ML20196A886
| ML20196A886 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/20/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196A861 | List: |
| References | |
| NUDOCS 8806300139 | |
| Download: ML20196A886 (2) | |
Text
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,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.104 AND 91 TO FACILITY OPERATING LICENSE N0. NPF-4 AND NPF-7 VIPGINTA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERA _TIVE NORTH ANNA POWER STAT 10N UNITS NO. 1 AND NO. 2 2
DOCKET N05. 50-338 AND 50-339 INTRODUCTION By letter dated March 30, 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. I and No. 2 (NA-182).
The proposed changes would add in-core thermocouples in the Accident Monitoring instrumenta-i tion, TS Table 3.3-10 and 4.3-7.
Q_ISCUSSBN The proposed change to add in-core thermocouples to the NA-182 Accident Monitoring instrumentation, TS Tables 3.3-10 and 4.3-7 is in accordance with the requirements of NUREG-0737, item 11.F.2, "Instrumentation for Detection of Inadequate Core Cooling" and Generic letter 83-37, "NUREG-0737 Technical Specifications."
Generic letter No. 83-37, "NUREG-0737 Technical Specifications," requires that TS provide assurance that facility operation is maintained within acceptable limits for each facility in accordance with NUREG-0737.
The change would add in-core thermocouples tc TS Table 3.3-10, Accident Monitoring Instrumentation and require 4 thermocouples per core quadrant for operability determination while allowing 2 thermocouples per quadrant as the minimum number of operable channels for operation.
Also, the in-core thermocouples will be added to TS Table 4.3-7, Accident Monitoring Instrumentation Surveillance Require-ments, requiring a "Channel Cheex" on a monthly basis and a "Channel Calibration" each refueling.
These changes are in conformance with the sample provided in to Generic letter 83-37, pages 15 and 16.
EVALUMHN The proposed changes are in conformance with NUREG-0737 and Generic letter 83-37.
Therefore, based on all of the above, we find these changes to be acceptable.
8806300139 880620' PDR ADOCK 05000338 P
,.. 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 or 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 Commission has previously published a proposed finding that the arrendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendments meet the eligibil-ity criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9).
Pursuant to 10 CFR 551.22(b), no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of the amendments.
E9E$hE.I.9N 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 proposed manner, 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 or to the health and safety of the public.
Date:
Jur.e 20, 1988 Principal Contributor:
Leon Engle
.