ML20153C677

Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed

ML20153C677
Person / Time
Site:	Quad Cities, LaSalle, Framatome ANP Richland
Issue date:	09/17/1998
From:	Curet H SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	NRC
References
REF-PT21-98 NUDOCS 9809240167
Download: ML20153C677 (4)

Text

Sep-17 I 90 15:20 SPC-ND RA/ NAM 509+375+8775 P.02 NRC Oper,ations Center U. S. Nuclear Regulatory Commission Washington, D. C.

Attachment to Siemens Power Corocration - Nuclear Division 10 CFR 21 Reoort (Fuel Cvele and Materials Event Notification Worksheet/NRC Form 361 A) of Sectember 17.1998 10 CFR Part 21 Notification of Defect Relative to MCPR Operating Limits as impacted by Gap Conductance of Co-Resident BWR Fuel For BWR reactors where SPC provides reload fuel, postulated transient events are analyzed each cycle to establish MCPR operating limits. During transition cycles, SPC establishes limits for SPC fuel and also for co resident fuel manufactured by other fuel vendors. Transient analyses are required to address co-resident fuel as well as SPC fuel because previous co-resident fuel transient analyses and limits may no longer be valid due to changes in core neutronic characteristics. Inputs to the transient analyses include the fuel pellet to cladding gap heat transfer coefficient for both SPC fuel and co resident fuel. The gap heat transfer coefficient is calculated using the RODEX2 computer code.

An SPC internal licensing methodology review was performed and concerns were identified relative to the values for several fuel rod characteristics used in the RODEX2 analyses to calculate gap conductance values for input to the transient analyses fo co-resident fuel. An evaluation of these concerns determined there exists reportable defects. The defects were a consequence of modeling the co-resident fuel with cold worked cladding - typical of SPC cladding -instead of annealed cladding as it should have been. The gap conductance behavior of the co-resident fuel affected the core wide neutronic behavior through void reactivity feedback during certain transients and, consequently, the calculation of the transient ACPR for the limiting SPC fuel.

The defects are non conservative MCPR operating limits previously provided to Comed for LaSalle Unit 2 Cycle 8 and Quad Cities Unit 2 Cycle 15. The previously calculated and reported operating limit for LaSalle will be revised before the reactor starts up (anticipated startup in March 1999). The previously calculated and reported operating limits for Quad Cities Unit 2 Cycle 15 were determined at the limiting EOC exposure conditions. Corrected analyses have been performed which demonstrate that the current operating limits are bounding from BOC to a cycle gi exposure of 8 GWd/MTU. The Quad Cities Unit 2 operating limits will be revised before the cycle reaches 8 GWd/MTU. \{

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0 FUEL CYCLE FACILITY EVENT NUMBER: 34791 FACILITY: SIEMENS POWER CORPORATION NOTIFICATION DATE: 09/17/98 RXTYPE: URANIUM FUEL FABRICATION NOTIFICATION TIME: 18:31 [ET)

COMMENTS: LEU CONVERSION (UF6 to UO2) EVENT DATE: 09/17/98 i FABRICATION & SCRAP RECOVERY EVENT TIME: 12 : 00 [PDT] i COMMERICAL LWR FUEL LAST UPDATE DATE: 09/17/98 CITY: RICHLAND REGION: 4 COUNTY: BENTON STATE: WA NOTIFICATIONS l LICENSE #: SNM-1227 AGREEMENT: Y DOCKET: 07001257 MONTE PHILLIPS RDO NRC NOTIFIED BY: HARVEY CURAT VERN HODGE NRR HQ PPS OFFICER: DICK JOLLIFFE EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION:

