Letter Sequence Other |
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MONTHYEARML20062K2451982-08-10010 August 1982 Forwards Description of Plan for Upgrading Meteorological Sys Per Reg Guide 1.23 & NUREG-0654.Field Testing Program Scheduled for Aug/Sept 1982 Will Be Modified.Procedure Developed to Compensate for Uncertainties in 35-ft Sensors Project stage: Other ML20023B3571983-04-15015 April 1983 Forwards Response to Generic Ltr 82-33, Suppl 1 to NUREG-0737,Requirements for Emergency Response Capability. Safety Parameter Display Sys Will Operate from Emergency Response Facilities Computer Sys.W/One Oversize Drawing Project stage: Request ML20073M2231983-04-15015 April 1983 Forwards Response to 821217 Generic Ltr 82-33 Re Schedule for Addressing Each Element of Emergency Response Capability.Schedule Developed Following Guidelines Contained in Suppl 1 to NUREG-0737 Project stage: Other ML20154J3951983-05-0303 May 1983 Discusses Negotiations Re Util 830415 Response to Generic Ltr 82-33.Licensee Proposed Implementation Dates,Summarized in Encl,Acceptable.Record of 820806 Telcon Encl Project stage: Other ML20078D5831983-09-27027 September 1983 Forwards Program Plan for Implementation of Control Room Design Review of Beaver Valley Power Station, Following Guidelines in Suppl 1 to NUREG-0737,per Generic Ltr 82-33 Project stage: Other ML20083E9701983-12-21021 December 1983 Advises That Atmospheric Radioactive Effluent Release Assessment Sys Will Be Operable by End of Fourth Refueling Outage Commencing Oct 1984,per 830415 Response to Generic Ltr 82-33 & NUREG-0737,Item III.A.2.2 Project stage: Other ML20087L4571984-03-14014 March 1984 Provides Followup to 840228 Telcon Re Suppl 1 to NUREG-0737, Development of Emergency Operating Procedures, from Generic Westinghouse Emergency Response Guidelines. Development Will Continue as Described Project stage: Other ML20084H5191984-04-30030 April 1984 Provides Approx Starting Dates & Summaries of Each Review Phase of Control Room Design Review,In Response to NRC .Summary Rept Expected to Be Submitted in Nov 1985 Project stage: Other ML20091H9491984-05-30030 May 1984 Requests Rev to Procedures Generation Package Submittal Date to 840701 Due to Need for Addl Review of Revised Package Incorporating Addl Concerns Re Emergency Operating Procedure Task Analysis,Per Suppl 1 to NUREG-0737 Project stage: Other ML20092N5791984-06-28028 June 1984 Forwards Procedures Generation Package Re Methods for Developing & Implementing function-oriented Emergency Operating Procedures,Per Generic Ltr 82-33 Project stage: Other ML20198D2521986-05-0909 May 1986 Forwards Responses to Items 1 Through 3 from Generic Ltr 86-04, Policy Statement on Engineering Expertise on Shift. Util Currently Utilizes Dedicated Shift Technical Advisor (STA) at Unit 1 & Plans to Use STA at Unit 2 Project stage: Request ML20206H4931986-06-19019 June 1986 Safety Evaluation on Generic Ltr 83-28,Item 4.2.3 & 4.2.4, Preventive Maint Program for Reactor Trip Breakers/Life Testing. Licensee Position Unacceptable Project stage: Request ML20206G2351986-09-30030 September 1986 Rev 4 to ASME Code Baseline Document Project stage: Request ML20214C9841986-11-0303 November 1986 Provides Required Info & Describes Compensatory Measures Presently in Place to Ensure Easy Access Between Control Room & Emergency Response Facility Project stage: Other ML20214J6501987-05-12012 May 1987 Responds to NRC Re Interim Review Results on Abnormal Transient Guidelines Procedures Generation Package for Facility.Response Refs Util 870408 Submittal Re Unit 2 SER Confirmatory Item 47 Procedures Generation Package Project stage: Other ML20235T2491989-02-21021 February 1989 Advises That Action Plan Schedule for Corrective Action Re Deviations Identified in Insp Rept 50-334/88-02 Revised. Tasks for Emergency Operating Procedures Will Be Completed by May 1989 Project stage: Other 1984-05-30
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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 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 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 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
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UNITECFSTATES
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!' p, _ NUCLEAR REGULATORY COMMISSION g ; j wAssiscrow. o.c. rosss mar 0 3 1983 - -
~-
MEMORANDUM FOR: Steven A. Varga, Chief
. Operating Reactors Branch #1, OL FROM: 6 Project Manager --
Operating Reactors Branch fl. DL ,
SUBJECT:
NEGOTIATIONS WITH'THE LICENSEE ON HIS RESPONSE TO 1
GENERIC LETTER 82 BEAVER VALLEY UNIT 1 The licensee (Duquesne Light Company) provided his response to Generic Letter 82-33 on April 15, 1983. Subsequent to that, I have provided - ' '
ORRf 5 (W. Paulson) with 'a copy of his letter and a summarf sheet.
._ On_May 2,1933, L had_a meeting at _the si_te_with the licensee's repre .__ _ __
sentatives (K. Grada and S. Sovick) and the NRC Resident Inspector W.
Troskosky. I was provided with background material and justifications l for the licensees April .15,1983 response. I consider the licensee's proposed implenentation dates, as stated in his April 15, 1983 letter, .,
and as justified in the May 2 meeting, reasonable logical and based on his overall projected events for the next few years. Therefore, tinless I have been dir6cted otherwise, I consider all the proposed implementation f dates, summarized in the enclosure, acceptable. The Resident Inspector had no opposition to any proposed date.
