ML042780496
| ML042780496 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Fermi, Cooper, FitzPatrick  |
| Issue date: | 09/30/2004 |
| From: | Post J General Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 40982, MFN 04-108 | |
| Download: ML042780496 (6) | |
Text
0913012004 U.S. NuclearRegulatory Commission OperationsCenter Event Report FareeI General Information or Other (PAR) Event# 40982 Rep Org: GENERAL ELECTRIC COMPANY Notification Date I Time: 08/2412004 17:36 (EDT)
Supplier: GENERAL ELECTRIC COMPANY Event Date I Time: 08/24/2004 (EDT)
Last Modification: 09130/2004 Region: 1 Docket #:
City: WILMINGTON Agreement State: Yes County: License #:
State: NC NRC Notified by: JASON S. POST Notifications: EUGENE COBEY R1 HQ Ops Officer: MIKE RIPLEY JOEL MUNDAY R2 Emergency Class: NON EMERGENCY ERIC DUNCAN R3 10 CFR Section: WILLIAM JOHNSON R4 21.21 UNSPECIFIED PARAGRAPH VERN HODGE NRR PART 21 REPORTABLE CONDITION AND 60-DAY INTERIM REPORT NOTIFICATION: NON-CONSERVATIVE SAFETY LIMIT MINIMUM CRITICAL POWER RATIO Global Nuclear Fuel (GNF) and GE Nuclear Energy (GENE) have determined that the current GNF process for determination of the Safety Limit Minimum Critical Power Ratio (SLMCPR) can result in a non-conservative SLMCPR. GENE has historically used a non-conservative SLMCPR impact of 0.01 as the threshold for reportability under I OCFR21. A preliminary screening evaluation has been completed for all plants operating with a SLMCPR calculated by GNF to determine those that have a nonconservative impact of 0.01 or greater. Verification has been completed for those plants that the screen showed to have a non-conservative SLMCPR impact of 0.01 or greater.
Verification has not been completed for the plants that the screen showed had an impact of less than 0.01 or were unaffected, thus requiring a 60-Day Interim Report notification pending verification completion.
The plants for which GNF calculates the SLMCPR are identified [below]. Those plants for which the preliminary screen indicated that the current SLMCPR is unaffected are identified as a 60-Day Interim Report. Upon completion of verification (assuming the results of the screen are confirmed) the status of these plants will be changed to Not Reportable. GENE will provide a follow-up report to the NRC by September 29, 2004. The plants for which the current SLMCPR is non-conservative by 0.01 or greater are identified as a Reportable Condition under 10CFR21.21(d). These plants will take action to address the Reportable Condition.
GNF has notified all plants that have been confirmed to be affected. The plants that have a non-conservative SLMCPR for current plant operation will take action to mitigate the potential impact. Depending on the specific circumstances, mitigating actions to protect the SLMCPR may include increasing the OLMCPR to assure compliance with the low flow calculated SLMCPR. In some cases sufficient conservatism may exist in the OLMCPR at low flow to bound the increased SLMCPR. Each affected plant will notify the NRC and take appropriate action iftheir Technical Specifications are affected.
There are no actions necessary for the plants that are unaffected pending completion of verification. If,in the course of verification, GNF determines that there is an impact, the affected utility will be notified immediately. GNF
09/30/2004 U.S. NuclearRegulatory Commission OperationsCenter Event Report Paee 2 General Information or Other (PAR) Event# 40982 will complete the verification and GENE, will provide a follow-up letter to the NRC by September 29, 2004.
Affected and 60-Day Interim Notification Plants:
60-Day Interim Report: Clinton, Oyster Creek, Brunswick 1, Brunswick 2, Nine Mile Point 2, Fitzpatrick (60-Day interim report for current operation, Reportable Condition for SLMCPR licensing submittal), Pilgrim, Vermont Yankee, Dresden 2, Dresden 3, LaSalle 1, LaSalle 2, Limerick 1, Limerick 2, Peach Bottom 2, Peach Bottom 3, Quad Cities 1, Quad Cities 2, Perry 1, Duane Arnold, Monticello, Hope Creek, Hatch 1, Hatch 2, Browns Ferry 2 Reportable Condition: Nine Mile Point 1, Fermi 2, Fitzpatrick (60-Day interim report for current operation, Reportable Condition for SLMCPR licensing submittal), Cooper.
