ML20215B919

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Safety Evaluation Supporting Amends 63 & 44 to Licenses NPF-9 & NPF-17,respectively
ML20215B919
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 09/29/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215B917 List:
References
NUDOCS 8610090446
Download: ML20215B919 (2)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 63TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 44 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY DOCKET NOS. 50-369 AND 50-370 McGUIRE NUCLEAR STATION, UNITS 1 AND 2 INTRODUCTION By letters dated July 15, 1985 and March 12, 1986, Duke Power Company, the licensee for McGuire Nuclear Station. Units 1 and 2, requested that valve NI-1228 be deleted from Table 3.6-2 in the Technical Specifications, and, in addition, proposed a station modification which would remove the con-tainment isolation signal to this valve. The licensee's justification for the change is that valve operation is administratively controlled, and during plant operation the valve is normally closed, which makes the con-tainment isolation signal to this valve unnecessary.

By letters dated May 14, 1986 and July 14, 1986, the licensee also requested, among other things, that seven valve designations listed in Table 3.6-2 be corrected. These changes are to correct an error and do not change plant operation or any safety analysis. The remaining changes proposed by the licensee in the May and July 1986 letters will be handled separately.

EVALUATION Changes associated with valve NI-1228 The staff has reviewed the licensee's submittals, relevant piping and instrumentation diagrams and the containment isolation provisions on associated fluid lines. Valve NI-1228 is inside containment in a 3/4-inch line that connects the reactor hot leg safety injection line at a point between the containr.ent isolation valves, with the check valve test header downstream of the inboard containment isolation valve.

Its primary function is to act as a block valve to isolate the safety injection line from the non-safety grade check valve test header.

The staff concludes that the containment isolation signal to valve NI-122B is unnecessary and the plant administrative controls are adequate to ensure that valve NI-122B is closed during plant power operations. Therefore, the requested deletion of valve NI-122B from Table 3.6-2 in the Technical Speci-fications and the plant modification to McGuire Nuclear Station are acceptble.

Changes associated with Table 3.6-2 valve designations The licensee has proposed to correct an error in the valve designations as follows:

8610090446 860929 PDR ADOCK 05000369 [

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CF-151A to CF-151B CF-135A to CF-135B NF-233A to NF-233B NM-25A to NM25AC NV-849A to NV-849AC NM-3A to NM-3AC NM-22A to NM-22AC We agree with the licensee that the existing valve designations are in error and are appropriately corrected by the proposed changes.

We' find that these char.ges are strictly administrative in nature and do not impact plant safety or operation. Accordingly, these changes are acceptable.

ENVIRONMENTAL CONSIDERATION These amendments involve changes to the installation or use of facilities' com-ponents located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendments 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 exposure. The Commission has previously issued a pro-posed finding that these amendments involve no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amend-ments meet the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.

CONCLL'SION The Commission made proposed determinations that the amendments involve no significant hazards consideration which were published in the Federal Register t

(51FR30569and30571)onAugust 27, 1986, and consulted with the state of North Carolina. No public comments were received, and the state of North Carolina did not have any comments.

We have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will i

not be endangered by operation in the proposed manner, and (2) such activities l

will be conducted in compliance with the Commission's regulations, and the l

issuance of these amendments will not be inimical to the connon defense and l

security or to the health and safety of the public.

Principal Contributors:

R. J. Giardina D. Wigginton Dated:

September 29, 1986

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