ML20196B808

Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements

ML20196B808
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	12/02/1988
From:	NRC
To:
Shared Package
ML20196B806	List: ML20196B801 ML20196B808
References
GL-83-28, NUDOCS 8812070038
Download: ML20196B808 (3)

Text

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ENCLOSURE 1 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST-MAIN NANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)

ZION NUCLEAR POWER STATION DOCKET NOS. 50-295/304

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1.0 INTRODUCTION

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SUMMARY

Generic Letter 83-28 describes intermediate term actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit 1 of the Salem Nuclear Power Plant.

This report is an evaluation of the responses submitted by Comonwealth Edison Company, the licensee for the Zion Nuclear Power Station for Items 3.1.3 and 3.2.3 of the Generic Letter. The actual documents reviewed as parc of this evaluation are listed in the references at the end of this report.

The requirerents for these two items are identical with the exception that Item 3.1.3 applies these requirements to the Reactor Trip System components and Item 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both items were evaluated together.

2.0 REQUIREMENT Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety. Appropriate changes to these test requiremnts, with supporting justification, shall be submitted for staff approval.

G812070038 881202 PDR ADOCK 05000295 P PDC

. 3.0 EVALUATION The licensee for the Zion Nuclear Power Station responded to these requirements with submittals dated November 5,1983, August 22, 1988 and a verbal comitment made during a telephone conference call on October 31, 1988. The licensee's initial response was found unacceptable for both items and a request for additional information was issued on March 23, 1987 which clarified the issues.

The licensee's second response was acceptable for the reactor trip system components but did not address all other safety-1 elated components. The licensee's verbal response of October 31, 1988 addressed the issue by stating that no post-maintenance test requirements for safety-related components other than RTS components were found in the Technical Specifications which would degrade safety. The licensee committed in this verbal response to provide written confimation of their verbal statement. In this respect, the licensee had ideni.1fied only the testing of the diesel generators under the Zion Confimatory Order of February 29, 1980 as degrading safety. However, the testing required under this order is surveillance testing which is outside the

- scope of G.L. 83-28 Item 3.2.3.

4.0 CONCl.USION Based on the licensee's statements that no post-maintenance test requirements were found in the Technical Specifications which would degrade safety and the exclusion of the Zion Confirmatory Order testing, we find the licensee's responses acceptable for Items 3.1.3 and 3.2.3 of Generic Letter 83-28.

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5.0 REFERENCES

e 1. NRC Letter, D.G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, "Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 63-28)", July 8,1983.

2. Conmonwealth Edison Letter to NRC, P.L. Barnes to H.R. Denton, Director, Office of Nuclear Reactor Regulation, November 5,1983.

. 3. Commonwealth Edison Letter to NRC, c,L. Tryzna to Director, Office of Nuclear Reactor Regula ), August 22, 1988.

4., Commonwealth Edison Letter to NR1, G.L. Tryzna to Director, Office of Nuclear Reactor Regulation, October 1988 Major Contributor: D. Lasher

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storage of SNM contaminated waste in DOT authorized shipping containers. Further, the areas delineated in paragraph 1.4.5 have also been designated for this purpose, as well as the drum warehouse of the Plutonium facility.

1.4.8 Automated Reactor Inspection System (ARIS)

The ARIS is a computerized manipulator used to perform ultrasonic testing of reactor vessel welds. The equipment will be maintained and stored in the Fab 9 area of the Plutonium Facility, the Metals and Hafnium Complex, and the facility at the Mt. Vernon site when not in use. When not being stored or undergoing maintenance, the ARIS may be used at nuclear power reactor sites anywhere in the United States where the U.S. Nuclear Regulatory Commission retains jurisdiction for regulatit.7 the use of licensed materials.

1.4.9 Eddy Current Eauioment IECE)

The Eddy Current Equipment (ECE) is a computerized, electro-me::hanical manipulator used to perform eddy current testing of steam generators. The equipment will be maintained, tested, and stored in an area of the Plutonium Plant designated as the Nuclear Services Operations (NSO) area.

Thia area is within and adjacent to the Drum Warehouse area.

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