/
lb ,
Peter S. Tam, Project Manager Operating Reactors Branch #1 Division of Licensing cc: W. Paulson ,
G. Dick .
J. Lyons J. Shea W. Troskoski, Resident Inspector .
at Beaver Valley l
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RECORD OF TELEPHONE CONVERSATION BEAVER VALLEY UNIT I Da te: August 6,1982 "
Time: 2:00 p.m.
Participants:
S. Sovick (DLC) '
T. Vassello (DLC)
P. Lk ng (SAI)
R. Liner (SAI) -
P. Ta ( .j ,
C / [L -
Background
SA!, contractor to flRC on NUREG-0737 items I.A.2.1 and II.B.4, prepared a draf t TER on these issues. The TER identified a number of open items to be resolved. Pages from the draf t TER have been telecopied to DLC and the .
purpose of the conference call was to see how these may be resolved.
Discussion and Agreemcnts' RE: P. 9, paragraph that reads "The .9eaver Valley training program appears to . . . . . . . . . . .does not believe. . . . . . . . training program meets thi s requirement..."
DLC stated that IE Inspection Report 81-29 (12/28/81) should clarify and close this item. P. Tam agreed to provide copy of the report to SAI.
RE: P. 9, Item A.2.e '
DLC indicated that non-licensed: instructors teach basic courses such as rathematics, physics, etc., they do not get involved in subjects such as plant operation. They therefore do not need to go through a reoualification program.
RE: P.10 Item C,1 DLC pointed out that flRC does not have a document 'that gives the "80 hours core damage training" requirceent, Furthermore, it really depends on how hours are added up.
P. Tam will follow up<g~f withit$0. !! igg {inton to clarify this.*
- Follow up calls were made on August 9,19 ihvolving S. Sovick, K. Grada, D. Wigginton and P. Tam. Nigginton exp ined that the "80 hours" requirement is considered by NRC to be the :S 'd..T. ' for core damage nitigation training. INPO has recomended 120-140 hours for the same training. It is, nevertheless, possible to count some hours in topics such as heat transfer, DNS, steam tables, etc. as hours in core damage mitigation training.
S. Sovick requested to know what other utilities h:v: claimed credit fdr.
Wigginton informed him that reviews-of Ginna and Zion are most near completion.
Sovick will contact these utilities.
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l l RE: P.10. Item C.3 Requalification Program. See Item C.1 above.
RE: P.ll, Iten II.B.4 See Item C.1 above. DLC indicated IE Inspection _ Reports 81-18 and 82-05 -
should shed light on this. Copies will be provided SAI by P. Tam.
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;) NUCl(EAR'RE2ULATCRY COMMISSION wasumavow,0.c. rosss
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)DocketNo.50-334> 2S M MEMORANDUM FOR:
Darrell G. Eisenhut, Director, Division of Licensing, NRR ,. /
TilRU: d Steven A. Varga, Chief, Operating Reactors Branch No. 1, DL l' Gus C. Lainas, Assistant Director for Operating Reactors, f4 -
Division of Licensing FROM: _f aDProject Manager, Operating Reactors Branch No.1, DL I
SUBJECT:
BEdVERVALLEYUNIT1-NEGOTIATIONSWITHTHELICE NUREG-0737 ITEMS Per direction provided in your July 12 and June 1,1983 memoranda, I have documented the reasons for accepting the late implementation dates for the following items:
Safety Parameter Display System (SPDS) - G. Dick, LPM Guidance provided states that "Without further negotiation, operability dates
,m through December 31, 1985, are pcceptable." The SPDS will be fully installed during 5/85 the 4th refueling outago, tentatively scheduled to occur from 2/85 to (V1 However, operators will not~ be trained by then; training will be done on the SPDS, and is scheduled to be completed during the 5th refueling outige, tentatively scheduled to occur in July 1986.
Since 'bperability" is defined as including completion of staff training, the licensee's proposed " operability" date would exceed the guidance provided. I discussed with the lead PM (June 15,1983) the date exceeds the guideline, it is reasonable and is thus acceptable.and he a Emergency Operating Procedures - J. Lyons, Lead PM Guidance provided states that "Without further negotiations, implementation of upgraded, human-factored, function-oriented E0Ps through December 31, 1985, are acceptable." The licensee has proposed to implement the new E0Ps after the 5th refueling cutage, since the next one, the 4th, would be too soon for him.
The 5th one is tentatively scheduled to occur in July 1986.
Since it is reasoiable to implement new procedures at the beginning of a fuel cycle rather tha's at the middle, and since the proposed implementation date is
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~ less than 1 year beyond the guidelide," FEon' sider the licensee's date reasonable. I. discussed with the Lead PM (June 15, 1983) and he agreed that the proposed date is acceptable,,
Reg. Guide 1. 97 - J. Shea , Lead PM The licensee has committed to provide a report on his evaluation of R.G.1.97 instrumentation in November 1985. The evaluation of such instrumentation is plan. It isconcurrently perfonned with CRDR, according to the licensee's integrated reasonable to believe that complete implenentation of R.G.1.97 (defined by the licensee to include installation of equipment and staff trained) will not happen until some time after December 1985.
Complete implementation of this R.G. is contingent upon procurement, receipt and installation of a large number of pieces of equipment. Prior to all these, the licensee has to test, analyze and identify equipment to be replaced / upgraded.
Thus the above date is a reasonable one and should be considered acceptable.
M eter S. Tam, Project Manager
. Operatfrig Reactors Branch No.1 Division of Licansing u
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