ML032060429
| ML032060429 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Perry, Fermi, Oyster Creek, Hope Creek, Grand Gulf, Cooper, Pilgrim, Susquehanna, Columbia, Brunswick, Limerick, River Bend, Vermont Yankee, Duane Arnold, Clinton, Quad Cities, FitzPatrick, LaSalle (DPR-016, DPR-019, DPR-021, DPR-022, DPR-025, DPR-028, DPR-029, DPR-030, DPR-033, DPR-035, DPR-044, DPR-046, DPR-049, DPR-052, DPR-056, DPR-057, DPR-059, DPR-062, DPR-063, DPR-068, DPR-071, NPF-005, NPF-011, NPF-014, NPF-018, NPF-021, NPF-022, NPF-029, NPF-037, NPF-039, NPF-043, NPF-047, NPF-057, NPF-058, NPF-062, NPF-066, NPF-069, NPF-085) |
| Issue date: | 07/21/2003 |
| From: | Nicholson B Thermo Electron Corp |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML032060429 (9) | |
Text
Jul 22 03 05: 19p THERMO 713 272 2258 p.
2 ELECTRON CORPORATION Flow Systems 713) 272-0404 9303W. Sam Houston Parkway S.
Fax: (713] 272-2272 Houston, TX 77099-5298 wwwt.hermoflowsystems.corn TESIS A 10CFR PART 21 NOTIFICATION Contacts:
Barry Nicholson Director of Quality Assurance Barry Hutchison Technical Support Leader July 21, 2003 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Thermo Westronics Model 2100C Series Recorders This letter is notification of a possible defect associated with Thermo Westronics Series 2100C recorders. The Series 21 OC is a DIN size programmable chart recorder utilized in control room applications of Nuclear Power Plants. The recorders in question were manufactured under the Thermo Westronics OCFR50 Appendix B Quality Program between August 2002 and January 2003.
On or about May 30, 2003, Thermo Electron determined that a random reset anomaly could possibly occur on the Series 21 OC recorder. This anomaly surfaced during the manufacture of three (3) commercial grade Series 2100 recorders. When the reset occurs, the recorder must be re-initialized to resume normal fumction.
The root cause of the anomaly has been traced to a timing issue between the CPU Printed Circuit Board Assembly (PCBA) and the Memory Module. A 27C256 EPROM, used as a decoder on the Memory Module, has changed manufacturers several times during the life of this product. The EPROM as produced by the original manufacturer is no longer available.
Newer versions of this 27C256 EPROM typically fimction at faster speeds. The faster chip speed can cause a delay in the transition from "send" to "receive" on the CPU Module and thereby result in the reset. This reset event is random and does not occur on every recorder.
After engineering evaluation, Thermo Electron has incorporated a modification to the CPU PCBA to ensure compatibility with the faster EPROM on the Memory Module. This modification eliminates the timing delay and subsequent possibility of the reset. Future shipments of this CPU Module shall incorporate this modification.
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Jul 22 03 05: 20p THERMO 713 272 2258 p.3 ELECTRON CORPORATION To ensure compatibility on previously installed recorders, the Memory Module shall only be offered as part of a kit that includes the newer version CPU PCBA.
The scope of this notification includes ten (10) Series 2100C safety related recorders, all of which were thoroughly tested and did not exhibit this reset at the time of shipment. However, since it is not possible to determine the exact manufacture date of the 27C256 EPROM used on these recorders, this notification is being issued.
The following is a list of the safety related recorders included in the scope of this notification including Serial Number, Ship Date, Customer, Location Shipped To, and Purchase Order.
Serial Number Ship Date Customer Shipped To Purchase Order 2100C1824 2100C1827 2100C1828 2100C1829 2100C1830 2100C1831 2100Cl832 2100C1833 2100C1834 2100C1835 12/04/02 01/08/03 02/19/03 08/16/02 08/16/02 01/25/03 01/25/03 01/28/03 01/28/03 01/28/03 Corn Fed De Electricidad Dominion Nuclear Dominion Nuclear Duke Power Co.
