ML20065E315

Safety Evaluation Supporting Amends 114 & 96 to Licenses NPF-9 & NPF-17,respectively

ML20065E315
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/18/1990
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065E313	List: ML20065E310 ML20065E315
References
NUDOCS 9010020093
Download: ML20065E315 (3)

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'.1 i['., k UNITED STATES NUCLEAR REGULATORY COMMISSION

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION L

l RELATED TO AMENDMENT NO.114TO FACILITY OPERATING LICENSE NPF-9 l

AND AMENDMENT NO. 96 TO' FACILITY OPERATING LICENSE NPF-17 '

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DUKE POWER COMPANY h

DOCKET NOS. 50-369 AND 50-370 NCGUIRE NUCLEAR STATION. UNITS 1 AND 2

1.0 INTRODUCTION

L By letter dated April-24, 1990 Duke Power Company (the licensee) proposed amendments for ticGuire Nuclear Station, Units 1 and 2.

The proposed amendments -

would provide for the relocation of tabular listings of containment penetration conductorovercurrentprotectivedevicesfromtheTechnicalSpecifications(TO)

-to Chapter 16 of the Final Safety Analysis' Report (FSAR), " Selected Licensee

! Comitment Manual." Specifically, TS Table 3.8-la " Unit 1 Containment Penetration Conductor Overcurrent Protective Devices," and TS Table'3.8-lb, " Unit 2 Containment Penetration Conductor Overcurrent Protective Devices," would be deleted, and references to them in TSs 3/4.B.4 would be changed to reference FSAR Chapter 16. ' The TS Index would be updated to reflect these deletions.

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'2.0. EVALUATION TS Tables 3.8-la and 3.8-lb list' devices (deenergizing circuit breakers and fuses) associated with the protection of containment electrical penetrations and-penetration conductors due to excessive current. 'For each device number, the tables-identify: location, trip setpoint or continuous rating, response time, and the associated, system powered by the circuit.: The proposed amendments involve no substantive changes-to the contents of the tables, only format changes due to their

relocation from the TSs to the FSAR.

TS 3.8.4 requires as a limiting condition for operation (LCO), that the devices listed in these tables be maintained operable while the-facility is-in Modes 1,'2, 3, and 4; TS 4.8.4-requires, as a surveillance requirement (SR),'that the devices periodically be demonstrated operable and functionally tested. These LCOs anc SRs would not.be changed by the proposed unendments except to-reflect the revised location of the tables. - Consequently, all of the proposed changes are'of an administrative nature.

McGuire FSAR Chapter 16 contains selected licensee comitments, primarily derived from former TSs, to control important plant.equipmer.t and operating conditions. The comitments involve systems and components that are part of r

the licensing basis, as described elsewhere in~ the FSAR, butLthat are not

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of such a level.of importance as'to require the more rigorous controls associated with TSs.. For convenience, Chapter 16.is located in a separate binder entitled p

"McGuire Nuclear Station Units 1 and 2; Selected Licensee Comitments." A copy L

is located in the McGuire control room for use by operators along with the TS L

document.

The manual is also received and maintained by holders of the FSAR and

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key station personnel that are holders of the TSs.

Station activities required by these comunitsents are controlled and implemented in accordance with the licensee's procedures and directives.

In the event future changes are needed to this information in the FSAR, the proposed changes would be evaluated in accordance with the proutss described in l

10 CFR 50.59.

Under 10 CFR 50.c9, proposed changes determined by the licensee not i

1to involve an unreviewed safeta question may be made without prior Commission l-approval. A report of such changes, including a susunary of the safety evaluation of each, would be submitted annually to the Commission. Additionally, the licensee u

requires that all changes to the FSAR Chapter 16 receive Station Manager approval, L

and that, upon issuance, all revisions to FSAR Chapter 16 be distributed to holders of the Selected Licensee Cosunitment Manual, including the NRC.

The Comunission has l

L deterinined, as part of its implementation policy for TS improvements, that the lists of these overcurrent protective devices are appropriate for miocation to a L

document controlled by the licensee under 10 CFR 50.59.

t Accordingly, we find that the proposed changes have no adverse impact upon safety and are, therefore, acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

These amendments involve changes in a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The staff has determined that the amendments involve no significant increase in the amounts, and no l

significant change in the types, of any effluents that may be released offsite j

and that there is no significant increase in individual or cumulative occupational radiation exposure. - The Conunission has previously issued a. proposed finding that these amenosents involve no significant hazards consideration, and there has:been no public cossnent 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 environsental i

assessment need be prepared in connection with the issuance of these amendments.

4.0 -CONCLUSION l

The Commission's proposed determination that the amendments involve no significant hazards consideration was published in the Federal Register (55 FR 20353) on May 16, 1990. The Comission consulted with the State of North Carolina. No public comments were received, and the State of North Carolina did not have any coments.

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-l 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 these amendaents will not be inimical to the cecmon defense and security or to= the health ano safety of the public.

Principal Contributor:

D. Hood, PDflI-3/DRP-I/II Dated: September 18, 1990

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t DATED: Sentomber 18. 1990 q

AMENDMENT NO.'114 TU FACILITY OPERATING LICENSE NPF McGuire: Nuclear. Station, Unit 1:

j AMENDMENT-NO. 96 TO FACILITY. 0PERATING LICENSE NPF McGuire Nuclear Station,- Unit 2:

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