ML033280519
| ML033280519 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Perry, Fermi, Grand Gulf, Limerick, River Bend, Clinton  |
| Issue date: | 11/18/2003 |
| From: | Post J General Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| MFN 03-045 | |
| Download: ML033280519 (6) | |
Text
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11/18/2003 U.S. NuclearRegulatory Commission Operations CenterEvent Report Page I General Information or Other (PAR) Event# 40005 Rep Org: GENERAL ELECTRIC COMPANY Notification Date I Time: 07/18/2003 12:13 (EDT)
Supplier: GENERAL ELECTRIC COMPANY Event Date I Time: 07/18/2003 (PDT)
Last Modification: 11/18/2003 Region: 4 Docket #:
City: SANJOSE Agreement State: Yes County: License #:
State: CA NRC Notified by: JASON POST Notifications: JACK FOSTER NRR HQ Ops Officer: STEVE SANDIN ANIELLO DELLA GRECA R1 Emergency Class: NON EMERGENCY JOHN MADERA R3 10 CFR Section: LINDA SMITH R4 21.21 UNSPECIFIED PARAGRAPH PART 21 REPORT INVOLVING IMPACT OF FUEL CHANNEL BOW ON CONTROL ROD BLADES The following is a portion of text received as a fax:
"July 18, 2003 "MFN 03-045
Subject:
60 Day Interim Notification: Impact of Fuel Channel Bow on Control Rod Blade Deviations
Reference:
Letter from Jason Post (GENE) to USNRC, 'Interim Surveillance Program for Fuel Channel Bow Monitoring', MFN 03-030 Revision 1, April 30, 2003 "This communication is to inform you that GE Nuclear Energy (GENE) has been evaluating a potentially reportable condition (PRC) on the impact of fuel channel bow on control rod blades. The original channel bow evaluation for increased fuel channel - control rod blade interference did not consider previously evaluated deviations in the control rod blade. Channel bow can cause increased deflection and stresses in control rod blades, which must be considered in control rod blade deviation evaluations. The PRC evaluation is limited to control rod blades delivered to those plants identified in the referenced letter, where an interim surveillance plan for channel bow monitoring is recommended, because those are the only plants where there is a concern about increased fuel channel - control rod blade interference.
"As described in the referenced letter, it was determined that BWR/6 and BWR/4 & 5 C-lattice plants with Global Nuclear Fuel (GNF) thick/thin channels potentially have increased channel bow that can cause fuel channel control rod blade interference. An interim surveillance program was provided to augment the surveillance requirements in the plant Technical Specifications until other actions, which mitigate or limit the potential for control rod - fuel channel interference due to channel bow can be identified and implemented. This surveillance program provides early indication of potentially degraded operational performance and assurance that action is taken before reaching excessive levels of control rod interference. This surveillance plan is limited to BWR/6 and BWR/4&5 C-
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1111812003 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page 2 General Information or Other (PAR) Event# 40005 lattice plants with GNF thick/thin channels and GENE control rods. There have been no indications of excessive interference on BWR/2, 3 and 4 D-lattice plants, and as a result, they are excluded from the interim surveillance program.
"The PRC evaluation was initiated by GENE on May 19, 2003. GENE will not have completed the evaluation by July 18, 2003, when the 60 day evaluation period expires. Therefore, GENE is submitting this 60 Day Interim Notification under 10CFR21.21 (a)(2) to inform the NRC that we are working on the issue, and to commit to report the results of the evaluation no later than September 23, 2003."
GE Nuclear Energy has identified the following as affected plants: Clinton, Nine Mile Point 2, Fermi 2, Grand Gulf, River Bend, Limerick 1 & 2 and Perry 1.
- UPDATE ON 9/24/03 AT 0055 FROM POST TO LAURA*****
GE submitted its 60 day update letter which indicated no change from previously submitted information.
- *
- UPDATE ON 11/18/03 @ 2115 BY JASON POST TO GOULD * *
- This communication is to inform you that GE Nuclear Energy (GENE) has completed the evaluation of the potentially reportable condition (PRC) identified in References 2 and 3 and has concluded that it is NOT a Reportable Condition under 10CFR21.
