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Category:BOARD NOTIFICATION (TO LICENSING BOARD OR LICENSING
MONTHYEARNUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants ML20136G3711985-11-21021 November 1985 Board Notification 85-091:submits Info Re Grand Gulf Tdi Emergency Diesel Generator Overspeed Condition on 851106. Probably Caused by Malfunction of Woodward Governor Mechanism.Damage Being Assessed & Evaluated ML20136G3661985-11-21021 November 1985 Board Notification 85-090:forwards Tdi 851106 Part 21 Rept Re Potential Problem W/Emergency Diesel Generator Engine Intake & Exhaust Valve Springs Furnished by Betts Springs Co.Issue Resolved IR 05000277/19850111985-07-22022 July 1985 Board Notification 85-070:forwards Enforcement Action Notification Resulting from Insp Repts 50-277/85-11 & 50-352/85-12 Re Radiation Protection at Peach Bottom & Security at Limerick IA-87-778, Board Notification 84-024:forwards SECY-84-34 Re Emergency Diesel Generators Mfg by Transamerica Delaval,Inc.Staff Continuing Overall Assessment of Reliability of Diesel Engines1984-02-15015 February 1984 Board Notification 84-024:forwards SECY-84-34 Re Emergency Diesel Generators Mfg by Transamerica Delaval,Inc.Staff Continuing Overall Assessment of Reliability of Diesel Engines ML20244C8141984-02-15015 February 1984 Board Notification 84-024:forwards SECY-84-34 Re Emergency Diesel Generators Mfg by Transamerica Delaval,Inc.Staff Continuing Overall Assessment of Reliability of Diesel Engines ML20215H9031983-10-27027 October 1983 Annotated Board Notification 83-164:forwards Allegations Re Certain Qa/Qc Activities.Source of Allegations Confidential. Related Documentation Encl ML20204G5401983-10-14014 October 1983 Board Notification 83-158:forwards Oct 1983 Sser 19 Re Matters Identified in Sser 18 & Listed in SECY-83-366,that Must Be Resolved Prior to Fuel Loading.Matters Adequately Resolved ML20151H4871983-05-0404 May 1983 Board Notification 83-057:forwards Differing Prof Opinions Re Sys Interaction & Safety Classification.Info Relates to Board Notifications 83-17 & 83-44 Re Unresolved Safety Issue A-17 ML20204F0461983-04-12012 April 1983 Board Notification 83-42:forwards Info Re Unanalyzed Reactor Vessel Thermal Stress During Cooldown.B&W Informed NRC of Preliminary Safety Concern Evolving from Further Consideration of 800610 St Lucie Upper Head Voiding Event ML20204F0361983-03-0404 March 1983 Board Notification 83-27:forwards 830221 Memo & Final Eg&G Rept Re Addl RELAP-5 Calculation for Semiscale S-SR-2 Test ML20244B9901983-01-0707 January 1983 Board Notification 83-03:notifies of Allegations Re Design Aspects of Component Cooling Water Sys Including Seismic Classification,Instrumentation & Control Design/ Classifications Approaches & Design of Generator Intakes ML20214K5091982-11-16016 November 1982 Board Notification 82-119:forwards Repts Re Design Verification Program - Phase I for Diablo Canyon Unit 1 ML20204F0161982-09-29029 September 1982 Board Notification 82-97:forwards Transcript of NRC 820909 Meeting W/State of CA Re Design Verification Program & Independent Design Verification Program:Auxiliary Bldg, Interim Technical Rept ML20204F0091982-09-24024 September 1982 Board Notification 82-93:forwards Addl Info Re Semiscale Test Results Concerning Feed & Bleed Mode of Core Cooling ML20214W7511982-08-19019 August 1982 Board Notification 82-89 Forwarding Transcript of NRC 820806 Meeting W/Util & Teledyne Engineering Svcs in Bethesda,Md Re Phase I of Facility Idvp.W/O Encl ML20213E2401982-08-12012 August 1982 Forwards Info Items Re Independent Design Verification program-Phase 1 (Idvp).Nrc Evaluating Info as Part of Ongoing Review of Idvp Efforts & Will Rept on Results Prior to Reinstatement of License.W/O Encl ML20062E1621982-07-20020 July 1982 Board Notification 82-70:notifies of Differing Prof Opinion Re Sensitization of BWR Stainless Steel Weldments ML20204E9541982-06-18018 June 1982 Board Notification 82-60:forwarding Info Re Design Verification Program from Teledyne Engineering Svcs,Rl Cloud Associates,Inc & Rf Reedy,Inc ML20054E9231982-06-10010 June 1982 Board