exam for Test Administered on 971215-18 at Facility ML20212G4791997-10-28028 October 1997 Forwards SER Accepting Licensee 970213 Request Re Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20149G3261997-07-18018 July 1997 Notification of 970805 Meeting W/Util in North Bethesda,Md to Discuss Plans & Schedules for Resolution of 10CFR50.61 Updated Info for Pressurized Thermal Shock Evaluation ML20149D2851997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317-21 IR 05000334/19970031997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam Repts 50-334/97-03OL & 50-412/97-03OL (Including Completed & Graded Tests) for Tests Administered on 970317-21 & 970428- 0502 ML20149D2891997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317 ML20148E1881997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-60 W/Util on 970623 to Discuss Surveillance Test Program Apparent Violations ML20138Q1171997-02-27027 February 1997 Rev 1 to Notification of Significant Licensee Meeting 97-20 W/Util on 970307 in King of Prussia,Pa to Discuss Plant Configuration Control Issues Related to Component Mispositionings ML20135D1271997-02-20020 February 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970304 to Discuss Plant Configuration Control Issues Re Component Mispositionings ML20133D6221997-01-0202 January 1997 Rev 3 to Notification of Significant Licensee Meeting 96-128 W/Util in King of Prussia,Pa Re Predecisional EC to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20132E7361996-12-17017 December 1996 Notification of Significant Licensee Meeting 96-462 Rev 2 W/Util on 961230 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4601996-12-0606 December 1996 Notification of Significant Licensee Meeting W/Util on 961219 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4921996-12-0404 December 1996 Notification of 961219 Significant Licensee Meeting 128 W/Util in King of Prussia,Pa to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review1996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20141M6491996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20129E7161996-09-30030 September 1996 Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484 ML20059K7871994-01-0606 January 1994 Notification of Enforcement Conference 94-06 W/Util on 940118 to Discuss EDGs Solid State ATC Timer/Relays ML20059C3261993-12-28028 December 1993 Discusses Suggestion for More Efficient Use of NRC & Licensee Resources ML20058E4201993-11-26026 November 1993 Notification of Significant Licensee Meeting 93-157 W/Util on 931202 to Discuss AIT Exit Meeting ML20059K5501993-11-0808 November 1993 Notification of Significant Licensee Meeting 93-146 W/Util on 931115 in King of Prussia,Pa to Discuss Training Program Improvement Following Initial Exam Results from May 1993 ML20059K2711993-11-0303 November 1993 Discusses 931027 Operating Reactors Events Briefing Conducted to Inform Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931020. List of Attendees Encl ML20059H1381993-11-0202 November 1993 Notification of 931110 Meeting W/Util in Rockville,Md to Discuss Dlc Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059G1271993-11-0202 November 1993 Notification of Significant Licensee Meeting 93-139 W/Util on 931119 in King of Prussia,Pa to Discuss Enforcement Conference Re Open Containment Penetration During Refueling ML20059J4471993-11-0202 November 1993 Notification of Cancellation of 931110 Meeting W/Util in Rockville,Md to Discuss Util Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20056G8161993-08-23023 August 1993 Notification of Significant Licensee Meeting 93-111 W/Util on 930902 to Discuss Plant Operator Training Program ML20202H7351993-07-22022 July 1993 Informs That Investigation Re Potential Wrongdoing Initiated by OI on 930223,under Case 1-93-008 Being Closed.Evaluation of Facts & Circumstances Surrounding Issues Indicate That No Underlying of Regulatory Requirements Exist ML20126F4161992-12-18018 December 1992 Notification of 930107 Meeting W/Util in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in Highhead Pressure Safety Injection Sys ML20128D2701992-11-25025 November 1992 Notification of 921210 Meeting W/Dl in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in High Pressure SIS 1999-09-24
[Table view] |
Text
. . - . - - .. .- - - .
, October 16, 1998 i
l MEMORANDUM TO: Docket File FROM: Donald S. Brinkman, Senior Project Manager /s/
Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M69428)
The attached request for additional information (RAI) (Attachment 1) was transmitted by facsimile on October 2,1998, to Frank Ferri of Duquesne Light Company (DLC) for use in a telephone conference call on October 9,1998. DLC responded by fascimile on October 9,1998
(
(Attachment 2). The RAI and response were discussed in a conference call on October 9,1998.
This memorandum and the attachments do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-334 Attachments: As stated i
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% , , , p +# October 16, 1998 MEMORANDUM TO: Docket File FROM: Donald S. Brinkman, Senior Project anager l' .$A '& '
Project Directorate 1-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M69428)
The attached request for additional information (RAl) (Attachment 1) was transmitted by :
facsimile on October 2,1998, to Frank Ferri of Duquesne Light Company (DLC) for use in a telephone conference call on October 9,1998. DLC responded by fascimile on October 9,1998 (Attachment 2). The RAI and response were discussed in a conference call on October 9,1998.
This memorandum and the attachments do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-334 Attachments: As stated
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i ANSWERS NEEDED FOR CLOSING OUT A-46 ISSUE (SER)
- 1. On page 1 of your May 16.1997 response, you stated that "The tank wall analyses for SSEL vertical flat-bottom tanks (QU-TK1 and WT-TK-10) were performed as part of their overall GIP-2 evaluation." Please state your evaluation results. If the result is not satisfactory, have you modified the equipment?
- 2. On page 2 of your May 16,1997 response, you stated that "Our SQUG consultant, EQE inc., is analyzing the flat-bottom tank outliers. The anchorage outlier issues for other tanks are being resolved through more detailed modeling of the tank-support system..."