Channel bow can cause increased deflection and stresses in control rod blades. The impact of channel bow on as-designed control rod blades was considered when the surveillance program identified in Reference 1 was developed_ However, the evaluation did not consider known control rod blade deviations from as-designed conditions that had previously been addressed. The evaluation to determine the impact of channel bow on control rod blade deviations, as reported to the NRC in References 2 and 3, has now been completed. The evaluation concluded that the increased loads from channel bow do not impact the structural integrity of control rods with known deviations from as-designed conditions. Therefore, it does not produce a significant safety hazard or lead to violation of a technical specification safety limit.
As described in the Reference 1 letter, it was determined that BWR/6 and BWR/4 & 5 C-lattice plants with Global Nuclear Fuel (GNF) thick/thin channels are potentially susceptible to increased channel bow that can cause increased fuel channel - control rod blade interference. A surveillance program is recommended per Reference 1 for the potentially susceptible 8 plants listed above. This evaluation examines known deviations from the as-designed condition for original equipment manufactured (OEM) control rod blades and for "DuraLife" and "Marathon" replacement blades in the potentially susceptible plants.
The PRC evaluation was initiated by GENE on May 19, 2003. GENE reported the results of the evaluation for OEM blades and "DuraLife" replacement blades in Reference 3. GENE has now completed the evaluation applicable to "Marathon" replacement blades. These evaluations indicate that there is no change from the previous information provided in Reference 1. Therefore, GENE is submitting this Final Notification to inform the NRC that the evaluations have been completed, and to report the GENE conclusion that this is NOT a Reportable Condition per 10CFR21.
References:
- 1. Letter from Jason Post (GENE) to USNRC, "Interim Surveillance Program for Fuel Channel Bow Monitoring",
MFN 03-030 Revision 1, April 30, 2003
- 2. Letter from Jason Post (GENE) to USNRC, "60 Day Interim Notification: Impact of Fuel Channel Bow on Control
11/18/2003 U.S. NuclearRegulatory Commission OperationsCenter Event Report Paze 3 General Information or Other (PAR) Event# 40005 Rod Blade Deviations," MFN 03-045, July 18, 2003
- 3. Letter from Jason Post (GENE) to USNRC, "60 Day Interim Notification: Impact of Fuel Channel Bow on Control Rod Blade Deviations," MFN 03-103, September 23, 2003 Notified Reg 1 RDO(Rogge), Reg 3 RDO(Lipa), Reg4 RDO(Kennedy), and NRR(Foster)
See related events #39634 and 39806
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NOV 18 03 07:01PM GE UCLEPR EERGY/408 925 1490 P.1/3 GENuclearEnergy General Eleetric CoMpovy 175 CurtnerAve., San Jose, C 95125 NovemBer 18, 2003 MFN 03-146 Document Control Desk United States Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738
Subject:
Final Report Notification - Impact of Fuel Channel Bow on Control Rod Blade Deviations
References:
- 1. Letter from Jason Post (GENE) to USNRC, "Interim Surveillance Program for Fuel Channel Bow Monitoring", MFN 03-030 Revision 1, April 30,2003
- 2. Letter from Jason Post (GENE) to USNRC, "60 Day Interim Notification: Impact of Fuel Channel Bow on Control Rod Blade Deviations," MFN 03-045, July 18, 2003
- 3. Letter from Jason Post (GENE) to USNRC, "60 Day Interim Notification: Impact of Fuel Channel Bow on Control Rod Blade Deviations," NIFN 03-103, September 23, 2003 This communication is to inform you that GE Nuclear Energy (GENE) has completed the evaluation of the potentially reportable condition (PRC) identified in References 2 and 3 and has concluded that it is NOT a Reportable Condition under IOCFR21.
Channel bow can cause increased deflection and stresses in control rod blades. The impact of channel bow on as-designed control rod blades was considered when the surveillance program identified in Reference 1 was developed. However, the evaluation did not consider known control rod blade deviations from as-designed conditions that had previously been addressed. The evaluation to determine the the impact of channel bow on control rod blade deviations, as reported to the NRC in References 2 and 3, has now been completed. The evaluation concluded that the increased loads from channel bow do not impact the structural integrity of control rods with known deviations from as-designed conditions. Therefore, it does not produce a significant safety hazard or lead to violation of a technical specification safety limit.
