ML20073J488
| ML20073J488 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/24/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073J486 | List: |
| References | |
| NUDOCS 9105080210 | |
| Download: ML20073J488 (3) | |
Text
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. f* M%g UNITED STATES T!),,
i NUCLEAR REGULATORY COMMISSION 1., S WASHINoTON, D.C. 20556
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y SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PELATED TO AMENDMENT tl0. 42 TO FAClllTY OPERATING LICENSE NO. NPF-5'/
PUBLIC SERVICE ELECTRIC & GAS COMPANY
,A,TLANTIC CITY ELECTRIC COMPANY HOP E C R E E K, G E N E,R AT I N G,,S,T AT I O N_
l ppgET NO. 50-354
1.0 INTRODUCTION
By letter dated December 28, 1990, Public Service Electric & Cas Company (the licensee) submitted a request for changes to the Hope Creek Generating Station (HCGS), Facility Operating License No. NPF-57. The requested changes would make the HCGS Technical Specifications (TS) definition for CRITICAL POWER RATIO more generic with regard to the critical power correlation. This will permit the use of new NRC-approved fuel designs and their associated NRC-approved correlations without requiring amendment of this section each time. Additionally, the bases for THERMAL POWER and MINIMUM CRITICAL POWER r
l RATIO are modified to reference the latest approved version of the GC Standard Application for Reactor Fuel (GESTAR II) and to more clearly define how certain MCPR factors are determined, i
l 2.0 MALUATION The Definitions section of the TS was modified to make the definition for CRITICAL POWER RATIO more generic with regard to the critical power correlation used. The change will define CRITICAL POWER RATIO as the ratio of that power in an assembly which is calculated by application of the " applicable NRC-approved critical power correlation" to cause some point in the assembly to experience boiling transition, divided by the actual assembly power. The previous definition specified General Electric's "GEXL" correlation which has been modified to include considerations for a high performance spacer (ferrule ty "GEXL-plus"pe) design in the GE9 fuel. The new correlation is termed, This amendment will permit the use of new NRC approved fuel designs and their associated NRC approved correlations without requiring amendment of this section each time. Additionally, the Bases for THERMAL POWER I
and MINIMUM CRITICAL POWER RATIO have been modified to reference the latest approved version of the GE Standard Application for the Reactor Fuel (GESTAR II) and to more clearly define how MCPR K factors are determined.
f In order to install any new fuel design in the HCGS reactor, the change in fuel design and supporting correlations will have been previously reviewed and approved by the NRC.
New core operating limits will have been generated and documented in the CORE OPERATING LIMITS REPORT, as required by the TS, to ensure that all safety criteria were met for all analyzed accidents and limiting transients.
9105080210 910424 PDR ADOCK 05000354 P
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2-i This process, along with the requirements of 10 CFR 50.59, ensures that the j
fuel systcm design, nuclear design, thermal / hydraulic design and the cenclusions of the original core analysis are re-analyzed and remain valid for the accidents and limiting transients previously evaluated in the UFSAR.
Based j
cn our review, we conclude that the proposed uanges to the CRITICAL POWER RATIO and the bases for THERi?AL POWER and MINIMUM CRITICAL POWER RATIO are primarily administrative in nature and are acceptable.
l The staff, with the concurrence of PSE&G, made the following editorial change:
1 The parenthetical note immediately folicwing Reference 1 on page B 2-2 and Ecference 2 on page B 3/4 2-4 was changed from "(latest approved revision)" to
"(The approved revision at the time the reload analyses are performed. The approved revision rumber shall be identified in the CORE OPERATING LIMITS
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REPORT.)"
The above change was necessary to clearly identify which revision of General Electric Standard Application for Reactor Fuel, NE0E-24011-P-A was used. The abcve change did not increase the scope of the original amendment request and did not affect the staff's original no significant hazards determination.
3.0 STATE CONSULTATION
s In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSICERATION J
This amendment changes a requirement with respect to installation or use of l
a fecility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff bas detcrmined that the crendment involves no i
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 i
increase in individual or cumulative occupational radiation exposure. The l
Commission has previously issued a proposed finding that the amendment involves ne signficant hazards consideraticn, and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for
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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 this amendment.
5.0 CONCLUS,10N_
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of l
the public will not be endangered by operation in the proposed manner, i
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- and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be-inimical to the common defense and security nor to the health and safety of the public.
Principal Contributor:
Stephen Dembek Date:
April 24, 1991 l
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