ML20133N414

Safety Evaluation Re Util 831107 & 850828 Responses to Generic Ltr 83-28,Items 3.1.2 & 3.2.1 & 850701 Request for Addl Info.Responses Re Vendor & Engineering Test Guidance & Testing Requirements After Maint Acceptable

ML20133N414
Person / Time
Site:	Brunswick
Issue date:	10/23/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133N410	List: ML20133N409 ML20133N414
References
GL-83-28, NUDOCS 8510290427
Download: ML20133N414 (3)

Text

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1. UNITED STATES

1. jog 8 o NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO GENERIC LETTER 83-28, ITEMS 3.1.2 AND 3.2.1 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET N05.'50-325 AND 50-324 1.0 Introduction Subsequent to two failures in the reactor trip system at Salem Nuclear Power Station in February 1983, the Nuclear Regulatory Commission (NRC)

GL issued Generic Letter (GL) 83-28 on July 8, 1983 to all licensees.

83-28 required licensees to develop and implement improved programs for post-trip review, classification of equipment, vendor interface, post-maintenance testing, and RTS reliability. The letter also stated that the licensee's programs would be reviewed by NRC and that a Safety Evaluation (SE) would be issued. The licensee, Carolina Power & Light Company (CP&L), for Brunswick Nuclear Plant responded to GL 83-28 on November 7, 1983.

The licensee's responses to Action Items 3.1.1, 3.1.2, 3.2.1, 3.2.2, 4.1 and 4.5.1 were evaluated for compliance to the NRC staff's positions as defined in GL 83-28. An Interim Safety Evaluation was transmitted to the licensee by NRC letter dated July 1,1985. The NRC letter also requested

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that the additional information on Action Items 3.1.2, 3.2.1, and 3.2.2 be submitted according to consnents in the letter dated November 7,1983.

The licensee submitted supplemental responses to Action Items 3.1.2 and 3.2.1 in Letter Nos. NLS-85-276 and 309 dated August 28, 1985. The licensee committed to submit a supplemental response to Item 3.2.2 in December 1985. We will review this response when received and will then I

issue a final SE for Action Item 3.2.2.

This SE presents the evaluation of the licensee's supplemental responses to our request for additional infonnation concerning post-maintenance testing.

. 2.0 Evaluation By letters dated August 28, 1985, CPat provided supplemental information on Action Items 3.1.1 and 3.1.2. We have evaluated the licensee's responses against our request for' additional information presented in the July 1, 1985, transmittal of the SE for the Brunswick Nuclear Plants, i

8510290427 851023 c PDR ADOCK 05000324 P PDR

Delineated below are the results of the NRC evaluation and a brief sumar of the licensee's supplemental responses:

A. Testing and Maintenance (Reactor Trip System The licensee comitted in its response dated November 7,1983, to review vendor and engineering recomendations other This review than was to General Electric (GE) Service Information Letters (SILs).

ensure that appropriate test guidance was inclu required. Also, the licensee stated that SILs be implemented during the next outage.

l The licensee's supplemental response (Letter NLS-85-276) dated Au 28, 1985, states that their final review has been completed and they did not identify any vendor or engineering recomendations concernin test guidance which have not been implemented in periodic tests, maintenance appropriate.

instructions, or Technical Specifications, asThe accomplish the above, a list of instrument inputs to Two engineering recomendations are presently any future vendor recomendations.the licensee's supplemental re of GL 83-28.

B. Item 3.2.1 - Review of Test and Maintenance Procedu Specifications (All Other Safety-Related Components)

The licensee comitted in its response of November 7,1983, to review procedures and Technical Specifications to verify This that testingtesting of safety-related components is required after maintenan safety function prior to being returned to service.

The licensee's supplemental response (Letter NLS-85-309) dated Au 28, 1985, stated that the above review has been completed and The licensee's review of procedures and Technical documented.

Specifications confirmed that their post-maintena Ba, sed on our safety function prior to being returned to service. revie 3.0 Conclusion The licensee's supplemental responses to GL 83-28 Action Items 3.

3.2.1 stated the following:

. Applicable vendor and engineering test guidance has been incorporated into test and maintenance procedures.

t Review of procedures and Technical Specificat will function prior to being returned to service their Based on review of the information 28, 1985, submitted by the licensee it:we co supplemental responses dated Augustlicensee's actions on GL and meet the intent of GL 83-28.

Principal Contributor: T. E. Conlon October 23, 1985 Dated:

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