Duke Power Co.
Duke Power Co.
Duke Power Co.
Duke Power Co.
Duke Power Co.
Duke Power Co.
Laguna Verde, Mex.
Millstone Site Millstone Site Catawba Site Catawba Site Catawba Site Catawba Site McGuire Site McGuire Site McGuire Site 01-2-23014-CNP 45138755 Rev. 4 45138755 Rev. 4 NE 5462 001 NE 5462 001 NE 5462 001 NE 5462 001 NE 5703 001 NE 5703 001 NE 5703 001 Thermo Electron shall notify the above listed customers and make arrangements to implement the design modification, either by rework at the Thermo Electron - Houston facility, or by providing replacement kits to the customer site. It is estimated that rework associated with the design modification should be completed within sixty (60) days, or as soon as Thermo Electron has been contacted by the identified customers.
Should you have any questions regarding the above, please contact the undersigned.
Sincerely, Barry Nicholson Director of Quality Assurance cc: Larry Quick n7/99/9nnA
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0712212003 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze General Information or Other (PAR)
Event#
40011 Rep Org: THERMO ELECTRON CORPORATION Notification Date ITime: 07/22/2003 18:13 (EDT)
Supplier: THERMO ELECTRON CORPORTATION Event Date Time: 05/30/2003 (CDT)
Last Modification: 07/22/2003 Region:
4 Docket #:
City: HOUSTON Agreement State: Yes County:
License #:
State: TX NRC Notified by: BARRY NICHOLSON Notifications: DANIEL HOLODY R1 HQ Ops Officer: NATHAN SANFILIPPO ANNE BOLAND R2 Emergency Class: NON EMERGENCY KRISS KENNEDY R4 10 CFR Section:
JACK FOSTER NRR 21.21 UNSPECIFIED PARAGRAPH PART 21 NOTIFICATION DUE TO POSSIBLE DEFECT WITH THERMO WESTRONICS SERIES 2100C RECORDERS The following report was received via fax:
"July 21, 2003
Subject:
Thermo Westronics Model 2100C Series Recorders "This letter is notification of a possible defect associated with Thermo Westronics Series 2100C recorders. The Series 2100C is a DIN size programmable chart recorder utilized in control room applications of Nuclear Power Plants. The recorders in question were manufactured under the Thermo Westronics 1 OCFR50 Appendix B Quality Program between August 2002 and January 2003.
"On or about May 30, 2003, Thermo Electron determined that a random reset anomaly could possibly occur on the Series 2100C recorder. This anomaly surfaced during the manufacture of three (3) commercial grade Series 2100 recorders. When the reset occurs, the recorder must be re-initialized to resume normal function.
"The root cause of the anomaly has been traced to a timing issue between the CPU Printed Circuit Board Assembly (PCBA) and the Memory Module. A 27C256 EPROM, used as a decoder on the Memory Module, has changed manufacturers several times during the life of this product. The EPROM as produced by the original manufacturer is no longer available.
"Newer versions of this 27C256 EPROM typically function at faster speeds. The faster chip speed can cause a delay in the transition from "send" to "receive on the CPU Module and thereby result in the reset. This reset event is random and does not occur on every recorder.
"After engineering evaluation, Thermo Electron has incorporated a modification to the CPU PCBA to ensure
0712212003 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze General Information or Other (PAR)
Event#
40011 compatibility with the faster EPROM on the Memory Module. This modification eliminates the timing delay and subsequent possibility of the reset. Future shipments of this CPU Module shall incorporate this modification.
"To ensure compatibility on previously installed recorders, the Memory Module shall only be offered as part of a kit that includes the newer version CPU PCBA.
"The scope of this notification includes ten (10) Series 2100C safety related recorders, all of which were thoroughly tested and did not exhibit this reset at the time of shipment However, since it is not possible to determine the exact manufacture date of the 27C256 EPROM used on these recorders, this notification is being issued.
