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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
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Text
gSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 s street, Box 15830, sacramento, California 95813; (916) 452-3211 July 3,1980 Director of Nuclear Reactor Regulation ATTN: Mr. Darrell G. Eisenhut, Director Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket 50-312 Rancho Seco Nuclear Generating Station, Unit 1
Dear Mr. Eisenhut:
A letter from Victor Stello, Jr. to all PWR Licensees dated January 25, 1978, requested an evaluation of asymetric loss of coolant accident loads. A status report of this evaluation, " Effects of Asym-metric LOCA Loading-Phase II Status", BAW-1597, dated February 1980 was submitted to you earlier this year by B&W in a letter from J. H. Taylor dated February 14, 1980.
We have recently reviewed the final Phase II report prepared by Babcock & Wilcox, " Effects of Asymetric LOCA Loadings-Phase II Analysis",
BAW-1621, July 1980, which was transmitted to you by J. H. Taylor in a letter dated July 1,1980. This report demonstrates the ability of Rancho Seco Unit 1 to maintain core coolability in the unlikely event of an asymmetric LOCA loading. We find the results and conclusions of this report to be applicable to Rancho Seco Unit 1 and consider it the final response to the January 25, 1978 request.
If we can provide any additional information, please advise.
Sincerely, ohn. Mattimoe Assistant General Manager and Chief Engineer DM s
/b 8007080 /IJg g
AN ELECTRIC SYS TE M S E RVIN G MORE THAN 600,000 IN THE HEART OF C All F O R N ! A