ML20153C677: Difference between revisions

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{{#Wiki_filter: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.
{{#Wiki_filter:I Sep-17 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.
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.
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.                                                         \{
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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k'v 9909240167 980917 PDR   ADOCK 05000265 s                     PDR
~
9909240167 980917 PDR ADOCK 05000265 s
PDR


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)
0 FUEL CYCLE FACILITY EVENT NUMBER:
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:
34791 FACILITY: SIEMENS POWER CORPORATION NOTIFICATION DATE: 09/17/98 RXTYPE: URANIUM FUEL FABRICATION NOTIFICATION TIME: 18:31 [ET)
CCCC 21.21                 UNSPECIFIED PARAGRAPH l
COMMENTS: LEU CONVERSION (UF6 to UO2)
EVENT TEXT
EVENT DATE:
  - 10CFR PART 21 REPORT - DEFECT RELATED TO MCPR OPERATING LIMITS -
09/17/98 FABRICATION & SCRAP RECOVERY EVENT TIME:
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.
12 : 00 [PDT]
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
COMMERICAL LWR FUEL LAST UPDATE DATE:
  -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                   ,
09/17/98 CITY: RICHLAND REGION: 4 COUNTY: BENTON STATE: WA NOTIFICATIONS LICENSE #: SNM-1227 AGREEMENT: Y DOCKET: 07001257 MONTE PHILLIPS RDO NRC NOTIFIED BY: HARVEY CURAT VERN HODGE NRR HQ PPS OFFICER:
CERTAIN TRANSIENTS AND, CONSEQUENTLY, THE CALCULATION OF THE TRANS7ENT                 i DIFFERENTIAL CRITICAL POWER RATIO FOR THE LIMITING SPC FUEL.
DICK JOLLIFFE EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION:
CCCC 21.21 UNSPECIFIED PARAGRAPH 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 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 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 TRANS7ENT 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
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


              .g.. . . . ~ - -               .  -  . . . . . _ . ..          -        . . .. . . - . __
.g..
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                                   !
LICENSEE: SIEMENS POWER CORPOR PAGE # 2 OF EVENT NUMBER: 34791 CYCLE 15.
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.                          .
THE PREVIOUSLY CALCULATED AND REPORTED OPERATING LIMIT FOR l
SPC EVALUATED THIS ISSUE UNDER SPC CONDITION REPORT #6565, DATED 03/02/98,                           ;
LASALLE WILL BE-REVISED BEFORE THE REACTOR STARTS UP (ANTICIPATED STARTUP IN MARCH, 1999)*.
AND PREVIOUSLY INFORMED THE NRC OF THIS ISSUE VIA SPC INTERIM REPORT
THE PREVIOUSLY CALCULATED AND REPORTED OPERATING LIMITS FOR QUAD CITIES UNIT 2 CYCLE 15 WERE DETERMINED AT THE LIMITING END-OF-CYCLE EXPOSURE CONDITIONS.
        #98-004, DATED 07/22/98.
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
#98-004, DATED 07/22/98.
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l-NRC FORM 361 A U S NUCLEAR RtGULATORY COMMf 5510N LICENSE NUMeER 3
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111/941 FUEL CYCLE AND MATERIALS SN C 227 EVENT NOTIFICATION WORKSHEET fN' 7
6 a
REPORT TIME FACluTV OR CRGAN'IATION NAME CfjALLt2 CALLSACE TELEPNQNt
 