"Thermo Electron shall notify listed customers and make arrangements to implement the design modification, either by rework at the Thermo Electron - Houston facility, or by providing replacement kits to the customer site. It is estimated that rework associated with the design modification should be completed within sixty (60) days, or as soon as Thermo Electron has been contacted by the identified customers."
The affected sites include Laguna Verde, Mexico, Millstone, Catawba, and McGuire.
0711812003 U.S. Nuclear Regulatory Commwnission Operations Centter Event Report Pave I General Information or Other (PAR)
Event#
40005 Rep Org: GENERAL ELECTRIC COMPANY Notification Date / Time: 07/18/2003 12:13 (EDT)
Supplier: GENERAL ELECTRIC COMPANY Event Date I Time: 07/18/2003 (PDT)
Last Modification: 07/18/2003 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-
07/18/2003 U.S. Nuclear Regulator' Comnission Operations Center Event Report Pave 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
& 2 and Perry 1.
JUL D I MdY:
O1HM GL NUCLER IERGY/408 925 1490 P. 1/3 GE Nuclear Energy General Ncdric Company 175 C-innerAvc., Son Josi, CA 925 July 18, 2003 MFN 03-045 Document Control Desk United States Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738
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 ofpotentially degraded operational performance and assurance that action is taken before reaching excessive levels of control rod interference. This surveillance plan is limited to BWRI6 and BWR/4&5 C-lattice plants with GNF thick/thin channels and GENE control rods.
There have been no indications of excessive interference on BWRI2, 3 and 4 D-lattice plants, and as a result, they are excluded from the interim surveillance program.
I 07/18/2003 FRI 12:08 (TrX/RX NO 8047] Q)001
J UL CD UZ-3 vJ-L.)181-1 kpt lUt-L-tHl UlIKmbT/quo v4D 141JU Fe d/d MN 03-045 July 17, 2003 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 1 OCER21.21 (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.
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-NR'/DISP/PSIB) Mail Stop 6 F2 J. F. Foster (NRC-NR1R!DRW1/RORP) Mail Stop 12 H2 A. B. Wang (NRC-NRfDLPMLPD4) Mail Stop 7 El J. F. Yiapproth (GENE)
H. J. Neems (GENE)
G. B. Stramback (GENE)
B. I. Erbes (GENE)
PRC File 2
07/18/2003 FRI 12:08
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JUL 18 '03 09:13RM GE NUCLERR ENERGY/408 925 1490 P. 3/3 MFN 03-045 July 17, 2003 ATTACHMENT I Plants Recommended for Surveillance Program x
x x
x x
x x
x Utility AmerGen Energy Co.
AmerGen Energy Co.
Carolina Power & Light Co.
Carolina Power & Light Co.
Constellation Nuclear Constellation Nuclear.
Detroit Edison Co.
Dominion Generation Energy Northwest Entergy Nuclear Northeast Entergy Nuclear Northeast Entergy Operations, Inc.
Entergy Operations, Inc.
Entergy Nuclear Northeast Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
Exelon Generation Co.
FirstEnergy Nuclear Operating Co.
Nebraska Public Power District Nuclear Management Co.
Nuclear Management Co.
Pooled Equipment Inventory Co, PPL Susquehanna LLC.
PPL Susquehanna LLC Public Service Electric & Gas Co.
Southern Nuclear Operating Co.
Southern Nuclear Operating Co.
Tennessee Valley Authority Tennessee Valley Authority Tennessee Valley Authority Plant Clinton Oyster Creek Brunswick 1 Brunswick 2 Nine Nile Point 1 Nine Mile Point 2 Fermi 2 Millstone 1 Columbia FitzPatrick Pilgrim Grand Gulf RiverBend Vermont Yankee CRIT Facility Dresden 2 Dresden 3 LaSalle LaSalle 2 Limerick 1 Limerick 2 Peach Bottom 2 Peach Bottom 3 Quad Cities I Quad Cities 2 Perry 1 Cooper Duane Arnold Monticello PIM Susquehanna 1 Susquehan 2
Hope Creek Hatch I Hatch 2 Browns Ferry I Browns Ferry 2 Browns Ferry 3 3
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