ML20137T942
| ML20137T942 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/20/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137T902 | List: |
| References | |
| GL-84-13, NUDOCS 8512090165 | |
| Download: ML20137T942 (2) | |
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f UNITED STATES k
O NUCLEAR REGULATORY COMMISSION h
,j WASHINGTON, D. C. 20555 e
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 71 AND 57 TO FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION. UNITS NO. 1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339 INTRODUCTION:
By letter dated September 19, 1985 (Serial No.85-645), the Virginia Electric and Power Company ()the licensee) requested an amendment to the Technical Specifications (TS for the North Anna Power Station, Units No. I and No. 2 (NA-182). Specifically, the amendments would revise TS Sections 3/4.7.10 and 6.10.2 in accordance with the guidance provided in NRC Generic Letter 84-13
" Technical Specifications For Snubbers," dated May 3,1984.
DISCUSSION:
The proposed changes would add a statement to TS 3.7.10 specifying which snubbers shall be operable and delete Tables 3.7-4a and 3.7-4b.
This change would remove the requirement to update the TS when a snubber is added or deleted from NA-182. This is in accordance with NRC Generic Letter 84-13 dated May 3,1984 entitled " Technical Specifications For Snubbers." Generic Letter 84-13 recommends that Tables 3.7-4a and 3.7-4b be eliminated from the TS. Generic Letter 84-13 also reconenends that the TS be modified to specify which snubbers are required to be operable. This revision includes a statement specifying "All snubbers utilized on safety related systems shall be OPERABLE. For those snubbers utilized on non-safety related systems, each snubber shall be OPERABLE if a failure of that snubber or the failure of the non-safety related system would have an adverse effect on any safety related system." A list of snubbers will still be maintained as part of the plant records as required by TS 4.9.7.f.
TS 4.9.7.f requires "a record of the service life of each snubber, the date at which the designated service life conenenced and the installation and maintenance records on which the designated service life is based shall be maintained." The addition or deletion of a snubber will be documented in the plant records. These two changes are in accordance with the recomendations of Generic Letter 84-13.
Also references to Tables 3.7-4a and 3.7-4b have been deleted from the TS.
The proposed change would also add a statement to surveillance requirement 4.7.10.a regarding the early inspection of snubbers.
Early inspections can be used to set a new reference inspection date. However, the results of such 0512090165 051120 DR ADOCK 050 8
early inspections cannot be used to increase the inspection interval. This i
statement is present in the bases section of the TS and is being added to the surveillance requirements for clarification purposes. This statement is also consistent with the reconnendation of Generic Letter 84-13.
for additional functional testing of snubbers (should it be required)ple size In section 4.7.10.c, the expression that is used to determine the sam has been modified to be in accordance with Generic Letter 84-13.
The exemptions from functional testing for large snubbers greater than 50 kips for NA-182 during the Cycle 3 and Cycle 1 refueling outages, L
respectively, have been deleted since these outages have been completed.
l EVALUATION:
The proposed changes are in conformance with the NRC Generic Letter 84-13, j
and are, therefore acceptable. In addition, removing the exemptions for i
functional testing of snubbers greater than 50 kips for specified refueling l
outages already completed is an administrative change which provides l
consistency to the NA-182 TS with respect to timeliness, and is therefore acceptable.
ENVIRONMENTAL CONSIDERATIONS l
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 l
and changes in surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant i
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 Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public connent on such finding. Accordingly, these amendments l
meet the eligibility criteria for categorical exclusion set forth in 10 CFR t
51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement i
or environmental assessment need be prepared in connection with the issuance
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of the amendments.
CONCLUSION We have 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 operation in the promsed manner, and (2) such activities will be conducted in compliance witi the Consission's regulations, and the issuance of these amendments will not be inimical to the common t
defense and security or to the health and safety of the public.
Principal Contributor:
L. Engle Dated:
Novenber 20, 1985 l
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