As described in the Reference 1 letter, it was determined that BWRJ6 and BWR/4 & 5 C-lattice plants with Global Nuclear Fuel (GNF) thick/thin channels are potentially susceptable to increased channel bow that can cause increased fuel channel - control rod blade interference. A surveillance program is Tecommended per Reference 1 for the 11/18/2nn TTR 2n:fR FTT/RX Nn 2371 MM00
NOV 18 '03 07:01PM GE NUCLEAR ENERGY/408 925 1490 P.2/3 MFN 03-146 November 18, 2003 potentially susceptable plants listed in Attachment 1. This evaluation examines known deviations from the as-designed condition for original equipment manufactured (OEM) control rod blades and for DuraLifeTm and Marathon replacement blades in the potentially susceptable plants.
The PRC evaluation was initiated by GENE on May 19, 2003. GENE reported the results of the evaluation for OEM blades and DmraLife replacement blades in Reference 3. GENE has now completed the evaluation applicable to MarathonTM replacement blades. These evaluations indicate that there is no change from the previous information provided in Reference 1. Therefore, GENE is submitting this Final Notification to inform the NRC that the evaluations have been completed, and to report the GENE conclusion that this is NOT a Reportble Condition per I0CFR21.
Please contact me if you have any questions on this information at (408) 925-5362.
Sincerely, Jason. S. Post, Manager Engineering Quality and Safety Evaluations
Attachment:
- 1. Plants Recommended for Surveillance Program cc: S. D. Alexander (NRC-NRR/DISP/PSIB) Mail Stop 6 F2 J. F. Foster (NRC-NR/DRIP/RORP) Mail Stop 12 3:2 A. B. Wang (NRC-NRRDLPM/LPD4) Mail Stop 7 El J. F. Klapproth (GENE)
H. J. Neems (GENE)
G. B. Stramback (GENE)
B. J. Erbes (GENE)
PRC File 2
NOV 18 '03 07:02PM GE NUCLEAR ENERGY/408 925 490 P. 3/3 MFN 03-146 November 18, 2003 ATACH NT 1 Plants Recommended for Surveillance Program Utility Plant x AtnerGen Energy Co. Clinton AmerGen Energy Co. Oyster Creek Carolina Power & Light Co. Brunswick 1 Carolina Power & Light Co. Brunswick 2 Constellation Nuclear Nine Mile Point 1 x Constellation Nuclear. Nine Mile Point 2 x Detroit Edison Co. Fermi 2 Dominion Generation Millstone 1 Energy Northwest Columbia Entergy Nuclear Northeast FitzPatrick Entergy Nuclear Northeast Pilgrim x Entergy Operations, Inc. Grand Gulf x Entergy Operations, Xnc. River Bend Entcrgy Nuclear Northeast Vermont Yankee Exelon Generation Co. CRIT Facility Exelon Generation Co. Dresden 2 Exelon Generation Co. Dresden 3 Exelon Generation Co. LaSalle 1 Exelon Generation Co. LaSalle 2 x Exclon Generation Co. Limerick I x Exelon Generation Co. Limerick 2 Exelon Generation Co. Peach Bottom 2 Exelon Generation Co. Peach Bottom 3 Exelon Generation Co. Quad Cities I Exelon Generation Co. Quad Cities 2 x FirstEnergy Nuclear Operating Co. Perry 1 Nebraska Public Power District Cooper Nuclear Management Co. Duane Arnold Nuclear Management Co. Monticello Pooled Equipment Inventory Co. P1M PPL Susquehanna LLC. Susquebanna I PPL Susquehanna LC Susquehanna 2 Public Service Electric & Gas Co. Hope Creek Southem Nuclear Operating Co. Hatch 1 Southern Nuclear Operating Co. Hatc 2 Tennessee Valley Authority Browns Ferry I Tennessee Valley Authority Browns Ferry 2 Tennessee Valley Authority Browns Ferry 3 3
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