Letter Sequence Meeting |
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MONTHYEARML20236A0651975-10-15015 October 1975
Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days
Project stage: Other
ML20155J7791976-01-0505 January 1976
Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl
Project stage: Other
ML20148F2811976-06-0707 June 1976
Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads
Project stage: RAI
ML20244A6211978-01-25025 January 1978
Forwards Background & Current Status of Review of Asymmetric LOCA Loads for PWR Facilities & Revised Request for Addl Info on Subj
Project stage: RAI
ML19326B2771978-03-0909 March 1978
Responds to NRC .Plans Re Asymmetric LOCA Loads Safety Question Underway Since Oct 1975.Requests .Nrc Meeting W/B&W Owners Group in mid-March & Clarification of Requirements in NRC
Project stage: Meeting
ML19319D3951978-04-10010 April 1978
B&W 177FA Owners Group Asymmetric LOCA Loads Evaluations Programs
Project stage: Other
ML19319D3911978-05-0404 May 1978
Responds to NRC 780125 Request for Schedule for Evaluation of Asymmetric LOCA Loads.Forwards Rept, B&W 177FA Owners Group Asymmetric LOCA Loads Evaluation Program. Util Plans to Use Generic Analyses Where Applicable
Project stage: Request
ML19273A9921978-10-10010 October 1978
B&W 177 Fuel Assembly Owners Group Asymmetric LOCA Loads Evaluation Program,Phase 2. Evaluated Components Include Reactor Pressure Vessel,Fuel Assemblies,Control Rod Drives & Core Flooding Piping
Project stage: Other
ML19273A9831979-01-26026 January 1979
Submits Plan for Proceeding with Phase 2 Re Asymmetric LOCA Loads Program.Forwards Rept B&W 177 Fuel Assembly Owners Group Asymmetric LOCA Loads Evaluation Program,Phase 2 Identified Content & Schedule
Project stage: Other
ML19207A3941979-08-13013 August 1979
Informs of Multiphase Program to Evaluate Effects of Asymmetric LOCA Loads.Program to Be Completed Jul 1980
Project stage: Other
ML19296B2821980-02-15015 February 1980
Notifies Interim Rept BAW-1597, Effects of Asymmetric LOCA Loadings Responds to NRC 780125 Request.Rept Provides Justification for Continued Operation of Facility.Final Rept Will Be Forwarded by 800701
Project stage: Other
ML19320A8941980-07-0303 July 1980
Responds to NRC Requesting All PWR Licensees to Evaluate LOCA loads.BAW-1597 & BAW-1621 Submitted 800214 & 0701,respectively,demonstrate Ability of Facility to Maintain Core Coolability in Event of Asymmetric LOCA
Project stage: Other
ML19320A8651980-07-0303 July 1980
Notifies That Evaluation of BAW-1621,re Overall Asymmetric LOCA Loads,Will Be Submitted by 800805
Project stage: Other
ML19330C2781980-08-0505 August 1980
Advises of Review of BAW-1621, Effects of Asymmetric LOCA Loading - Phase II Analysis. Reactor Head Cable Access Platform Will Be Modified During Refueling Outage to Provide Horizontal Clearance at Svc Support Structure
Project stage: Other
ML15223A7081981-01-0909 January 1981
Forwards Request for Addl Info Re B&W 177-FA Owners Group Submittal on Asymmetric LOCA Loadings.Owners Group Should Convene Another Meeting W/Nrc After Review & Before Submittal.Info Due in 60 Days
Project stage: RAI
ML19347D1351981-02-26026 February 1981
Forwards 810109 Request for Addl Info Re B&W 177-FA Owners Groups Submittal on Asymmetric LOCA Loading.Response Should Be Submitted within 60 Days
Project stage: RAI
ML19347D3511981-03-11011 March 1981
Notifies That Util Will Provide Formal Response to NRC 810109 Request for Addl Info Re B&W 177-FA Owners Group Generic Submittal on Asymmetric LOCA Loadings by Jul 1981
Project stage: Request
ML20003E1581981-03-26026 March 1981
Responds to 810109 Request for Addl Info Re B&W 177-FA Owners Group.Requests Technical Review Meeting on 810402-03 in Bethesda,Md to Resolve Remaining Questions
Project stage: Meeting
ML16138A4971981-04-0909 April 1981
Summary of 810402-03 Meeting W/B&W Owners Group & Vendors in Bethesda,Md Re Proposed Responses to NRC 810109 Info Request Re Asymmetric LOCA Loadings
Project stage: Meeting
ML20031B3051981-09-24024 September 1981
Advises That Responses Submitted in Util Satisfy Questions Raised from Review of BAW-1621 Rept, Effects of Asymmetric LOCA Loadings-Phase II Analysis
Project stage: Other
2CAN018406, Comments on 830921 Draft Safeguards Agreement Under Npt Between USA & IAEA Subsidiary Arrangements, Intended to Be Implemented Through Facility License Amend.Markup Copy of Agreement Encl1984-01-23023 January 1984
Comments on 830921 Draft Safeguards Agreement Under Npt Between USA & IAEA Subsidiary Arrangements, Intended to Be Implemented Through Facility License Amend.Markup Copy of Agreement Encl
Project stage: Draft Other
ML20151J0531984-06-0606 June 1984
