Board Notification 82-93:forwards Addl Info Re Semiscale Test Results Concerning Feed & Bleed Mode of Core CoolingML20204F009 |
Person / Time |
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Site: |
Summer, Diablo Canyon, 05000000, Atlantic Nuclear Power Plant |
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Issue date: |
09/24/1982 |
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From: |
Eisenhut D Office of Nuclear Reactor Regulation |
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To: |
Ahearne, Asselstine, Gilinsky, Palladino N, Roberts NRC COMMISSION (OCM) |
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Shared Package |
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ML20204E909 |
List: |
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References |
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FOIA-88-99, TASK-AS, TASK-BN-82-93 BN--82-93, NUDOCS 8211040053 |
Download: ML20204F009 (1) |
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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 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 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 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 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 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 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 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 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 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 ML20155H8271998-11-0606 November 1998 Summarizes Sce&G Responses to Seven Items in Rept of Dam Safety Audit for Service Water Pond Dams at Virgil C Summer Nuclear Plant 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 ML20236K3111998-07-0101 July 1998 Notification of 980715 Meeting W/Util in Rockville,Md to Discuss Recent Licensed Operator Exam Process Problems & Positive Features 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 ML20197A7281998-02-19019 February 1998 Informs That Insp Rept from NRC Technical Assistance Contractor,Ferc Received & Evaluated.Insp Conducted on 970227.List of Seven Recommendations on Page 11 of FERC Rept Should Be Followed by Licensee.Dam Is Low Hazard ML20198T3161997-10-27027 October 1997 Discusses Review for Release of Records Re Differing Professional View from L Garner.Records Behind Tab a, Identified on Encl App,Should Be Placed in PDR ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20198T3701997-06-25025 June 1997 Responds to 970619 Memo Forwarding Recommendation of Dpv Panel & Requesting Plan & Schedule for Actions Re Salp.Plan Schedule Listed ML20198T3481997-06-24024 June 1997 Informs of No Objections to Dpv & Identity Being Publicly Disseminated ML20199B6781997-06-19019 June 1997 Accepts Panel Recommendations & Rationale for Recommendations Re Dpv Concerning Plant SALP ML20198T3841997-06-19019 June 1997 Accepts Panel Recommendations of Dpv Re Plant Salp. Recommendations Requested to Be Reviewed & Plan for Completing Action Including Schedule Requested to Be Provided ML20198T4181997-06-13013 June 1997 Summarizes Review Findings,Conclusions & Recommendations Re Plant Salp.Differing Professional View Encl ML20198T4251997-05-0808 May 1997 Informs That Recipients Have Been Selected to Serve on Panel to Review Differing Professional View.Purpose of Panel to Review Dpv & Make Recommendations for Resolution ML20198T5101997-04-29029 April 1997 Submits Three Potential Candidates for Differing Professional View on Plant SALP ML20198T4701997-04-25025 April 1997 Forwards Memo from Region II Re Documents in Disagreement W/Conclusions of Plant SALP Board.Recipient Requested to Chair Dpv Panel,Per Regional Ofc Instruction 2304,Rev 2,dtd 970131 & Provide Dpv Panel Recommendations by 970615 ML20198T4871997-04-17017 April 1997 Provides Another Perspective & Addl Background Info Re SALP Rating in Plant Support Area.Draft, Response to Comments on Plant SALP Rept Insp 50-395/96-99, Requested to Be Modified 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 ML20236M1171996-12-10010 December 1996 Responds to 960717 TIA 96-010 Requesting NRR Assistance in Evaluating Position Taken by Licensee for VC Summer Nuclear Station Re Interpretation of TS Definition of Core Alteration 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. 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[Table view] |
Text
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- {,J , :h %9 September 24,1982
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/ 1 Docket Nos. 50-275/323 and 50-395, 50-437 MDORANDUM FOR: Chairman Palladino commissioner Gilinsky cosmissioner Ahearne Commissioner Roberts Cornissioner Asselstine FRON: Darnell G. Eiserhut Director Division of Licensing, ONRR StBJECT: INFOR.MTION ITEM - RECENT INFORMATION WITH REGARD TO SEMISCALE TEST RESIA.TS (BN82-93)
Diablo Canyon Nuclear Power Piant, Units 1 & 2 Virgil C. Summer Station, Unit 1 '
Floating Nuclear Plants 1-8 ,
In accordance with present NRC procedures regarding Board Mtifications, the enclosed infonnation is being provided for your infbruation as constituting not infonnation relevant and material to safety issues.
This information is generic and may have applicability to all dockets with pressurized water reactors (PWRs).
The attached information describes recent tests in the Semiscale facility, a test facility approximately 1/1500th volume scaled to a typical Westinghouse 4 loop PWR. In the Semiscale tests, the "feed and bleed" code of core cooling was tested.
This infonnation is being provided as background since the staff does not l feel that sufficient infonnation is available to draw any conclusions from ;
the results. The staff is pursuing resolutions of the issue and will 1 transmit more information as it becoces available.
o ...a1 sisood tfs )
~ urr.11o.1.isenhuV 7 .~m .
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Darrell G. Eisenhut, Director 11o400:0 B20924 / ~
Division of Licensing t.,AnocK L Office of Nuclear Reactor Regulation
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