- *
- UPDATE FROM JASON POST (VIA FAX) TO CROUCH @ 2354 HRS. EST ON 09/29/04 ***
In part, the update reads:
"The evaluation for the potentially unaffected plants has now been completed. The results of the screening calculation have been confirmed: this is not a reportable condition for the plants that were previously identified as a 60-Day Interim Report notification in MFN 04-081" (See above).
Notified RIDO(Rogge), R2DO(Lesser), R3DO(Kozak), R4DO(Howell) and NRREO(Hodges).
Sep-30-2004 12:03am From-GNF NFE +9106756614 T-065 P.001 /004 F-539 I r EM Global Nuclear Fuel AJoint Vsnutire of CEToshibe,& Hitchl Global Nuclear Fuel - Americas, LLC Fuel Engineering Services P.O. Box 780, Castle Hayne Road Wilmington, NC 28401 To: L). 5 Po Ca d 4- Re I ecCoyJ Cain sso- h P .
Phone #: FAX It: __________________S From: tAa- k Q% - ~4 Jqs P6stl Phone It: (910) 675- G6/ S or 8*292- 4pG /,S FAX#: (910) 675-6614 or 8*292-6614 Remarks:
El Urgent El For your review E3 Reply ASAP 5l Please comment 09/29/2004 WED 23:54 [TX/RX NO 7778] E001
SoP-30-2004 12:03am From-GNF NFE +9106756614 T-065 P.002/004 F-539 GE NuclearEnergy OCnera1lEktcricCompany 3901 CadcHRyne Rooad Wilmingmon. NC28401 September 29, 2004 MFN 04-108 U.S. Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852-2738 Attention: Chief, Information Management Branch Program Management Policy Development and Analysis Staff
Subject:
Part 21 Final IReport: Non-conservative SLMCPR
Reference:
GENE letter, 'Tart 21 Reportable Condition and 60-Day Interim Report Notification: Non-conservative SLMCPR," MFN 04-081, August 24, 2004 Global Nuclear Fuel (GNF) and GE Nuclear Energy (GENE) previously notified the NRC in the reference letter that the current GNF process for determination of the Safety Limit Minimum Critical Power Ratio (SLMCPR) can result in a non-conservative SLMCPR. A preliminary screening calculation had been completed to identify the plants that were potentially affected. The evaluation was completed for the plants that had been determined to be potentially affected and these plants were identified as a reportable condition under IOCFR21.21(d) in MFN 04-081. The evaluation was not completed for the plants that had been determined to be potentially unaffected and these plants were identified as a 60-Day Interim Report notification under IOCFR21.21(a)(2) in MFN 04-081.
The evaluation for the potentially unaffected plants has now been completed. The results of the screening calculation have been confirmed: this is not a reportable condition for the plants that were previously identified as a 60-Day Interim Report notification in MFN 04-081.
GENE has historically used a non-conservative SLMCPR impact of 0.01 as the threshold for reporrability under IOCFR21. The identified non-conservative SLMCPR change only slightly exceeded the threshold for a Reportable Condition and would not lead to a substantial safety hazard due to the large margin to fuel failure associated with the SLMCPR and the multiple automatic and passive protection features of a 1B3W The plants for which GNF calculates the SLMCPR are identified in Attachment 1. Those plants for which the current SLMCPR is conservative are identified as Not Reportable.
09/29/2004 WED 23:54 [TX/RX NO 77781 [j 002
Sep-30-2004 12:03am From-GNF NFE +9106756614 T-065 P.003/004 F-539 September 29,2004 MFN 04-108 The plants for which the current SLMCPR is non-conservative by 0.01 or greater were previously identified as a Reportable Condition under 10CFR21.21(d) in MFN 04-081.
