ML20206D601

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Safety Evaluation Supporting Amends 106 & 92 to Licenses NPF-4 & NPF-7,respectively
ML20206D601
Person / Time
Site: North Anna  
Issue date: 11/10/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206D599 List:
References
NUDOCS 8811170147
Download: ML20206D601 (3)


Text

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B WASHINGTON, D. C. 20005 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEfitMEllT NOS.106 AND 92 TO FACILITY OPERATING LICENSE NO. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION, UNITS N0. 1 AND NO. 2 DOCKET fl05. 50-338 AND 50-339 INTRODUCTION By letter dated Septenter 20, 1988, as supplemented October 6, 1988, the Virginia Electric and Power Company (the licensee) requested a change to the Technical Specifications (TS) for the North Anna Power Station, Units No. 1 and flo. 2 (NA-1&2).

Specifically, the change would modify the NA-1&2 TS to permit conducting the third Type A test of the first 10-year inservice inspection (ISI) during the 1989 refueling /10-year ISI outage.

DISCUSSION Because the NA-1&2 TS currently requires a Type A test to be conducted at a 40 + 10-month frequency, the third Type A test would be due on or before November 11,1988 for NA-1 and on or before December 14, 1988 for NA-2.

The TS also specify that the "third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection." The NA-1 outage is currently scheduled to begin in April 1989 and the NA-2 outage is currently scheduled to begin in February 1989.

Appendix J III.D. requires that a set of three Type A tests be performed "at approximately equal intervals during each 10-year service period. The third test of each set shall be conducted when the plant is shutdown for the 10-year plant inservice inspections."

The NA-1&2 TS are much more specific and require that Type-A tests be "conducted at 40 + 10 month intervals during shutdown at Pa [ greater than or equal to) l 40.6 psig during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection."

As noted above, the 10-year plant ISI are currently scheduled for February 1989 for Unit 2 and April 1989 for Unit 1.

Type A tests shall be conducted during these outages such that the requirements of Appendix J and a portion of the l

requirerents of the TS will be met.

3811170147 881110 PDR ADOCK 05000338 P

PDC

i Since the 10-year plant inservice inspection outages are outside the 40 +

10 month TS interval requirement, the licensee has requested an amendmenE to the NA-182 TS.

No exemption is needed from Appendix J since postponing the test until the 1989 refueling outage still satisfies the requirewent that the test be conducted at "approximately equal in+.ervals" and the tests wili be conducted during the 10-year inservice inspection outage as required.

The second interval overall integrated leakage rate test for NA-1 was completed on September 11, 1984 The test demonstrated that the containment leakage rate was 43% of the maximum allowable leakage rate permitted by the NA-1 TS.

In addition, the test took into account leakage from individual valves and penetra-tions.

Subsequent testing of these valves and penetrations has demonstrated no degradation.

The second interval overall integrated leakage rate test for NA-2 was completed on October 14, 1984 The test demonstrated that the containment leakage rate was 92% of the maximum allowable leakage rate permitted by the NA-2 TS.

In addition, the test took into account leakage from individual valves and penetra-tions. Subsequent testing of these valves and penetrations has demonstrated no degradation.

EVALUATION The proposed extension of the surveillance interval does not involve a significant reduction in the margin of safety and will not result in a significant increase in the probability er consequences of a design basis accident previously evaluated.

In addition, the proposed extension of the surveillance interval does not impact the design basis of the containment and does not modify the response of the containment during a design basis accident. The 1984 Type A test results indicate that the containment integrity is adequate.

In addition, leakage from containment penetrations and valves, including air locks, is measured in accordance with NA-1&2 TS 3/4.6.1.2 and 3/4.6.1.3 whenever changes or activities occur (e.g., valve maintenance or modification, containment entries) which may affect leakage rate. Thus, the combined leakage of penetrations subject to Types B l

and C tests will continue to be maintained within the TS limits. Therefore, based on all of the above, the staff finds the proposed extension of the surveil-lance interval for Type A testing to be conducted during the NA-1821989 refueling /10-year ISI outages to be acceptable.

ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to surveillance requirements. The staff has determined that the amend-ments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Comission has previously published a proposed finding that the amendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(9).

Pursuant to 10 CFR 151.22(b), no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of the amendments.

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CONCLUSION We hayw concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operattun in the proposed menner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendments will not be inimical to the common defense and security ur to the health and safety of the public.

Data:

November 10, 1988 j

Priticipal Contributor:

L. Engle i

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