Letter Sequence RAI |
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Results
Other: 05000312/LER-1986-011, :on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed, ML20137L915, ML20198K880, ML20198K899, ML20203E922, ML20204C493, ML20204E581, ML20206T869, ML20207Q604, ML20207R069, ML20210F539, ML20210G003, ML20210K842, ML20211M464, ML20211P598, ML20211P612, ML20212H039, ML20213F038, ML20213F695, ML20213G414, ML20215K603, NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy
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MONTHYEARML20137L9151986-01-20020 January 1986 Comments on 851028 Commission Policy Statement on Engineering Expertise on Shift,Per NUREG-0737,Item I.A.1.1 Re Shift Technical Advisor.Util Pleased W/Incorporation of Technical Advisor Position in Operating Staff Project stage: Other ML20198K8801986-05-30030 May 1986 Forwards Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station. Plan Provides Preliminary Results of Util Mgt Review of Implications of 851226 Overcooling Incident.Formal Plan Expected by 860703 Project stage: Other ML20198K8991986-06-0202 June 1986 Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station Project stage: Other ML20206H3941986-06-20020 June 1986 Summarizes NRC Concerns Expressed at 860610 Meeting Re Preliminary Version of Action Plan for Performance Improvement at Plant.Formal Plan Scheduled for Submittal on or About 860701 Should Resolve Listed Concerns Project stage: Meeting ML20203E9221986-06-30030 June 1986 Forwards Rev 4 to Updated FSAR for Prairie Island Nuclear Generating Plant.Two New Vols Provided for Reprinting of Apps of Original FSAR Project stage: Other ML20206T8691986-07-0303 July 1986 Forwards Action Plan for Performance Improvement. Plan Addresses 851226 Event & Includes Prioritization Process Which Identifies Actions That Will Be Completed Before Restart.Review Requested Project stage: Other ML20202G0431986-07-0303 July 1986 Discusses Systematic Assessment Program Portion of Performance Improvement Program,Per 860617 & 18 Discussions. Little Progress Made to Define & Implement Meaningful Sys Review & Test Program.Review of Program Suggested Project stage: Approval ML20204E5811986-07-17017 July 1986 Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program Project stage: Other ML20204E5741986-07-21021 July 1986 Forwards Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program, Per 860717 Meeting Request Project stage: Meeting 05000312/LER-1986-011, :on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed1986-07-23023 July 1986
- on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed
Project stage: Other ML20204C4931986-07-23023 July 1986 Responds to Retrospective Part of Issue 2a Re Completeness of Staff & Licensee Actions Associated W/Control Sys,Per Stello 860313 Memo to Denton in Response to Investigation of 851226 Incident.Issue 2a Closed Project stage: Other ML20212E9511986-07-29029 July 1986 Forwards General Comments on Util 860703 Action Plan for Performance Improvement.Prior to Scheduled 860814 Working Meeting W/Util,Staff Will Provide Addl Comments to Be Addressed in Meeting Agenda Project stage: Meeting ML20214N8311986-09-0505 September 1986 Forwards Request for Addl Info Re Util Action Plan for Performance Improvement & Preliminary List of Issues to Be Resolved in Electrical,Instrumentation & Control Portion of Proposed SER Project stage: RAI ML20210K8421986-09-12012 September 1986 Rev 1 to Design Basis Rept Project stage: Other ML20210G0031986-09-15015 September 1986 Forwards Amend 1 to Action Plan for Performance Improvement. Util Determined Installation of Emergency Feedwater Initiation & Control Sys Prior to Restart Feasible Project stage: Other ML20210G2431986-09-15015 September 1986 Forwards Audit Plan for Safety Evaluation of Facility Action Plan for Performance Improvement of Control Room Design & Spds.Audit Should Be Conducted in Early Oct to Preclude Impact on Proposed Restart Date Project stage: Approval NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy1986-09-26026 September 1986 Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy Project stage: Other ML20215K6031986-10-16016 October 1986 Submits Results of Survey on Engineering Expertise on Shift. Findings of Survey Include That Plants Utilize Shift Technical Advisors That Are on-call & That Differences from Commission Policy Statement Handled on case-specific Basis Project stage: Other ML20213F6951986-11-0606 November 1986 Forwards non-nuclear Instrumentation & Instrumentation & Control Sys Schematics & Piping & Instrument Drawings,In Response to NRC 860530 Request Project stage: Other ML20213F0381986-11-0707 November 1986 Advises of Revised Schedule for Completion of NUREG-0737, Item III.D.3.4 Re Control Room Habitability.Provisions to Complete Item III.D.3.4 Will Be Implemented Prior to Startup from Current Outage Anticipated in Early May 1987 Project stage: Other ML20211M4641986-12-0303 December 1986 Advises of Actions Taken in Response to Recent Burnout of Pressurizer Heater Bundle.Sessions Scheduled at Lynchburg Simulator During Feb 