ML20154H534

Safety Evaluation Supporting Amend 90 to License DPR-6

ML20154H534
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/17/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154H517	List: ML20154H514 ML20154H525 ML20154H534
References
NUDOCS 8805250387
Download: ML20154H534 (2)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PELA1ED TO AMEhDPENT NO. 90 TO FACILITY OPERATING LICENSE NO. OPR-6 CONSLMERS POWER COMPANY BIG ROCK POINT PLANT 99.C.K.EL,Nf:_ f 9:_1f_5 l

1.0 INTR 000CTION By letter dated Cecen.ber 14, 1987 Consumers Power Company (the licensee) requested anendnent to the Technical Specifications (TSs) appended to facility Operating License No. DPR-6 for the Big Rock Point Plant. The proposed anendrent would remove the numerical designator from I-type fuel for each subsequent fuel crerating cycle.

2.0 ,E, VALUATION The mechanical, thermal, hydraulic, and neutronic analysis for all Big Rock Point "I" fuel is the sane as that for previous Reloads 1-1 and I-2. The design report previcusly issued for Big Rock Point Reload I-1 (Exxon Nuclear Company (ENC) Report XN-NF-85-38(P), Rev. O, "Cesign Report for Big Pock Point I-1"), is applicable for all Relcads of "I" fuel. The limits are derived in a n.anner identical to that described in ENC Report XN-NF-79-21, Revisicn 1 "Big Rock Point LOCA Analysis using the ENC WREM NJP-BWR ECCS Evaluation Fcdel - MAPLHGR Analysis." This report has been previously reviewed and accepted by the NRC and has been used as a basis for issuing previcus reload an.endments. As stated in the XH-NF-79-21 report, reactor operation within the NRC-approved limits assures conforwance with 10 CFP 50.46 criteria for maxinum cladding ten:perature, rrctal-water reaction, and hydrogen release.

These changes are editorial in nature in that they do not request departure from previcusly NRC-approved practices for Big Rock Point, but only change ene colon.n heading in each of Tables 1 and 2 of Technical Specification 5.2.1.(b) from "Relcad 1-1/I-2" to "Reload I Fuel."

Based on our review, we find this change acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

l This anendment involves a change in the installatien or use of a facility

] conpor.ent located within the restricted area as definec' in 10 CFR Part 20.

We have detervincd that the arrendnent involves no significant increase in the anounts, and no significant change in the types, of any effluents that may be i released effsite, and that there is no significant increase in individual or '

cunulative occupational radiation exposure. The Conmission has previously 1 l

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2 issued a proposed finding that this anendtrent involves ne sigr.ificant hazards censideration and there has been no public ccuent on such finding. Accordingly, this anendaent meets the eligibility criteria for categorical exclusion set forth it.10CFR51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environtrental impact statenent or environntntal assessnent need be prepared in connection with the issuance of this anendrent.

400 CO,N,CLUS10N __

We have concluded, based on the considerations discussed above, that (1) there is reescrable assurar.cc that the health and safety of the public will not be endangered by operation in the proposed nenner, and (2) such activities kill be cer. ducted in con;pliance with the Conn;ission's regulations, and the issuance of the ener.dnent will r.ct be inimical to the corwon defense ar.d security or to the health and safety of the public.

Cate: t'6y 17,1988 Frincipal Centributor: W. Scott

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