ML20247P727

Safety Evaluation Supporting Amend 69 to License DPR-22

ML20247P727
Person / Time
Site:	Monticello
Issue date:	09/12/1989
From:	Office of Nuclear Reactor Regulation
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ML20247P717	List: ML20247P710 ML20247P727
References
NUDOCS 8909270256
Download: ML20247P727 (3)

Text

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- s 044 9'o UNITED STATES E

1 NUCLEAR REGULATORY COMMISSION f,

E WASHINGTON, D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 7'

RELATED TO. AMENDMENT NO. s;o TO FACILITY OPERATING LICENSE N0. DPR-2?

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NORTHERNSTATESPOWERNOMPANY I

MONTICELLO NUCLEAR GENERATING PLANT

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DOCKET NO. 50-263

1.0 INTRODUCTION

By letter dated March 7,1989, Northern States Power Company (the licensee) submitted a license amendment application proposing to revise the Monticello Technical Specifications (TS) to pemit the use of alternates in meeting the quorum requirement for the plant Operations Comittee (OC). The plant OC consists of at least six (6) members drawn from key supervisors of the Onsite Supervisory Staff, whose responsibilities include the review of:

(1) modifi-cations to plant systems or components described in the Updated Safety Analysis Report for Monticello; (2) changes to nonnal and emergency operating procedures; (3) TS change proposals; and (4) the results of TS violation investigations.

The specific TS changes proposed are as follows:

Change paragraph "6.2.B.1" to "6.2.B.1.a."

In the first sentence of paragraph 6.2.B.1, change "...at least six (6) members...." to "...at least six (6) regular membe rs.... "

In the second sentence of paragraph 6.2.B.1, change "... appoint a Vice Chainnan frosi the OC membership to act in his absence...." to

... appoint a regular member to act as Vice Chairman in his absence...."

s Add two new sentences at the end of paragraph 6.2.B.1 to read:

" Alternates to the regular members shall be designated in writing by the Chairman, or Vice Chainnan in the Chainnan's absence, to serve on a temporary basis. No more than two alternates shall participate as voting members of the Operations Comittee at any one time."

In paragraph 6.2.B.4, change "...a majority of the permanent members...." to "...a majority of the membership...."

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L2.0 DISCUSSION AND EVALUATION i

The TS for Monticello currently do not':ddress the use of alternates on the l

lP ant OC in meeting the_ quorum requirmeent. The day-to-day plant operational demands placed on the onsite supervisory staff who also serve on the plant 0C l

as permanent or regular members, and the related multiple responsibilities on those individuals, necessitates the use of alternates in order to provide some flexibility in operating the plant. The need for such flexibility and the use l

of altemates for the plant OC was recognized by the NRC staff in the development-of the Standard Technical Specifications, developed for General Electric I

boiling water reactor _ which: (1) allows the use of alternates for regular DC members in meeting the committee quorum requirement, thereby reducing the heavy time demands pinced on plant OC regular members; and (2) provides for a masonable degree of flexibility in the day-to-day business of plant operational activities which will not compromise safety.

The TS changes proposed by the licensee will allow the use of up to two (2) alternates for meeting the plant OC quorum requirement; and nc more than two I

alternates _ would participate as voting members at any one time on the plant OC.

OC team members are defined as regular members being individuals wiio normally J

fill OC positions, while OC alternates are defined as membership positions filled by anyone other than a regular member, designated to serve as an alternate in writing by the OC Chairman or Vice Chairman in the absence of the l

. Chairman.

The proposed TS changes, and the basis provided by the licensee in support of l

those changes, have been reviewed and are found to be reasonable and acceptable j

as proposed..The changes being accepted for the Monticello TS are consistent-and similar to those found acceptable by the NRC staff for other licensed nuclear I

plant TS and confom with the plant DC membership and' quorum requirements set forth in the Standard Technical Specifications. The changes do not affect the physical. configuration of the plant or how it is operated. Nor are plant systems or operating procedures affected by this change. The change merely provides the licensee with administrative flexibility to more efficiently and effectively utilize and schedule onsite supervisory staff for the day-to-day operations of the plant and the functioning of the plant OC.

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3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, with respect to these items, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the e,

issuance of this amendment.

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4.0 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: John J. Stefano, NRR Dated: September 12, 1989

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