Letter Sequence Meeting |
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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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July 29, 1986 i
Docket No. 50-312 DISTRIBUTION Qocket File >
JPartlow NRC PDR RIngram L PDR SMiner Mr. John E. Ward PBD#6 Rdg RWeller Assistant General Manager, Nuclear FMiraglia Gray File Sacramento Municipal Utility District OGC, MNB 9604 NThompson 6201 S Street ACRS-10 HDenton P. O. Box 15830 EJordan JTaylor Sacramento, California 95813 BGrimes R:V
Dear Mr. Ward:
By letter dated July 3,1986, you forwarded the Sacramento fiunicipal Utility District (SMUD) Action Plan for Performance Improvement at the Rancho Seco l
Nuclear Generating Station. The NRC staff has performed a preliminary review l
of the SMUD Action Plan to assess the general adequacy, scope and content of the Plan. A preliminary version of your Action Plan was discussed at a meeting with you on June 12, 1986.
The Action Plan appears to be comprehensive and goes beyond the issues and deficiencies related to the December 26, 1985 overcooling transient. However, as your Plan preser.tly indicates, there are many elements or items in your program which are needed to provide an adequate basis for the staff's review.
l I
We will need a schedule for your submittal of the information as soon as possible to plan the staff's review and evaluation.
l The staff has met with SMUD several times since the December 26, 1985 l
overcooling event to discuss SMUD's proposed program for restart of Rancho Seco. During these meetings, and in related correspondence, the staff has provided guidance regarding the scope and content of your restart report and the issues which will require resolution in your corrective action progran.
Based on our preliminary review of the SMUD Action Plan, we are enclosing general comments which should be considered in the preparation of your supplement to the Action Plan. Most of these comments involve issues that were raised in our previous meetings. Specifically, the si comments from our June 12 meeting (sent to you on June 20,1986)gnificant regarding the lack of necessary details, discussion of restart items and longer term items, and the systems review and test program still need to be addressed.
Prior to the scheduled August 14, 1986 " working" meeting with your staff to discuss the detailed aspects of your plan, the staff will provide additional comments that should be addressed in your meeting agenda.
Sincerely, Oripalaleneng l
$$[1s$ SINb12 3%,
PDR Harold R. Denton, Director I
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Office of Nuclear Reactor Regulation
Enclosure:
As Stated y
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PBD#6 PBD-6 P
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Dh Hhmitan SMi RWeller;cf JS JTaylor p M FMi a 1 4 mer 7/t.3/86 7/486 7/13/86 7/aW86 7/g;f/86 7Q 6
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i Mr. John E. Ward Rancho Seco Nuclear Generating Sacramento Municipal Utility District Station cc:
Mr. David S. Kaplan, Secretary Sacramento County and General Counsel Board of Supervisors Sacramento Municipal Utility 027 7th Street, Room 424 District Sacramento, California 95814 6201 S Street P. O. Box 15830 Ms. Helen Hubbard Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
Washington, D.C.
20036 Mr. Ron Columbo Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 4440 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 Resident Inspector / Rancho Seco c/o U. S. N. R. C.
14410 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814
D Enclosure
S ON THE RANCHO SEC0 j
ACTION PLAN FOR PERFORMANCE IMPROVEMENT 1.
The action items to be implemented prior to completion of the restart test program or to the restart of the plant need to be described in detail. Similarly, insofar as practicable, actions in the near tem and long term require greater specificity.
Near term and long term should be defined in the time domain. The bases for categorizing actions as near term and long tern should be described.
2.
The plan is not clear with regard to schedt.les for completion of the various elements. Schedules for actions to be.taken prior to plant restart or prior to completion of the restart test program are not clearly defined (e.g., Appendix F). Where evaluations are to be performed to define corrective actions, schedules for performance and completion of the evaluation and implementation of any identified corrective actions should be provided. We recommend a separate section be included which deals with schedules and clearly indicates what actions will be complete and implemented by restart, the following refueling outage, and other future dates.
3.
The Action plan is deficient in that it fails to cross reference, in most instances, the elements of the program that address the NUREG-1195 findings as enumerated in Appendix B.
4.
There are many action items which are similar to areas in the B&W0G plan. A detailed interface requirement should be provided to discuss how the two programs are intertied.
5.
The action plan does not provide sufficient information regarding the review to be performed in the following areas:
a.
S.G. overfill protection system b.
Makeup /high pressure injection system c.
Remote and local indication d.
Containment isolction e.
Interaction between ICS, NNI and other safety related systems; and f.
Partial loss of ICS and NNI.
6.
The Action plan should include reevaluation of the transient and accident analyses assuming partial or full loss of the non-safety grade ICS and NNI systems used for event mitigation.
7.
It is not clear from the Rancho Seco Action Plan how the systems to be reviewed as part of the Systens Review and Test Program (SRTP) will be selected.
For example, will the tentative list of systems in Section 4D be submitted to the PAG for approval and then adjusted from the input received from the PP&MIP or will the initial selection of systens be
b o
-2 based on preliminary output from the PP&MIP? Clarification of the system selection process is required including how the output of the PP&MIP will be used in that process. We would also like clarification as to how the Rancho Seco SRTP is modeled after the Davis-Besse SRTP, and how the results of a review of the Davis-Besse SRTP will be factored into the Rancho Seco plan.
8.
It appears that contract personnel are playing a major role in assisting to implement the improvement program.
Please indicate the organization and personnel who will be responsible for Rancho Seco during startup, power testing, and subsequent power operation.
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