ML20195C817
| ML20195C817 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/19/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20195C806 | List: |
| References | |
| NUDOCS 8605300613 | |
| Download: ML20195C817 (2) | |
Text
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o UNITED STATES g
g NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NIJCLEAR REACTOR REGULATION i
RELATED T0' AMENDMENT NOS. 79 AND 68 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 N0. 2 DOCKET NOS. 50-338 AND 50-339
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Introduction:==
By letter dated August 6,1985, the Virginia Electric and Power Company (the licensee) proposed changes to the Technical Specifications (TS) for the North Anna Power Station Unit Nos.1 and 2 (NA-142). Specifically, the proposed change would eliminate redundancy in requirements as presently stated in TS 6.5.3.1.
Discussion:
The proposed changes would eliminate the NA-1&P TS 6.5.3.(n) which is redundant to several other requirements listed in TS 6.5.3.1.
TS 6.5.3.1 specifies various audits which the Quality Assurance (QA) Department is required to maintain on NA-182 station activities.
Presentl
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of TS 6.5.3.1 are TS 6.5.3.1.(1) and 6.5.3.1 (m)y included within the scope which require the QA Department to audit the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) (including implementing procedures) at least every 24 months. Also, TS 6.5.3.1(n) specifies an audit of activities required by Regulatory Guide 1.21, Revision 1, June 1974, and Regulatory Guide 4.1, Revision 1, April 1975, at least once per 12 months.
Provisions contained in Regulatory Guide 1.21 (Revision 1-June 1974) and Regulatory Guide 4.1 (Revision I-April 1975) were used by the licensee in developing the ODCM and PCP. Copies of the ODCM and PCP were included in the licensee's submittal for the NA-1&? Radiological Effluent Technical Specifications (RETS) and were found to be acceptable by the NRC. Changes to these documents require approval of the NA-1&2 Station Nuclear Safety and Operating Committee (SNSOCl and submittal to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which any change was made.
The implementing procedure for the ODCM and the PCP contain OA Program requirements as specified in the licensee's Nuclear Power Station QA Program.
The ODCM and PCP and associated implementing procedures are audited as required by TS 6.5.3.1(1) and (m) to ensure compliance with the licensee's Nuclear Power Station OA Manual.
8605300613 860519 PDR ADOCK 05000338 p
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The above referenced programs and procedures constitute the QA Program which implements the applicable provision of the Regu.latory Guides referenced above.
The proposed changes would increase the audit frequency of the ODCM and PCP (including implementin TS 6.5.3.1(l) and (m) g procedures) from 24 months to 12 months for and delete the redundant audit requirement for 12 months j
specified in TS 6.5.3.1(n).
Evaluation:
The proposed changes, as noted above, are administrative in nature and increase the audit frequency of the ODCM and PCP (including the associated implementing procedures) from 24 months to 12 months and delete the redundant requirement specified in the NA-182 TS 6.5.3.1(n), thereby eliminating a redundant requirement and providing greater consistency to the NA-1&P TS. On this basis, we find the proposed changes to be acceptable.
Environmental Consideration:
These amendments involve a change in the installation or use of a facility component located within the re:t-icted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve no significant increase in the amounts, and no signifiant change in the types, of any effluents that may be released offsite, and taat there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously 4
published a proposed finding that these amendments involve no significant hazards consideration and there has been no public coment on such finding.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 951.22(c)(9). These amendments also involve changes in recordkeeping, reporting or administrative procedures or require-ments. Accordingly, with respect to these items, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(10).
Pursuant to 10 CFR 551.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
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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 proposed manner, and (2) such activities will be conducted in compliance with the Comission'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: May 19, 1986 Principal Contributor:
L. B. Engle 6
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