Please state your evaluation results. If the result is not satisfactory, have you modified the tank and anchorage?
- 3. On page 21 of your January 31,1996 submittal, you stated that "A total of 230 outliers were identified for BVP-1 SSEL equipment items." Have all the outliers been resolved?
If not, provide status for them.
- 4. On page 34 of your January 31,1996 submittal, you stated that "Seven (7) outliers were identified during the plant walk-downs and one (1) thru analysis." Have all the 7 outliers and the one thru analysis been resolved? How many were resolved by modification and how many were resolved by analysis?
! ATIACHMENT 1 1
- 10/,09/98 FRI 10:20 FAI 724 8434 1 DUQUEsNE LIGHT BVPs s&L @ 002 I
Response to NRC RAI Dated October 2,1998
' l l
- 1. Both of these tanks have been given further analysis by EQE, and found to have seismic capacities that exceed demands. We are presently reviewing their calculations, but expect them to form the basis of outlier resolution for these tanks.
1
- ' The GIP evaluation that was performed, is a sequential evaluation of the load i
transfer mechanisms at work in a vertical cylinder, flat-bottom tank undergoing '
l seismic acceleration.' For tank overturning assessment, it provides a series of reduction factors related to the various loaded structural elements, e.g., anchor i chair plates and welds, tank wall plate, that reduce anchor bolt stresses used to calculate the tank's overall resistance to overturning. The tank wall stresses are, therefore,just one of several factors that are used in the capacity determination.
l Both of the subject tanks failed to satisfy the conservative acceptance criteria of the GIP. For the WT-TK-10, Demineralized Water Storage Tank, capacity was !
controlled by bending in the top plate of the anchor chair; the tank wall stress did j
not govern. Of the wall compression stress determinations, elephant-foot buckling was controlling over diamond-shape, but not when compared to the chair top plate l bending. 'Ihc QS-TK-1, Refueling Water Storage Tank, capacity was also controlled by anchor chair limits, however, this tank is encircled by a reinforced concrete wall, which embeds the chairs. It was initially ignored as a conservatism, ;
but would effectively eliminate chair overstresses.
- 2. The refined model analyses were successful. As an example, the diesel air-start tank rack frame reanalysis included more realistic support conditions, response ;
frequency (12 Hz.), and SRSS load combination, which resulted in satisfactory.
anchorage loads. The Componem Cooling Water Heat Exchanger supports use embedded Nelson studs (40 on fixed-end; 26 on sliding end) that were more .
numerous than the GIP criteria considered (5 max.), therefore, they were outliers. ;
A detailed evaluation of the stud clusters using conventional methods showed the supports to be adequate.
- 3. The outlier count of 230 given in the Summary Report included those items on the SSEL that were shown in the report as outliers in Tables 5.3 (general equipment) and 6.2 (tanks & heat exchangers). A recount of those tables for this update, resulted in a total of 231 (206 general; 25 tanks & IIx). In addition, there were 7 cable tray outliers (Table 7.3) identified in the report, which includes one that was selected during a walkdown and later failed the GIP analysis. The separate Relay Summary Report (Table 2.1-1), identified 17 contactor outlicts requiring resolution, which included 9 relay types that were qualified to IEEE 344-71, but not found in the SQUG database, and 8 fire protection contactors that had no f seismic qualification.
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NMENT 2 l
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. 10/09/98
_FRI 10:21'FAI 724 6434671 DUQUESNE LIGHT BVPS S&L @ 003 The status of the various outliers is as follows:
General SSEL couinment (206)- 133 completed; 73 open. Of the 73 open,51 are dampers that were outliers because we chose not to use the SQUG Air Handler equipment class guidelines. Instead, a separate damper class was developed for SQUG by EQE, which has been applied along with a second walkdown of the dampers. An analysis is currently being prepared by EQE that will document their acceptability. The remaining 22 open outliers will generally require minor i physical modifications to remove potential interactions (rather than the use of i analysis), and review of existing calculations. Also included in the open outliers ;
are 3 AOVs for which operator manual actions are being reviewed to assure sufficient procedural guidance in the event air supply is lost, and 3 duct-mounted fans for which floor ARS do not exist.
Tanh & Heat Exchangers (25) - All 25 outliers have been resolved, although as identiFad in Item 1, EQE analyses arc still bemg reviewed by DLC. ;
Cable tray & Conduit (7) - 4 have been resolved; 2 by reinstallation of missing attachment clamps,1 by more accurately modeling floor connection details, and 1 by reviewing existing analysis to resolve an interaction issue. Of the remaining 3, analysis is being used for 2 (the nonsafety-related RCP power supplies, and rod-hung drain piping), and a minor modification may be required for the third (11 conduit support).
Contactors (17) 'All 8 fire protection system contactors have been resolved, almost exclusively through replacement with IEEE 344-75 qualified relays.
Review of previous modification documentation has resolved 1 of the 9 non-SQUG-qualified relays, while an EQE ' review of existing qualification t documentation (BVPS and industry) has provided a reasonable preliminary basis for concluding that the remaining 8 relays can be considered to be acceptable.
Such assessments.will be formalized before these relays are considered to be resolved. Additionally, we currently intend to replace the 2 General Electric HGA relays that were bad actors, but which had acceptable SQUG system affects, i
- 4. The response to this question can be found in Item 3.
BVPS commitment for complete resolution of all outliers remains the 13*
refueling outage, currently scheduled for Spring,2000. l l
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