Discussion During performance of SLMCPR calculations for an extended operating domain condition, GNF discovered an apparent flow impact where a lower flow condition at rated power had a more limiting SLMCPR than the rated flow condition. Current procedures specify that the SLMCPR be calculated on the upper boundary of the power/flow operating map only at 100% power/100% flow (ratedP/ratedl:). The SLMCPR is calculated at 3 operating points in the cycle: (1) Beginning of Cycle (BOO),
(2) Peak Hot Excess (PDE), and (3) End of Cycle (EOC) at rated P/rated F conditions.
The SLMCPR calculation is dependent upon many fuel and cycle parameters and the most limiting SLMCPR may occur at any of the analyzed points, The SLMCPR is the most limiting bundle MCPR from these calculations that corresponds to 0.1% of fuel rods in the core being susceptible to boiling transition due to the postulated occurrence of the limiting Abnormal Operating Occurrence (AOO) event.
In the instances where this concern was discovered, the control rod patterns used at the off-rated flow/rated power condition created a more limiting bundle-by-bundle MCPR distribution than the control rod patterns used at rated power/rated flow, even though both control rod patterns met the criterion defined in the SLMCPR calculation process, and it produced a more limiting SLMCPR.
GENE/GNF previously notified the affected plants as identified in MEN 04-081, August 24, 2004. There are no actions necessary for the plants Thar are confirmed to be unaffected as identified in Attachment 1.
If you have any questions, please call me at (910) 675-6608.
Sincerely, Jason. S. Post, Manager Engineering Quality & Safety Evaluations cc: S. D. Alexander (NRC-NRXUDIPM/IPSB) Mail Stop 6 F2 M. B. Fields (NRC-NRRJDLPMJLPD4) Mail Stop 7 El C. V. Hodge (NRC-NRR/DIPM/IROB) Mail Stop 12 H2 J. F. 1Klapproth (GENE)
H. J. Neerns (GENE)
L. M. Quintana (GENE)
T'. Rumsey (GENE)
PRC File 2
09/29/2004 WED 23:54 [TX/RX NO 7778] E6003
Sep-30-2004 12:03am From-GNF NFE +910ST56614 T-065 P.004/004 F-539 September 29, 2004 MFN 04-108 Affachment 1 - Plants Previously Identified in MFN04-081 Not Reportnhle Utilitv Plant Rcpornable Conditinn (per lNU04-OR1) x AmerGen Energy Co. Clinton x ArnerGen Energy Co. Oyster Creek x Carolina Power & Light Co. Brunswick I x Carolina Power & Light Co. Brunswick 2 x Constellation Nuclear Nino Mile Point I x Constellation Nuclear. Nine Mile Point 2 x Detroit Edison Co. Fermi2 Dominion Generation Millstone 1i)
Energy Northwest Columbia Entergy Nuclear Northeast TFzPatrick x(2 Entergy Nuclear Northeast Pilgrim Entergy Operations, Inc. Grand Gulf x EnTergy Operations, Inc.- River Bend Entergy Nuclear Northeast Vermont Yankee x Exelon Generation Co. CRITFacility Exelon Generation Co. Dresden 2 x E~xelon Generation Co. Dresden 3 x Exelon Generation Co. LaSalle 1 x Exelon Generation Co. LaSalle 2 x Exelon Generation Co. Limerick I x Exelon Generation Co. Limerick 2 x Exelon Generation Co. Peach Bottom 2 x Exelon Generation Co. Peach Bottom 3 x Exelon Generation Co. Quad Cities I x Exclon Generation Co. Quad Cities 2 x FirstEnergy Nuclear Operating Co. Perry 1 x x Nebraska Public Power District Cooper Nuclear Management Co. Duane Arnold x Nuclear Management Co. Monticello Pooled Equipment Inventory Co. PFM x PPL Susquehanna LLC. Susquehanna I PPL Susquehanna LLC Susquehanna 2 PSEG Nuclear Hope Creek x Southern Nuclear Operating Co. Hatch I x Southern Nuclear Operating Co. Hatch 2 x Tennessee Valley Authority BrownsFerry I (1 Tennessee Valley Authority Browns Ferry 2 Tennessee Valley Authority Browns Ftrry 3 Notes:
- 1. Plant is in an extended shatdown
- 2. Not reportable for current operation, Reportable Condition for SLMCPR licensing submittal 3
09/29/2004 WED 23:54 [TX/RX NO 7778] I0j004