CCCC 21.21 UNSPECIFIED PARAGRAPH l

EVENT TEXT

- 10CFR PART 21 REPORT - DEFECT RELATED TO MCPR OPERATING LIMITS -

FOR BWR REACTORS WHERE SIEMENS POWER CORPORATION (SPC) PROVIDES RELOAD FUEL, POSTULATED TRANSIENT EVENTS ARE ANALYZED EACH FUEL CYCLE TO ESTABLISH MINIMUM CRITICAL POWER RATIO (MCPR) OPERATING LIMITS. DURING TRANSITION CYCLES, SPC ESTABLISHES LIMITS FOR SPC FUEL AND ALSO FOR CO-RESIDENT FUEL MANUFACTURED BY OTHER FUEL VENDORS. TRANSIENT ANALYSES ARE REQUIRED TO ADDRESS CO-RESIDENT FUEL AS WELL AS SPC FUEL BECAUSE PREVIOUS CO-RESIDENT FUEL TRANSIENT ANALYSES AND LIMITS MAY NO LONGER BE VALID DUE TO CHANGES IN l CORE NEUTRONIC CHARACTERISTICS. INPUTS TO THE TRANSIENT ANALYSES INCLUDE THE FUEL PELLET TO CLADDING GAP HEAT TRANSFER COEFFICIENT FOR BOTH SPC FUEL AND CO-RESIDENT FUEL. THE GAP HEAT TRANSFER COEFFICIENT IS CALCULATED i USING THE RODEX2 COMPUTER CODE.

AN SPC INTERNAL LICENSING METHODOLOGY REVIEW WAS PERFORMED AND CONCERNS WERE IDENTIFIED RELATIVE TO THE VALUES FOR SEVERAL FUEL ROD CHARACTERISTICS i USED IN THE RODEX2 ANALYSES TO CALCULATE GAP CONDUCTANCE VALUES FOR INPUT TO THE TRANSIENT ANALYSES FOR CO-RESIDENT FUEL. AN EVALUATION OF THESE CONCERNS DETERMINED THAT REPORTABLE DEFECTS EXIST. THE DEFECTS WERE A l CONSEQUENCE OF MODELING THE CO-RESIDENT FUEL WITH COLD-WORKED CLADDING, l

-TYPICAL OF SPC CLADDING, INSTEAD OF ANNEALED CLADDING, AS IT SHOULD HAVE BEEN. THE GAP CONDUCTANCE BEHAVIOR OF THE CO-RESIDENT FUEL AFFECTED THE CORE WIDE NEUTRONIC BEHAVIOR THROUGH VOID REACTIVITY FEEDBACK DURING ,

CERTAIN TRANSIENTS AND, CONSEQUENTLY, THE CALCULATION OF THE TRANS7ENT i DIFFERENTIAL CRITICAL POWER RATIO FOR THE LIMITING SPC FUEL.

THE DEFECTS ARE NON-CONSERVATIVE MCPR OPERATING LIMITS PREVIOUSLY PROVIDED TO COMMONWEALTH EDISON FOR LASALLE UNIT 2 CYCLE 8 AND QUAD CITIES UNIT 2 (Continued on next page) a

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LICENSEE: SIEMENS POWER CORPOR PAGE # 2 OF EVENT NUMBER: 34791 CYCLE 15. THE PREVIOUSLY CALCULATED AND REPORTED OPERATING LIMIT FOR l LASALLE WILL BE-REVISED BEFORE THE REACTOR STARTS UP (ANTICIPATED STARTUP IN MARCH, 1999)*. THE PREVIOUSLY CALCULATED AND REPORTED OPERATING LIMITS FOR QUAD CITIES UNIT 2 CYCLE 15 WERE DETERMINED AT THE LIMITING END-OF-CYCLE EXPOSURE CONDITIONS. CORRECTIVE ANALYSES HAVE BEEN PERFORMED '

WHICH DEMONSTRATE THAT THE CURRENT CPERATING LIMITS ARE BOUNDING FROM  !

BEGINNING-OF-CYCLE TO A CYCLE EXPOSURE OF 8 GWd/MTU. THE QUAD CITIES J UNIT 2' OPERATING LIMITS WILL BE REVISED BEFORE THE CYCLE REACHES 8 GWd/MTU. .

SPC EVALUATED THIS ISSUE UNDER SPC CONDITION REPORT #6565, DATED 03/02/98,  ;

AND PREVIOUSLY INFORMED THE NRC OF THIS ISSUE VIA SPC INTERIM REPORT

1. 98-004, DATED 07/22/98.

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See attached summary of defect related to MCPR operating limits. Affected customer (Comrnonweakh Edison / Quad Cities Unit 2 (operating) and LaSalle Unit 2 (not operating)). Tha NRC was previously informed of the issue via SPC Interim Report 98-004 (7/22/98h l

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• Date of reporting to NRC Operation Center. Defect was evaluated under SPC Condition Report 6565 initiated March 2,1998.

Duty Officer: Report #

NRC FORM 361 All1/943 I ,