Forwards Request for Addl Info Re Asymmetric LOCA Loads. Addl Info Needed in Order to Complete Safety Evaluation of plant-specific LOCA Analysis.Response Requested by 840731
Project stage: Approval
ML20138H8951985-06-30030 June 1985
Rev 0 to Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept
Project stage: Other
ML20138H8761985-10-25025 October 1985
Forwards Rev 0 to 01-0300-1395, Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept
Project stage: Other
ML20210V1941986-09-25025 September 1986
Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation
Project stage: Other
ML20235Z7871986-10-15015 October 1986
Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty
Project stage: Other
ML20215N1621986-10-31031 October 1986
Forwards Rev 1 to Impell Corp 01-0300-1395, Leak-Before- Break Evaluation of Reactor Coolant Loop, Final Rept. Analysis Revised to Comply w/NUREG-1061,Vol 3
Project stage: Other
ML20215N1671986-10-31031 October 1986
Rev 1 to, Leak-Before-Break Evaluation of Reactor Coolant Loop
Project stage: Other
ML20236J8741987-08-0404 August 1987
Forwards Request for Addl Info Re Util Proposed Application of Leak Before Break Methodology to Eliminate Dynamic Effect of Postulated Primary Loop Pipe Ruptures from Design Basis, Per GDC-4.Response Requested within 30 Days of Ltr Receipt
Project stage: RAI
ML0311505101987-08-0404 August 1987
Withdrawn NRC Generic Letter 1987-014: Operator Licensing Examinations
Project stage: Request
ML20238B5121987-08-25025 August 1987
Responds to NRC 870804 Request for Addl Info Re Elimination of Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility.Addl Time Will Be Required to Evaluate & Adequately Address Each Item of Request
Project stage: Request
ML20236R7881987-11-20020 November 1987
Advises That Addl Info Requested in NRC Will Not Be Provided on 871231,per .Util Has Changed Contractors for leak-before-break Analysis in Order to Obtain Clarifications.Submittal Will Be Made by 880130
Project stage: Other
ML20148A5331988-03-0303 March 1988
Requests That Proprietary WCAP-11699 Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl
Project stage: Other
ML20148A5251988-03-14014 March 1988
Forwards Proprietary WCAP-11699 & Nonproprietary WCAP-11700, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Trojan Plant, leak-before-break Analysis Final Repts
Project stage: Other
ML20196L1891988-06-29029 June 1988
Advises That Proprietary WCAP-11699 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 880314 Request
Project stage: Other
ML20151T4041988-08-0505 August 1988
Forwards Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility,Per Util 851025 & 861031 leak-before-break Evaluations & WCAP-11699
Project stage: Approval
1981-03-26
[Table View] |
Summary of 810402-03 Meeting W/B&W Owners Group & Vendors in Bethesda,Md Re Proposed Responses to NRC 810109 Info Request Re Asymmetric LOCA Loadings| ML16138A497 |
| Person / Time |
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| Site: |
Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
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| Issue date: |
04/09/1981 |
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| From: |
Vissing G
Office of Nuclear Reactor Regulation |
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| To: |
Office of Nuclear Reactor Regulation |
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| References |
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| TAC-08602, TAC-08843, TAC-8602, TAC-8843, NUDOCS 8104200321 |
| Download: ML16138A497 (12) |
|
Text
05 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Dockets Nos. 50-269/27Ar/289/3O2/3l2/3l3 and 346 FACILITIES: Oconee 1, 2 and 3, Three Mile Island 1, Rancho Seco, Arkansas Nuclear One Unit 1, Davis-Besse 1, and Crystal River Unit 3 LICENSEES:
Babcock and Wilcox Reactor Owner Group -
Duke Power Company, Metropolitan Edison Company, Sacramento Municipal Utility District, Arkansas Power and Light Company, Toledo Edison Company-and Florida Power Corporation
SUBJECT:
SUMMARY
OF MEETING WITH THE B&W OWNERS GROUP CONCERNING PROPOSED RESPONSES TO NRC INFORMATION REQUEST OF JANUARY 9, 1981, REGARDING ASYMMETRIC LOCA LOADINGS Introduction By letter dated January 9, 1981, we requested from each B&W NSS owner addi tional information as a result of our review of the B&W 177-FA Owners Group submittal on "Effects of Asymmetric LOCA Loadings -
Phase II Analysis" - B&W 1597 dated February 1980 and B&W 1621 dated July 1980. Since there were a lot of questions and the responses would be quite complicated, we suggested that we convene a meeting with the Owners Group to discuss the responses before formal responses were submitted.
