ML20212N166

Forwards Topical Rept Evaluation of XN-NF-85-67 (P),Rev 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel. Rept Acceptable as Ref for Application to Jet Pump BWR Reload Cores,W/Listed Conditions

ML20212N166
Person / Time
Issue date:	07/23/1986
From:	Lainas G Office of Nuclear Reactor Regulation
To:	Ward G SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
Shared Package
ML20212N170	List: ML20212N166 ML20212N200
References
NUDOCS 8608280110
Download: ML20212N166 (2)

Text

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1. . July 23, 1986 Mr. Gary N. Ward, Manager Reload Licensing Exxon Nuclear Company, Inc.

P. O. Box 130 Richland, WA 99352

SUBJECT:

ACCEPTANCE FOR REFERENCING 0F LICENSING TOPICAL REPORT XN-NF-85-67 (P), REVISION 1, " GENERAL MECHANICAL DESIGN FOR EXXON NUCLEAR JET PUMP BWR RELOAD FUEL" We have completed our review of the subject topical report submitted by the Exxon Nuclear Company by letter dated April 21, 1986. This report provides a design description and a summary of supporting analyses and test results for the Exxon Nuclear Company (ENC) Jet Pump Boiling Water Reactor (JP-BWR) 8x8 and 9x9 reload fuel designs. Our safety evaluation of the licensing topical report is enclosed.

Based on our review, in accordance with Section 4.2 of the Standard Review Plan, of the licensing topical report XN-NF-85-67 (P), Revision 1, we conclude that this report may be referenced as an acceptable mechanical design of the

. ENC 8x8 cnd 9x9 fuel for application to jet pump BWR reload cores with the conditions which follow:

(1) The licensee proposing to use this fuel must assure that the local

- power limits provided in the plant technical specifications are within the bounds of the LHGR limit curves shown in Figures 3.1, ,

3.2, and 3.3 of XN-NF-85-67 (P), Revision 1, and I (2) The approval based on review of this report is limited to previously approved burnup levels for BWR fuel (30,000 MWD /MTU batch average exposure). Staff approval for operation to extended burnup levels is contingent on the generic approval of the method by which burnup is considered in the design and analytical processes as described in XN-NF-82-06 (P) and Supplements 1, 2, 4, and 5.

3. ENC has demonstrated conformance to acceptable design limits for fuel rod bowing to exposures of 30,000 MWD /MTU for the 8x8 fuel and 23,000 MWD /MTU for the 9x9 fuel. Additional justification with  !

regard to fuel rod bowing must be provided for operation beyond I these burnup values.

As the result of our review, we find the subject topical report l acceptable for referencing in fuel reload licensing applications if tne methodology has been applied in accordance with the limitations delineated in the report and the associated NRC evaluation, which is enclosed. The evaluation defines the basis for acceptance of the report.

86052ao11o PDR 860723 TOPRP EMygxxy C ,_ , ,5 Q PDR v! '-

2 We do not intend to repeat out review of the matters described in the report and found acceptable when the report appears as a reference in licensing applications, except to assure that the material presented is applicable to the specific plant involved. Our acceptance applies only to the matters described in the report.

In accordance with procedures established in NUREG-0390, it is requested that ENC publish accepted versions of this report, proprietary and non-proprietary, within three months of receipt of this letter. The accepted versions shall incorporate this letter and the enclosed evaluation between the title page and the abstract. The accepted versions shall include an -A (designating accepted) following the report identification symbol. i Should our criteria or regulations change such that our conclusions as to the acceptability of the report are invalidated, ENC and/or the applicants referencing the topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective i applicability of the topical report without revision of their respective documentation.

Sincerely.

Original afgned by lo dvdg'D Gus C. Lainas, Assistant Director r Division of BWR Licensing Office of Nuclear Reactor Regulation

Enclosure:

As stated DISTRIBUTION tCentral File' A. Marinos PDR G. Lainas DCS M. W. Hodges RSB R/F R. Emch W. Houston L. Phillips T. Speis RSB Members D. Crutchfield G. Suh E. Rossi G. Suh R/F

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DBLfRSB  : DBL:AD /

' 0FC : DBL:RSB -

____ . __________:____ _ __ .:____________:________ f___{  :

NAMs.SUH:jhLiv:LPHILLPS :MWH0DGES :GLAINAS'  :  :  :

DATE : ~J/'7/86 :15/IC/86  : F/)S/86

4/d/86

'0FFICIAL RECORD COPY

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