/ p) g rf4AyQ NuMstR.
Sep,-17-99 15:20                        SPC-ND RA/ NAM                                                  509+375+8775                                        P.01
U SIEMENS POWER CORPORATION NUC. Div.
  ,  e 1
H. D. Curet
l l-            NRC FORM 361 A         . 3 U S NUCLEAR RtGULATORY COMMf 5510N         LICENSE NUMeER 111/941 FUEL CYCLE AND MATERIALS                                                             SN C 227 REPORT TIME EVENT NOTIFICATION WORKSHEET FACluTV OR CRGAN'IATION                                 NAME CfjALLt2 7            fN' CALLSACE TELEPNQNt
($091375-8563 EvthT TIME gygNy pArg LOCAT ON 08 tytNT I NCLUDE COUNIV AN0 51ATtr PORTION OF PLANT AFFtCYg0 N/A 9 / 17 / 98 RiChland. Benton County, WA N/A tVENT CLA5$lFICATsON EVINT TYPES INCIDENT REPORT $
              / p)
(30.52. 40 60. 70 501 GENERAL EMERGENCY
U       g      SIEMENS POWER CORPORATION NUC. Div.
* X FUEL CYCLE 20 2201 LC$$ TMEFT to TEC Vt ACTION Siff AREA fMtRGENCY ME DICALJACA DEM.C 20 2202 ACTUAL /THRf ATENED UNPLANNEO gg OVERf xPOSURE CONTAMINATION ALtRI TRANSPCRT& TION 20 2202 "O IV AL#TM'I'II"'I D SAFETY (QUIPMtNT W@
rf4AyQ H. D. Curet NuMstR.
RfLtASE FAILURE NO F ATION OF UNUSUAL I
($091375-8563 EvthT TIME       gygNy pArg   **        LOCAT ON 08 tytNT I NCLUDE COUNIV AN0 51ATtr                       PORTION OF PLANT AFFtCYg0 N/A               9 / 17 / 98           RiChland. Benton County, WA                                       N/A tVENT CLA5$lFICATsON                 EVINT TYPES                                 INCIDENT REPORT $ (30.52. 40 60. 70 501 GENERAL EMERGENCY
WA$TF MANAGEMENT X
* X   FUEL CYCLE                   20 2201     LC$$ TMEFT                     to               TEC Vt ACTION Siff AREA fMtRGENCY             ME DICALJACA DEM.C           20 2202     ACTUAL /THRf ATENED           gg         UNPLANNEO OVERf xPOSURE                               CONTAMINATION ALtRI                           TRANSPCRT& TION               20 2202     "O IV AL#TM'I'II"'I D                     SAFETY (QUIPMtNT RfLtASE                        W@
21 21 N NCO PLI ANC E WT C A NAT N s
FAILURE NO F ATION OF UNUSUAL                                                         I WA$TF MANAGEMENT           X 21 21 N NCO PLI ANC E                           WT C         A NAT N s     INCIDENT REPORT                 IkOUSTR!As./COMMf RCIAL       26 73       FITNESS FOR Ou17               tta 44)     FIRf / E *PLOSiON TRANSPORTATf0N EVENT             FOREIGN EVENT                 36 33     MIS ADVINISTRA TION             7012       CRITICALITY / SNM LOST INFORMATION ONLY                 OTHER {$psCdf l               36 83     shAADe ATOR EVENT             70 62 U
INCIDENT REPORT IkOUSTR!As./COMMf RCIAL 26 73 FITNESS FOR Ou17 tta 44)
TwtF,AL s aTTEMMED             j OTHER q$powyl                                                 33 77     *UPTLRf D WELL                 CRITICALITY CONTROL + 4 MOUR LOGGING SOURCf                 (ButitTIN 9101) 3g ty     IRRt TRif vaSL( W(LL                                                       {
FIRf / E *PLOSiON TRANSPORTATf0N EVENT FOREIGN EVENT 36 33 MIS ADVINISTRA TION 7012 CRITICALITY / SNM LOST INFORMATION ONLY OTHER {$psCd l 36 83 shAADe ATOR EVENT 70 62 TwtF,AL s aTTEMMED j
CRITICAUTV CONTROL + 24 MOUR                 j LOG 0 LNG SOURCE               ISULLEIIN 9101)
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              ' ONLY UNDtR OLD 1991 ORESER                                         A0 26     Y AiUNG5/ waste CAM           orMER NoN.CFR REQuimtMENT FaltuRE NOTIFICAT4ONS TES         NO       Wi.L DE   ANYTHING ONU$UAL On                       VF5 ilmasa amwn NRC REGION'                                                   g      NOT UNDER$70007                           NO I
OTHER q$powyl 33 77
STATit                                             a                                                           'E          I DoD ALL SYSTEM 1 FUNCTION LOCAL 7                                                             AS REQu'*t :
*UPTLRf D WELL CRITICALITY CONTROL + 4 MOUR LOGGING SOURCf (ButitTIN 9101)
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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
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.
* Date of reporting to NRC Operation Center. Defect was evaluated under SPC Condition Report 6565 initiated March 2,1998.
Duty Officer:                                                                                 Report #
Duty Officer:
NRC FORM 361 All1/943 I                                 ,}}
Report #
NRC FORM 361 All1/943 I
,}}