Notification:Notifying of Drywell to Wetwell Vacuum Breakers Which Can Be Subj to air-clearing Load Resulting from Pool Swell Following Postulated Loca.Components Can Be Overstressed by Impact Load ML20204E9511982-06-0404 June 1982 Board Notification 82-57:forwarding Info Re Status of Independent Design Verification Program Activities Relevant to Safety Issue on Design Adequacy.Results Will Be Reported Prior to Reinstatement of License ML20204E9381982-06-0202 June 1982 Board Notification 82-53:forwarding Summary of 820430 Discussion of Bechtel Rate in Completion of Project.Info Relevant to Design Adequacy Safety Issue ML20209B3661982-04-26026 April 1982 Board Notification 82-42 Forwarding Items Re Design Verification Program,Phase I for Facility.W/O Encl ML20212L2111982-03-24024 March 1982 Board Notification 82-29:forwards Listed Documents Re Seismic Design Adequacy of Facility ML20212L1871982-03-15015 March 1982 Board Notification 82-24:forwards W Cooper Re Design Verification Program Manager for Facility.W/O Encl. Related Info Encl ML20204E9331982-01-27027 January 1982 Board Notification 82-06 Forwarding Design Verification Program for Power Ascension:Diablo Canyon Nuclear Power Plant Unit 1, & Qualification Document - Design Verification Program for Power Ascension ML20151H1791982-01-20020 January 1982 Board Notification 82-04 Forwarding Info Re Pressurized Thermal Shock ML20204E9051981-11-0505 November 1981 Forwarding Draft Board Notification 81-38, Seismic Reverification Program Presented During 811103 Meeting W/ PG&E Re Current Status of Review & Evaluation of Seismic Discrepancies in Facility Containment Annulus Area 1989-05-02
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20196D7021999-06-25025 June 1999 Informs That Reactor Sys Branch Prepared Suppl 1 to GL 83-11 Re Licensee Qualification for Performing Safety Analyses, Which Was Issued on 990624.Matl Related to Subj GL Should Be Placed in PDR & Made Available to Public DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20205J2811999-04-0606 April 1999 Notification of 990422 Meeting for Dockets 7200026 & 7200027 with PG&E in Rockville,Md to Dicuss PG&E Plans for Dry Cask Storage at Humboldt Bay & Diablo Canyon ML20205B2301999-03-25025 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990125-28 IR 05000275/19993011999-03-25025 March 1999 Forwards NRC Operator Licensing Exam Repts 50-275/99-301 & 50-323/99-301 for Tests Administered on 990125-28 ML20207M3401999-03-0202 March 1999 Notification of Canceled Meeting Scheduled for 990309 Re 7200026 & 7200027 for PG&E Plans for Dry Cask Storage at Humboldt Bay & Diablo Canyon ML20155H9051998-11-0303 November 1998 Notification of 981117 Meeting for Dockets 7200026 & 7200027 with Util in Rockville,Md to Discuss PG&E Plans for Dry Cask Storage ML20248K4451998-06-0202 June 1998 Notification of 980617 Meeting W/Util in Rockville,Md to Discuss PG&E Plans for Dry Cask Storage.Meeting Agenda Encl ML20247G9081998-04-0707 April 1998 Discusses Experts Needed for Plant Life Extension Cases,Per 980403 Discussion ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057A9941993-09-14014 September 1993 Forwards NRC Proposed Transcript Corrections ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20127P4161993-01-19019 January 1993 Provides Summary of 930113 Operators Reactors Events Briefing.List of Attendees & Viewgraphs of Elements Discussed Encl ML20126F0201992-12-16016 December 1992 Discusses Discrepancies in Svcs Rendered for 3rd & 4th Quarters of 1991 & 1st,2nd & 3rd Quarters of 1992.TLD Program for Humbolt Bay Site Did Not Strictly Follow Ltr of Contract ML20127D4321992-09-0101 September 1992 Forwards 920818 Petition Submitted by N Culver on Behalf of San Luis Obispo Mothers for Peace,Filed in Response to NRC Notice of Issuance of Amend to Licenses for Plant,Extending Expiration Date from 080423 to 210922 ML20058P5021990-08-15015 August 1990 Forwards Three Analyses of Shutdown Events Evaluated by Accident Sequence Precursor Program ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20247M1881989-05-26026 May 1989 Notification of 890613,14 & 15 Meetings W/Util in San Francisco,Ca to Discuss PRA Topics Re NRC Questions on long-term Seismic Program ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants 1999-08-27