1987 to Polish Operator Skills & Awareness,Per Performance Improvement Action Plan Project stage: Other ML20211P5981986-12-15015 December 1986 Forwards Amend 2 to Action Plan for Performance Improvement. Amend Identifies Specific Actions Required for Accomplishment Prior to or During Restart Project stage: Other ML20211P6121986-12-31031 December 1986 Amend 2 to Action Plan for Performance Improvement Project stage: Other ML20212H0391987-01-12012 January 1987 Responds to Questions Discussed During 861216 Telcon Re SPDS & Main Feedwater (MFW) Indication in Control Room.Util Will Revise Action Plan,Section 4B.19 Re MFW Pump Trips Project stage: Other ML20207Q6041987-01-20020 January 1987 Advises of Future Plans to Take Reactor Out of Cold Shutdown & Proceed Through Heatup to Hot Shutdown Conditions,Based on Interpretation of 851226 Confirmatory Action Ltrs for pre-start Activities Project stage: Other ML20210F5391987-02-0303 February 1987 Confirms Telcon Re Arrangements for Evaluation of Requalification Program.Evaluation Visit Scheduled for Wk of 870504.Ref Matl Requirements for Program Evaluation & Requirements for Administration of Written Exams Encl Project stage: Other ML20213G4141987-02-26026 February 1987 Advises That All Steps Necessary to Ensure That Reorganizational Efforts Do Not Adversely Impact Restart Schedule Taken,Per 870205 Request Project stage: Other ML20207R0691987-03-0303 March 1987 Advises That Plans to Proceed W/Sys Testing Program & Precriticality Startup Program,Including Hot Shutdown, Consistent W/Confirmatory Action Ltrs for Prestartup Activities.W/O Rept Project stage: Other ML20214L0191987-05-13013 May 1987 Forwards Request for Addl Info on Section 3.2.4 of Facility Restart Rept Re Steam Generator Overfill & Flooding of Main Steam Headers to Complete Review Project stage: RAI NUREG-1286, Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues1987-10-0707 October 1987 Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues Project stage: Approval ML20055C2051988-02-12012 February 1988 Forwards Safety Evaluation Supporting Util 871223 & 880211 Submittals Re Proposed Amends to Tech Specs (PA 155,Rev 2) for Plant.Salp Input Also Encl Project stage: Approval 1986-07-23
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g-MAY 131987 Docket flo.: 50-312 Mr. J. Carl Andognini Chief Executive Officer, Nuclear Sacramento Municipal Utility District 6201 S. Street Post Office Box 15830 Sacramento, California 95852-1830
Dear Mr. Andognini:
SUBJECT:
RANCHO SEC0 RESTART REPORT - REQUEST FOR ADDITIONAL INFORMATION (TAC N0. 61635)
By letter dated December 15, 1906, SMUD submitted the Restart Report for the Rancho Seco Nuclear Generating Station. We have reviewed Section 3.2.4 (Steam Generator Overfill and Flooding of the Main Steam Headers) of the Restart Report and find that we need additional information to complete our review. Please respond to the enclosed request for additional information.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is rot required under P.L.96-511.
Sincerely,
/s /
George W. Knighton, Director Project Directorate V Divison of Reactor Projects - III/IV/V and Special Projects
Enclosure:
As stated DISTRIBUTION
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T. Marsh NRC PDR/L FDR M. Hartzman D. Crutchfield G. Kalman G. Holahan J. Lee /R. Weller OGC-Bethesda hp3
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Raw DRSP/PDV DRSR/j RWeller:cd GWKdibnton 5// 3 /87 5/g3 /87 0FFICIA;. RECORD COPY
Wm -
O Mr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer Nuclear Station Sacramento Municipal Utility District 4
cc:
Mr. David S. Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal Utility Federal Energy Regulatory Comission District 825 North Capitol Street, N. E.
6201 S Street Washington, D.C.
20426 P. O. Box 15830 Sacramento, California 95813 Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, D.C.
20037 Mr. John V. Vinguist Acting Manager, Nuclear Licensing Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 l
Resident Inspector / Rancho Seco c/o U. S. N. R. C.
14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Comission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Jo;rr..'i 9. Ward, Chief r<adiolo.%, Health Branch State Pe3a tment of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacramento County Board of Supervisors 827 7th Street, Room 424 Sacramentc. California 95814 Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586
Q'*
REQUEST FOR ADDITIONAL INFORMATION OTSG OVERFILL AND FLOODING OF THE MAIN STEAM LINES RANCHO SECO NUCLEAR GENERATING STATION MECHANICAL ENGINEERING BRANCH DIVISION OF ENGINEERING AND SYSTEM TECHNOLOGY 1.
Provide an evaluation and verification that the design limits for the supports of the steam generator, the "A" main steam line and the "A" main steam bypass line have not been exceeded due to overflow and the injection of the 13000 gallons of water.
2.
Provide the results of the detailed examination of the welds and piping of the bypass line currently being performed.
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