ML20037D077
| ML20037D077 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/15/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037D076 | List: |
| References | |
| NUDOCS 8105210405 | |
| Download: ML20037D077 (3) | |
Text
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g UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C. 20555 O,*** /
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.29 AND NO.10 TO FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNITS NO. 1 AND NO.2 DOCKET NOS. 50-338 AND 50-339
==
Introduction:==
By letters dated May 13, 1981 (Serial No. 305) and May 15,1981(Serial No. 307), the Virginia Electric and Power Ccmpany (the licensee) requested changes in the Technical Specifications for Facility Operattag Licenses NPF-4 and NPF-7 for the North Anna Power Station, Units No.1 and 2 (NA-1&2).
The changes involve the removal of facility snubbers based on the ongoing NRC required multi-structure Amplified Response Spectra (ARS) reanalysis for NA-1&2. The ARS reanalysis has required, in some cases, the removal of plant specific snubbers listed in Table 3.7-4 of the NA-l&2 Technical Specifications.
Discussion and Evaluation:
1.
NA-l&2 Snubber 571 Based on the ARS reanalysis, thc licensee determined that snubber 571 should be removed. Upon further review, the licensee determined that snubber 571 was not only listed in Table 3.7-4 of the NA-2 Technical Specifications but also listed in Table 3.7-4 of the NA-1 Technical Specifications.
By letter dated May 13, 1981, the licensee requested that snubber 571 be removed from the NA-l&2 Technical Specifications. Our letter, dated May 14, 1981 authorized the licensee to delete snubber 571 from Table 3.7-4 of the NA-l&2 Technical Specifications.
As determined in the ongoing ARS reanalysis, the removal of snubber 571 does not decrease the margin of safety in that removal of.this snubber along with other support modifications will provide improved support of the piping system for applicable loads to be expected during a seismic event or during accident conditions.
Based on the above, we find acceptable the removal of snubber 571 from Table 3.7-4 of the NA-l&2 Technical Specifications. Also, for the reasons 810591n Y#
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- as stated above, this evaluation documents our authorization by letter dated May 14, 1980, permitting removal of snubber 571 from Table 3.7-4 of the NA-l&2 Technical Specifications.
2.
NA-1 Snubbers 403, 404. 409. and 410 Based on the NA-1 ARS reanalysis, the licensee has determined that snubbers 403, 404, 409, and 410 related to the Component Cooling Water System located in the station auxiliary building at location CC-244-Pent be replaced by.
new snubbers 411, at location CC-255-Pent and.412, at location CC-252-Pent.
This requires the deletion of snubbers 403, 404, 409, and 410 from Table 3.7-4 of the NA-1 Technical Specifications.. The licensee has stated that a future amendment request will add snubbers-411 and 412 to Table.3.7-4 of the NA-1 Technical Specifications upon completion of installation.
The removal of snubbers 403, 404, 409, and _410 and installation of snubbers 411 and 412 will provide greater support for the system piping for applicable loads to be expected during a seismic event or during accident conditions.
These modifications do not decrease the margin of safety and on this basis we find the changes acceptable.
3.
NA-2 Snubbers 401 and 402
~
Based on the ongoing NA-2 ARS reanalysis, the licensee has determined that-snubbers 401 and 402 at location CC-244-ABB be removed due to modifications to two rigid supports and addition of another snubber. This requires the i
deletion of snubbers 401 and 402 from Table 3.7-4 of the NA-2 Technical Specifications. The licensee has stated that a future amendment will add snubbers to Table 3.7-4 of the NA-2 Technical specifications following installation.
The deletion of these snubbers does not decrease the margin of safety in that the deletion of these snubbers.along with other modifications to the l
piping supports, will provide improved support for the piping systems for loads to be expected during a seismic or accident event. Therefore, we find these change to be acceptable.
l Environmental Consideration We have determined that the amendments do not authorize a change in l
effluent types or total amounts nor an increase in power level and l
will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Sl.5(d)(4), that an environmental impact statement or negative declaration and environ-mental inpact appraisal need not be prepared in connection with the l
issuance of these amendments.
l L
' Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability ce consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be ccnducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the cormion defense and security or to the health and safety of the public.
Date: May 15, 1981 i
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