Such a meeting was held on April 2 and 3, 1981, at the NRC offices in Bethesda, Maryland.
The attendees are identi fied in Enclosure 1.
Discussion and Conclusions Each item of the request of January 9, 1981, was discussed on how it would be addressed in the formal response-by reference to documentation in the docket files, by detailed data and drawings and/or by background infor mation and explanation. provides a summary of the proposed method of responses.
The proposed responses were discussed for their acceptability; a clear under standing on what would be acceptable by the staff was provided; and there appeared to be a general acceptance as to what would be expected in the formal responses.
However, to assure that the formal responses would be complete and the issues be resolved to the fullest degree possible, the Owners Group requested another meeting with the staff after the staff would have an opportunity to review a draft of the responses.
APR 14 1981
The.0wners Group.committed to provide -theastaff a.draft of thezresponses by June 26, 1981.
A meeting of the.-staff and Owners Group to discuss-thesdraft responses was scheduled for 10:00 am July:16t9 1981, at the.NRC Offices-in.
Bethesda.
Guy Vissing, Proj ac nagere Operating Reactors B 7nch-!#4.
Division of Licensing Encl osures:
- 1. Listrof Attendees
- 2. Summary-of: Proposed.Methods of Responses cc-.w/enclosures:
Seelast page
ATTENDANCE LIST MEETING WITH B&W OWNERS GROUP CONCERNING ASYMMETRIC LOCA LOADINGS APRIL 2 & 3, 1981 Attendance 1NRC April 2 April 3 Guy S. Vissing X
X G. A. Schwenk X(Part time)
A. J. Cappucci X"
Jack Page X"
J. Rajan X
X E. Chelliah X
X Garry G. Young x
James Shea X(Part time)
EG&G Idaho Randy Lippert X
X
- 0. Mark Hanner, Jr.
X X
Richard Rah1 X
X EDS Nuclear Gerry Slagis X
X John Edinger X
X B&W Barry J. Short X
X W. C. Nester X
X Wm. D. Maxhem X
X D. L. Howell X
X GPU Nuclear Lou Lanese X
X
-2 Attendance April 2 April 3 FPC Joe Vattamattam X
X AP&L Larry D. Young X
TECo John K. Wood x
SMUD R. A. Dieterich x
DPC R. S..Bhatnagan X
NUS Corporation
.Mike Schoppman x
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MEETING
SUMMARY
DISTRIBUTION Licensee: Duke Power Company, Metropolitan Edison Company, Sacramento Municipal Utility District, Arkansas Power & Light Company, Toledo Edison Company
& Florida Power Corporation
- Copies also sent'to those people on service (cc) list for subject plant(s)..
Docket File-8 NRC PDR L PDR ORB#4 Rdg TNovak JStolz Project Manager -6 Licensing Assistant-2 OELD Heltemes, AEOD IE-3 SShowe (PWR) or CThayer (BWR), IE Meeting Summary File-ORB#4, RFraley, ACRS-10 Program Support Branch J01shinski BGrimes, DEP SSchwartz, DEP SRamos, EPDB FPagano, EPLB GSchwenk ACappucci JPage JRajan ECHelliah GYoung JShea