ML20125B807

Safety Evaluation Supporting Amend 188 to License NPF-1

ML20125B807
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/04/1992
From:	Office of Nuclear Reactor Regulation
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Shared Package
ML20125B802	List: ML20125B799 ML20125B803 ML20125B807
References
NUDOCS 9212100159
Download: ML20125B807 (4)

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)P ei NUCLEAR REGULATORY COMMISSION o WASHINoToN, D.C. 20666 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION-RELATED TO AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-1 fpRTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE. OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR P1ANI DOCKET NO. 50-344 1.0. INTRODUCTION By letter dated September 25, 1992, and supplemented October 14, 1992 Portland General Electric Company, et al.- CPGE or licensee) submitted a request for changes to the Facility Operattng License No. NPF-1 for Trojan Nuclear Plant. The proposed changes would delete License Condition 2.C.(ll),

" Fuel Assemblies," from facility Operating License No. NPF-]. This is an administrative change since the license condition is no. longer necessary at Trojan Nuclear Plant, and is the result of a commitment made by the licensee in a letter dated March 2, 1990. This re 90-02, Supplement 1, " Alternative Require' nentsquest is related for Fuel to Generic Assemblies in the Letter Design Features.Section of Technical Specifications," which was issued on t

July 31, 1992.

2.0 EVALUATION The use of stainless steel rods in fuel assemblies was necessary to avoid; water-jetting through gaps in the baffle plates surrounding the reactor core-due to the pressure difference across the plates. Water impingement caused fuel rod damage-in peripheral fuel assemblies. .However, this-contradicted Technical Specification (TS) 5.3.1, ': uel Assemblies." License Condition 2.C.(ll) provided a waiver from the requirements- of-Technical Specifications 5.3.1, " Fuel As:emblies," which allowed use of stainless steel rods and extra grid straps in fuel assemblies. This paragraph has been continuously-modified to extend the waiver for subsequent cycles (i.e., Amendments.45, 60, 75, and 82).

With a modification to the reactor core internals to reverse the bypassiflow-direction between the core barrel and'the baffle plates, the pressure differential.was. reduced across the baffle plates, and thus allowed use of . _

unmodified fuel-assemblies. Amendment 91 to the license condition was issued-

-to prohibit fresh fuel assemblies containing stainless steel rods and extra-

. grid straps.

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However, in a letter dated March 2, 1990, the licensee interpreted this license condition as not applying to fuel reconstitution. TS Amendment 153 allowed a limited substitution of fuel rods with filler rods consisting of Zircaloy-4 or stainless steel, or by vacancies, provided that it was justified by a cycle-specific reload safety analysis. The licensee maintained that the license condition prevented the use of stainless steel rods in fresh fuel assemblies for the >urpose of coping with the baffle water-jetting problems, but did not limit tie use of stainless steel rods for other reasons such as fuel reconstitution. The licensee comitted to delete the contradictory license condition.

Since the modification eliminated the issue concerning baffle water-jetting damaging peripheral fuel assemblies, the need for License Condition 2.C.(11) is no longer relevant, and should be removed in order to avoid any contradiction between the License Condition 2.C (11) and TS 5.3.1. In regard to the cycle-specific reload safety analysis and fuel reconstitution issues, PGE committed in its October 14, 1992, letter to implement the features of Generic Letter 90-02, Supplement 1, although PGE chose the option not to change the 1rojan Technical Specifications. Specifically, any fuel reconstitution performed for the Trojan Nuclear Plant will be performed in accordance with an NRC-approved methodology as defined in Generic Letter 90-02, Supplement 1. This should preclude any future difficulties which may arise concerning the use of stainless steel rods in fuel assemblies.

Therefore, based upon the information provided in the licensee's submittal dated September 25, 1992, and supplemented October 14, 1992, and the information provided above, the staff approves the deletion of License Condition 2.C.(11) from Facility Operating License NPF-1.

3.0 STATE CONSVLTATION in accordance with the Commission's regulations, the Oregon State official was notified of the proposed issuance of the amendment. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes surveillance requirements. The NRC staff has determined that the amendment involves 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 radiation exposure. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 48824). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR Sl.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

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5.0 CONCLUSION

The Comission has 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 Comission's regulations, and (3) the issuance of the amendment will not be inimical to the comon defense and security cr to the health and safety of the public.

Principal Contributor: Lawrence E. Kokajko Date: December 4, 1992

November 30, 1992 Docket No. 50-344 fir. James E. Cross Vice President and Chief Nuclear Officer Portland General Electric Company 121 S.W. Saluon Street Portland, Oregon 97204

SUBJECT:

ISSUANCE Of AMfNDMENT FOR 1ROJAN NUCLEAR P J11 (1AC NO. M84651)

The Commission has issued the enclosed Amendment i 188 to facility Operating License No. NPT-1 for Trojan 11uclear Plant. The mendment consists of changes to the Technical Specifications (TS) in respons to your application dated September 25, 1992, and supplemented October ] , 1992 designated by you as LCA-216.

The amendment deletes License Condition 2. .(11), " fuel Assemblies," from facility Operating Licnese NPF-1. This i an administrative change since the license condition is no longer necessary at Trojan Nuclear Plant.

A copy of the related Safety Evaluati i is also enclosed. A notice of issuance will be included in the Comt ssion's next regular biweekly fMetal Resister notice.

Sir erely, Jriginal signed by:

-wrence E. K'okajko, Senior Project Manager

'roject Directorate V Division of Reactor Projects lil/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1, Amendment No.188 to IPF-1

2. Safety Evaluation cc w/ enclosures:

See next page i

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OfflCIAL RECORD COPY DOCUMENT NAME: TJ84651.AMD i

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