ML20212N338

Forwards Audit Plan for 870210-12 Safety Evaluation of SPDS in Lynchburg,Va

ML20212N338
Person / Time
Site:	Rancho Seco
Issue date:	01/14/1987
From:	Miner S Office of Nuclear Reactor Regulation
To:	Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
TAC-56525, NUDOCS 8701300399
Download: ML20212N338 (5)

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. Docket No. 50-312 January 14, 1987 Mr. John E. Ward

-Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station Post Office Box 15830 Mail Stop No. 291 Sacramento, California 95852-1830

SUBJECT:

AUDIT PLAN FOR THE EVALUATION OF RANCHO SECO'S SAFETY GRADE SAFETY PARAMETER DISPLAY SYSTEM (SPDS)

To assist you in preparino for our audit of the SPDS on February 10-12, 1987 at Babcock and Wilcox in Lynchburg, Virginia, we are enclosing our audit plan for the Safety Evaluation of the SPDS. If you have any questions on the audit plan, please contact me.

Sincerely,

/S/

Sydney Miner, Project Panager PWR Project Directorate #6 Division of PWR Licensing-B

Enclosures:

1. Amendment No. to DPR-54

2. Safety Evaluation cc w/ enclosures:

See next page DISTRIBUTION ACRS-10 Docket File BGrimes NRC & LPDRs JPartlow GKalman' SMiner RIngram PBD-6 files FMiraglia 0GC-Bethesda EJordan NThompson TUdo Ak/ //I PBD-6 P 6 PBj@ PBD#6 alman;eh er RWeller JStolz[U

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.....s h l? 9. - i r A Mr. John E. Ward Rancho Seco Nuclear Generating v Sacramento Municipal Utility District Station f.

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Y.' Mr. David S. Kaplan, Secretary Sacramento County J .and General Counsel Board of Supervisors ll- . Sacramento Municipal Utility 827 7th Street, Room 424 s"'

hx District 6201 S Street Sacramento, California 95814 q ?" P. 0. Box 15830 Ms. Helen Hubbard

, Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge y 2300 N Street, N.W.

Washington, D.C. 20037

..- Mr. Ron Columbo j- Sacramento Municipal Utility District

'" Rancho Seco Nuclear Generating Station 4440 Twin Cities Road Herald, California 95638-9799 N.. Mr. Robert B. Bo.rsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector / Rancho Seco c/o U. S. '- P.. C.

14410 Twin Cities Road Herald, California 95638 Regional Administrator, Reofon 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 k)

FNCLOSURE AUDIT PLAN FOR THE SAFETY EVALUATION OF PANCHO SEC0's SAFETY GRADE SAFETY PARAMETER DISPLAY SYSTEM l

1.0 OBJECTIVE The objective of the plan is to identify and document the scope, depth, ar)d' tasks for the subject audit. This audit plan will be forwarded to the licensee prior to the audit as an aid to prepare documents and schedule personnel to support the audit. This audit plan will also be forwarded to the staff's contractor as an aid to schedule personnel and prepare for the audit. The staff's goal in the audit is to collect and evaluate sufficient data to allow us to prepare a Safety Evaluation Report (SER) on the upgraded Safety Parameter Display System (SPDS).

2.0 BACKGROUND

By letter dated July 3,1986, Sacramento Municipal Utility District submitted for staff review an Action Plan for Performance Improvement at the Rancho Seco Nuclear Generating Station. The Action Plan was developed in response to the December 26, 1985 overcooling event at Rancho Seco.

The Action Plan cortained a task that identified an upgrade of the SPDS to safety grade status. The purpose of the upgrade was to meet some of the requirements contained in Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess An Accident." The staff's previous review of the SPDS was conducted on a basis of a non-safety grade system. The upgrade of the SPDS to a safety-grade system requires the staff to re-evaluate the system for conformance to safety grade requirements. -

During September 29 to October 2,1986, the staff conducted an audit at the Rancho Seco plant site. The scope of the audit was to collect and evaluate data on the licensee's Action Plan for Performance Improvement, the Detailed Control Room Design Review, and the upgrade of the Safety Parameter Display System (SPDS). Work on the upgrade of the SPDS was incomplete at the time of the audit. The licensee estimated that the upgrade of the SPDS would be complete for an audit by January 1987. This audit plan identifies the scope and depth of the review needed to complete the staff's evaluation of the upgraded SPDS.

3.0 AUDIT SCOPE In terms of audit scope, the staff plans to evaluate the methods used to design, test, verify and validate the upgraded SPDS. The staff's review will evaluate both hardware and software for the SPDS. Part of the evaluation was conducted during the staff's plant site audit of September 29, to October 2, 1986.

. a . -

The staff will utilize the guidance within Regulatory Guide 1.97,

" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess an Accident," to evaluate the SPDS. Also in the review of the software, the staff plans to utilize the guidance within Regulatory Guide 1.152,

" Criteria For Programmable Digital Computer System Software In Safety-Systems of Nuclear Power Plants," dated November 15, 1985 and in ANSI /

IEEE-ANS-7.4.3.2 -1982. Specific details on these audit tasks are identified in the enclosed agenda.

To support the audit, the licensee should have the following design documentation available for evaluation by the NRC Audit Team at the audit site:

1. Functional requirements.

2. Listing of software code.

3. Test plans and test procedures.

4. All products from the verification and validation activities.

5. Post installation test plans and test report.

4.0 AUDIT DATE AND SITE Based on recent conversations with the licensee, a tentative time for the audit was determined. The time selected was February 10-12, 1987 as the specific audit dates, with the exit briefing on the morning of February IP.

Based on the discussions with the licensee, the audit site is at the headquarters of the Babcock and Wilcox Company, located in Lynchburg, Virginia.

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TABLE I AUDIT AGENDA

1. NRC Audit Team Entry Briefing:

+ Identify scope of audit

+ Establish daily schedule for audit

2. On.an' overview basis, evaluate the design process, the design standards, and guidelines used in the development of the system.

3. On an overview basis, evaluate the design verification and validation plan and activities used in the design, development, and installation of the system.

4. EvaluTte the comparison of the development of the SPDS to the guidelines contained in Regulatory Guide (RG) 1.152, " Criteria for Programmable Digital Computer Software for Safety Related Systems of Nuclear Power Plants."

5. Conduct a walk-through of SPDS drawings of the hardware and software for two selected signals to the SPDS. Identify points in the walk-through where verification and validation activities occurred.

During the plant site audit of September 29 - October 2,1986, the staff requested the licensee to select one of the signals to be walked through.

The licensee selected containment building pressure as one of the signals.

With this audit plan, the staff identifies the second signal as T-cold, primary coolant loop.

6. Evaluate the results from validation test of the SPDS.

7. Evaluate the results from of the post-installation acceptance test of the SPDS.

8. Evaluate configuration control and the methods to be used for future design changes to the SPDS.

9. Evaluate review concerns on recent SPDS submittals by the licensee.

These submittals are:

a. Letter from J.E. Ward, Sacramento Municipal Utility District, to t

' F.J. Miraglia Jr., NRC,

Subject:

District Response to NRC Request for Information, dated November 20, 1986

b. SPDS Upgrade Sunnary Report, due to the NRC - December 31, 1986.

c. SPDS Updated Reliability Analysis, due to the NRC - December 31, 1986.

10. Exit briefino:

+ Preliminary observations and results from audit.

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