ML20154N707

Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Test Program for safety-related Components

ML20154N707
Person / Time
Site:	Waterford
Issue date:	09/22/1988
From:	NRC
To:
Shared Package
ML20154N705	List: ML20154N703 ML20154N707
References
GL-83-28, NUDOCS 8809290382
Download: ML20154N707 (2)

Text

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[puyk g p, NUCLEAR REGULATORY COMMISSION UNITED STATES ij WASHINGTON, D. C. 20665

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SAFETY EVALUATION FOR POST MAINTENANCE TESTING GENERIC LETTER 83-28 ITEMS 3.1.1, 3.1.2, 3.2.1 AND 3.2.2 ALL SAFETY-RELATED COMPONENTS WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382

1. INTRODUCTION -

On February 22, 1983, both of the reactor trip circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open when an automatic trip signal was generated due to a steam generator low-low level condition.

This incident occurred during plant startup and the reactor was tripped manually by the operator almost coincidentally with the automatic trip.

Shortly thereaf ter on February 25, 1983, during plant startup, both reactor trip circuit breakers again failed to open upon an automatic reactor trip signal from the reactor protection system. In this incident the reactor was manually tripped by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit break.ers to open has been detennined to be related to the sticking of the under voltage. trip device.

Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in i NUREG-1000. "Generic Implications of ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Comission requested (by Generic Letter 83-i8 dated July 8, 1983) all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to certain generic concerns. These concerns were categorized into four areas: (1) Post-Trip Review, (2) b EquipmentClassificationandVendorInterface,(3) Post-Maintenance pg Testing, and (4) Reactor Trip System (RTS) Reliability Improvements.

> mo 08 The third action item, Post-Maintenance Testing, consists of Action 8o Items 3.1 and 3.2. This safety evaluation report (SER) addresses Action me Items 3.1 and 3.2, "Post-Maintenance Testing (All Safety-Related 7 Components)."

o3 Y II. REVIEW GUIDELINES This evaluation of the utility response was conducted using NRR review

(' guidelines provided by memorandum dated February 11, 1985, from Mr. Frank J. Miraglia, Acting Director Division of Licensing, NRR to Mr. Richard P. Denise. Director of Reactor Safety and Projects, Region IV and other Regional Division Directors. The review guidelines state:

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a. The licensee should submit a statement indicating that has reviewed plant test and maintenance procedures and Technical Specifications to assure that post-maintenance operability testing of all safety-related components is required,

b. The licensee's statement should contain a verification that vendor recomended test guidance has been reviewed, evaluated, and where appropriate, included in the test and maintenance procedures or the Technical Specifications,

c. An unembiguous comitment should be obtained from each licensee that post-maintenance testing will verify component capability to perfom all safety functions.

III. EVALUATION AND CONCLUSION By letters dated March 5, 1984 November 15, 1985, and January 15, 1986, the licensee provided infomation regarding post-maintenance testing of safety-related components. During a telephone call on August 30, 1988, Mr. R. Produs, Licensing Engineer, provided additional infomation, which enhanced statements made in the submittal.

Post-maintenance operability testing demonstrates that equipment is capable of perfoming its safety functions and ensures operability prior to being returned to service. The licensee indicated it has conducted a review of test procedures, maintenance procedures, and Technical Specifications. As a result of this review, the licensee indicated that it has determined that post-main-tenance operability testing of all safety-related components is being conducted as required. In addition, the licensee indicated that it has verified that this post-maintenance operability testing is sufficient to assure that safety-related components are properly returned to service.

The licensee's administrative procedures prescribe e.n ongoing review program. This program ensures that any appropriate vendor or engineering

j. recomendations that could affect post-maintenance operability testing

' are incorporated into maintenance and test procedures or the Technical Specificatinns.

Based on our review, we conclude that post-maintenance testing of all safety-related components at Waterford Steam Electric Station, Unit 3 meets the review guidelines and is acceptable.

Principal NRC Contributor: G. A. Pick l Dated: September 22, 1988