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DISTRIBUTION See Attached JUN 41982 Docket No. 50-275 MEMDRANDUM FOR: Qiainnan Palladino comissioner G111nsky Comissioner Ahearne-
. ... Cossatssioner Roberts comissioner Asselstine FROM: Darn 11 G. Eisenhut Director Division of Licensing Office of Nuclear Reactor Regulation
SUBJECT:
INFORMATION ITEMS REGARDING THE DESIGN VERIFICATION PROGRAM -
PHASE 1 FOR DIABLO CANYON, UNIT 1 (BN 8247 )
In accordance with present NRC procedures for Board Notifications, the following is enclosed for infonnation of the Comission:
- 1. Teledyne Engineering Services, Independent Design Verification Program -
Fourteenth Semi-tnthly Status Report, transmitted by letter dated May 28,1982. ,
- 2. R. L. Cloud Associates Inc., Fourteenth Progress Report on Independent Denign Verification Pmgram, transmitted by letter dated May 26,1982. !
- 3. R. F. Reedy Inc., Semi-Monthly Report 14 on Quality Assurance Audit and Review, transmitted by letter dated May 28, 1982.
- 4. Teledyne Engineering Services, Designation and Potential Qualifications of Civil-Structural Consultant for IDVP, transmitted by letter dated May 28,1982. -
The information pn)vides the status of the Independent Design Verification Program (IDVP) activities for Diablo Canyon, Unit 1. The information is l relevant to the safety issue on the design adequacy of Diablo Canyon, Unit 1. 1 This is the stbject of Connission Order CLI-81-30 which is the basis for the I IDVP. The staff is evaluating the infonnation as part of its ongoing review of the IDVP efforts and will report on the results pr#0r to reinstatement of the license. The material does not pertain to those nat, ten that were resolved ;
tqy ALAB 644. .
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s20614o249 8206o4 Darrell G. Eisenhut. Director l l,j Division of Licensing ppg, ADocK osooo275,Y' Office of Nuclear Reactor Regulation /P yIL)
ClO ure's & cc: See next page *See Previous Condurrence for initials '
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> .} Y,..~ . ty.-- ( ( k g Docket No. 50-275 MEMORANDUM FOR: Chainnan Palladino Consnissioner Gilinsky Cocinissioner Ahearne Coninissioner Roberts Coom ssioner Asselstine FROM: Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
SUBJECT:
INFORMATION ITEMS REGARDING THE DESIGN VERIFICATION PROGRAM - PHASE 1 FOR DIABLO CANYON, UNIT 1 (BOARD NOTIFICATION NO. 82- )
In accordanca with hresent NRC procedures for Board Notification, the '
following is enclosed for infonnation of the Cocinission:
- 1. Teledyne Engineering Services, Independedt Design Verification Program -
Fourteenth Semi-Monthly Status Report, transmitted by letter dated May 28, 1982.
- 2. R. L. Cloud Associates Inc., Fourteenth Progress Report on Independent Design Verification Program, transmitted by letter dated May 26,1982.
- 3. R. F. Reedy Inc., Semi-Monthly Report 14 on Quality Assurance Audit and Review, transmitted by letter dated May 28, 1982.
- 4. Teledyne Engineering Services. Designation and Potential Qualifications of Civil-Structural Consultant for IDVP, transmitted by letter dated May 28, 1982.
The infonnation provides the status of the Independent Design Verification Program (lDVP) activities for Diablo Canyon Unit 1. The information is relevant to the safety issue on the design adequacy of Diablo Canyon Unit 1.
This is the subject of Comission Order CLI-81-30 which is the basis for the IDVP. The staff is evaluating the information as part of its ongoing review of the IDVP efforts and will report on the results prior to reinstatement of the Itcense. The material does not pertain to those matters that were re-solved by ALAB 644.
s Darrell G. Eisenhut Director Division of Licensing Office of Nuclear Reactor Regulation cc: See next page j ,
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Enclosures:
As stated cc: ASL8P ASLAP SECY OGC OPE Board Service List l
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