ML20149F785

Safety Evaluation Supporting Amends 78 & 59 to Licenses NPF-9 & NPF-17,respectively

ML20149F785
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/04/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20149F770	List: ML20149F767 ML20149F785
References
NUDOCS 8801140336
Download: ML20149F785 (3)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.78 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT N0. 59 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY DOCKET NOS. 50-369 AND 50-370 McGUIRE NUCLEAR STATION, UNITS 1 AND 2 I.

INTRODUCTION In NRC Inspection Reports Nos. 50-369/85-38 and 50-370/85-39, dated June 27, 1986, the staff identified concerns involving the McGuire Units 1 and 2 nuclear service water (RN) system. One of these concerns related to the Technical Specifications (TS) for the RN system, TS 3.4.7.4, which did not indicate the shared aspects of the McGuire RN system. A Notice of Violation and Proposed Imposition of Civil Penalty (Notice) was subsequently transmitted (Enforcement Action 87-07) to Duke Power Company (the licensee) on March 6, 1987.

Item B of that Notice concerned the fact that the licensee, contrary to TS 3/4.7.4, cross-connected the 1A and 2A trains of the McGuire RN system based on an incorrect 10 CFR 50.59 evaluation. By letter dated April 3,1987, the licensee responded to Enforcement Action 87-07 and comitted to revise the RN system TS to reflect the shared aspects.

By letter dated July 31, 1987, the licensee proposed license amendments to re-vise the RN system TS accordingly. The proposed license amendments revise the action statement of the RN system TS to reflect that some portions of the RN system are shared between the two units, but the system is not shared in its entirety. The shared and unshared portions of the RN system would be specifi-cally identified in the TS by adding Figure 3/4 7-1 to the specifications and adding new text to the Bases Section in addition to Table B 3/4 7-1 which lists the Unit 1 and 2 shared valves. The proposed amendments would also clarify the related surveillance requirement which is intended to be applied on a "per unit" l

basis.

II.

EVALUATION The revision to the ACTION Section of TS 3/4.7.4 includes separate statements to clarify the actions and allowable outage times for the situations in which an inoperable component affects a single unit or both units.

The previous action statement required that with only one RN loop OPERABLE, two loops were to be OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the plant was to be in at least hot standby I

within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l The first action statement, item (a) of the revised specification', is basically l

the same as the previous except that it requires the ACTION to be taken when the unit specific portion of only one RN loop is OPERABLE and requires that l

both unit specific loops be returned to OPERABLE status.

The action statement, h

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b

. therefore, applies to only one unit.

The second action statement, item (b) of the revised specification, addresses the shared portions of the RN system as defined by the new Figure 3/4 7-1.

It requires that with only one of the shared portions of the loop OPERABLE, both portions are to be returned to an OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or both units are to be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

In addition to the new action statements, the amendments also revise the sur-veillance requirements to state that at least two RN loops "per unit" shall be demnnstrated OPERABLE.

The previous surveillance requirements did not specify "per unit." The BASES Section of the Technical Specifications is also revised to reflect the shared aspects of the system.

The revised action statements include the same time requirements (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for hot standby and 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> for cold shutdown) as the previous TS. The revision is to assure that whenever a shared portion of the RN system is inocerable, both units are affected by the action statement.

The design of the RN system meets the requirements of General Design Criterion (GDC) 5. "Sharing of Struc-tures, Systems and Components" in that no single failure will prevent the RN -

system from perfonning its safety function, including, in the event of an acci-Jent in one unit, an orderly shutdown and cooldown of the other unit.

However, the previous TS 3/4.7.4 could have been interpreted in a manner which would indicate that GDC 5 could be violated in the event of certain equipment failures if the action statement was not applied to both units.

The revised TS 3/4.7.4 ensures that GDC 5 will be met by specifically identifying which portions of the RN system are shared and under what conditions the action statement should be applied to both units.

During its review of the licensee's submittal, the staff noted a labeling dis-crepancy between Table B 3/4 7-1 and Figure 3/4 7-1.

In the table, the valve in the low level intake supply lines to the RN system was labeled ORN-1 while the valve of interest on the drawing did not have an identifying number. Also in the table the valves identified as ORN-3A, C, ORN-7A, C and ORN-150A, C did not have the "C" designation in Figure 3/4 7-1.

Because these letters "A" and "C" have power supply connotations and since the figure is to be part of the TS, the staff concluded it should be corrected to agree with Table B 3/4 7-1.

In a subsequent discussion with the licensee, the licensee agreed that the proposed TS Figure 3/4 7-1 should be revised such that the valves numbered 3A, 7A and 150A become 3A, C; 7A, C and 150A, C while the single unnumbered valve between the low level intake and the RN system should be designated 1, to agree l

with Table B 3/4 7-1 where it is identified as ORN-1. Therefore, these l

administrative changes have been made.

Accordingly, the staff has reviewed the revision to TS 3/4.7.4 and its bases B 3/4.7.4 along with the licensee's justification and safety analysis related to the revision. Based on its review, the staff concludes that the revision, I

which is primarily a clarification, properly reflects the shared and unshared i

aspects of the nuclear service water system and adequately specifies when the action statement for the limiting conditions for operation should' apply to both l

units. The revision, thereby, assures that the McGuire nuclear service water I

system will be operated in accordance with GDC 5, as it relates to sharing of i

safety related equipment. The staff, therefore, concludes that the revision is acceptable.

I.

III. ENVIRONMENTAL CONSIDERATION These amendments involve changes to the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20 and clarification of a surveillance requirement. The staff has detemined 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 NRC staff has made a detemination that the amendments involve no significant hazards consideration, and there has been no public comment on such finding.

Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(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.

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IV. CONCLUSION The Comission made a proposed detemination that the amendments involve no significant hazards consideration which was published in the Federal Register-(52 FR 34003) on September 9, 1987. The administrative change subsequently made by the NRC staff regarding the labeling of certain valves in TS Figure 3/4 7-1 does not change this detemination or its basis. The Comission consulted with the state of North Carolina. No public coments were received, and the state of North Carolina did not have any coments.

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

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

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

will be conducted in compliance with the Comission's regulations, and the issuance of these amendments will not be inimical to the comon defense and security or to the health and safety of the public.

l Principal Contributors: Darl S. Hood, PDII-3/DR31/II l

William LeFave, Plant Systems Branch l

l Dated:

January 4, 1988 l

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DATED:

January 4, 1988 AMENDMENT N0. 78 TO FACILITY OPERATING 'ICENSE NPF McGuire Nuclea" Station, Unit 1 AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NPF McGuire Nuclear Station, Unit 2 DISTRIBUTION:

Docket File-50-369/370 HRC PDR Local PDR PRC System NSIC PD#23 Reading M. Rood D. Hood 0GC-Bethesda J. Stone E. Jordan L. Harmon W. Jones T. Barnhart (8)

ACRS (10)

ARM /LFMB GPA/PA E. Butcher D. Hagan L. Reyes S. Varga/G. Lainas W. LeFave 1

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