Latest revision as of 03:05, 11 December 2024

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  Constellation icon.png
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)
v • d • e


Text

I Sep-17 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.

O "l

k'v

~

9909240167 980917 PDR ADOCK 05000265 s

PDR

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 FABRICATION & SCRAP RECOVERY EVENT TIME:

12 : 00 [PDT]

COMMERICAL LWR FUEL LAST UPDATE DATE:

09/17/98 CITY: RICHLAND REGION: 4 COUNTY: BENTON STATE: WA NOTIFICATIONS 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 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 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 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 TRANS7ENT 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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Sep,-17-99 15:20 SPC-ND RA/ NAM 509+375+8775 P.01 e

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l-NRC FORM 361 A U S NUCLEAR RtGULATORY COMMf 5510N LICENSE NUMeER 3

111/941 FUEL CYCLE AND MATERIALS SN C 227 EVENT NOTIFICATION WORKSHEET fN' 7

REPORT TIME FACluTV OR CRGAN'IATION NAME CfjALLt2 CALLSACE TELEPNQNt

/ p) g rf4AyQ NuMstR.

U SIEMENS POWER CORPORATION NUC. Div.

H. D. Curet

($091375-8563 EvthT TIME gygNy pArg LOCAT ON 08 tytNT I NCLUDE COUNIV AN0 51ATtr PORTION OF PLANT AFFtCYg0 N/A 9 / 17 / 98 RiChland. Benton County, WA N/A tVENT CLA5$lFICATsON EVINT TYPES INCIDENT REPORT $

(30.52. 40 60. 70 501 GENERAL EMERGENCY

  • X FUEL CYCLE 20 2201 LC$$ TMEFT to TEC Vt ACTION Siff AREA fMtRGENCY ME DICALJACA DEM.C 20 2202 ACTUAL /THRf ATENED UNPLANNEO gg OVERf xPOSURE CONTAMINATION ALtRI TRANSPCRT& TION 20 2202 "O IV AL#TM'I'II"'I D SAFETY (QUIPMtNT W@

RfLtASE FAILURE NO F ATION OF UNUSUAL I

WA$TF MANAGEMENT X

21 21 N NCO PLI ANC E WT C A NAT N s

INCIDENT REPORT IkOUSTR!As./COMMf RCIAL 26 73 FITNESS FOR Ou17 tta 44)

FIRf / E *PLOSiON TRANSPORTATf0N EVENT FOREIGN EVENT 36 33 MIS ADVINISTRA TION 7012 CRITICALITY / SNM LOST INFORMATION ONLY OTHER {$psCd l 36 83 shAADe ATOR EVENT 70 62 TwtF,AL s aTTEMMED j

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OTHER q$powyl 33 77

  • UPTLRf D WELL CRITICALITY CONTROL + 4 MOUR LOGGING SOURCf (ButitTIN 9101)

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3g ty IRRt TRif vaSL( W(LL CRITICAUTV CONTROL + 24 MOUR j

LOG 0 LNG SOURCE ISULLEIIN 9101)

' ONLY UNDtR OLD 1991 ORESER A0 26 Y AiUNG5/ waste CAM orMER NoN.CFR REQuimtMENT FaltuRE NOTIFICAT4ONS TES NO Wi.L DE ANYTHING ONU$UAL On VF5 ilmasa amwn NRC REGION' NOT UNDER$70007 NO g

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g NO EVENT DESCRIPTION (Continue on separate sheet if necessary)

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

,

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