ML20127C243
ML20127C243 | |
Person / Time | |
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Site: | Beaver Valley, 05000000 |
Issue date: | 11/01/1984 |
From: | Sheron B Office of Nuclear Reactor Regulation |
To: | Knighton G Office of Nuclear Reactor Regulation |
Shared Package | |
ML20126J910 | List: |
References | |
FOIA-84-926 NUDOCS 8411120125 | |
Download: ML20127C243 (2) | |
Similar Documents at Beaver Valley, 05000000 | |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
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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 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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 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 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 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 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 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 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 1999-09-24 |
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NOV 011984 MEMORANDUM FOR: George Knighton, Chief Licensing Branch #3 Division of Licensing FROM: Brian W. Sheron, Chief Reactor Systems Branch .
Division of Systems Integration
SUBJECT:
BEAVER VALLEY UNIT 2 OPERATING LICENSE REVI.EW .
Plant Name: Beaver Valley Unit 2 Docket No.: 50-412 Licensing Stage: OL Responsible Branch: Licensing Branch #3 Project Manager: B. Singh -
Review Branch: Reactor Systems Branch ~
Review Status: Awaiting Information '
, The information requested in enclosure 1 is needed to close Open Item'161.
Original signed by:
Brian W. Sheron, Chief Reactor Systems Branch Division of Systems Integration
Enclosure:
As stated cc: R. W. Houston RSB Section Leaders B. Singh %
CONTACT: E. Lantz, RSB x27839
( DISTRIBUTION Docket File RSB R/F q RSB P/F: Beaver Valley U ELantz R/F BSheron
/ LMarsh Elantz d FFICIAL RECORD COPY f DSI:RSB # 05 . R DSfdSB .
Elgrtiz: gd LMarsh BShe on 11/f/84 11/[ /84 11/ /84
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ENCLOSURE 1 BEAVER VALLEY-2 OPERATING LICENSE REQUEST FOR ADDITIONAL INFORMATION 440.21 In its' August 10, 1984, response to SER Open Item $161, regarding
~' '
the reliability of a residual heat removal system that meets GDC-34, the Duquesne Light Company stated:
"In the event the system is unavailable, the safety grade
~
systems discussed in FSAR Section 5.4.7.4.6 are qualified to .
perform the function of removing residual heat from the reactor core for normal, abnormal, and design base accident conditions."
However, there is no Section 5.4.7.4.6 in the FSAR. '
This response also states:
" Class IE safety-related equipment associated with the ECCS, AFWS, and S/G PORV's are identified in Table 3.11-1."
However, Table 3.11-1 has been removed from the FSAR (Amendment 8). Thus this response is not acceptable.
To be acceptable, clear descriptions of the shutdown and long term coolihg methods that conform to GDC-34 are needed in the FSAR and also confirmation that all of the components used in these methods are environmentally qualified.
.