ML18064A864
| ML18064A864 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/17/1995 |
| From: | Haas K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9508240078 | |
| Download: ML18064A864 (4) | |
Text
consumers Power POWERING MICHIGAN'S PROGRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 August 17, 1995 Nuclear Regulatory Commission Document Crintrol Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT RESPONSE TO NRC GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 This letter provides the Consumers Power Company 90 day response to Generic Letter 92-01, Revision 1, Supplement 1 for the Palisades reactor vessel.
CPCo submitted the available information on the Palisades reactor vessel beltline materials in our response to Generic Letter 92-01, Revision 1 dated July 3, 1992 and in our PTS submittals of December 28, 1994 and January 16, 1995.
We took the following actions to acquire that information:
I.
Reviewed fabrication records supplied by Combustion Engineering (CE) in 1983.
- 2.
Reviewed the results of an All Consulting Inc. search of their database and the Power Reactor Embrittlement Data Base~
- 3.
Used copper measurements provided by Lukens Steel that were recorded in their logbooks, but were not on the material certificates.
- 4.
Reviewed ABB/CE's chemical logbooks in Chattanooga.
- 5.
Reviewed Generic Letter 92-01 submittals from other plants.
- 6.
Contacted other Utilities to confirm the applicability of reported data and to share information.
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- 7.
Performed a comprehensi.ve review of weld fabrication processes.
- 8.
Reviewed reactor vessel surveillance programs and capsule analysis reports from other utilities.
- 9.
Searched Westinghouse material archives and records.
- 10.
Chemically analyzed welds from the Palisades retired steam generators and physically tested them for fracture toughness.
- 11.
Reviewed the NRC Reactor Vessel Integrity Database.
To the best of our knowledge, CPCo has obtained and reviewed all applicable information on the fabrication of the Palisades reactor vessel (RV) beltline materials. The information having the most potential for change is the best estimate chemistry for each of the beltline weld materials. Nonetheless, because of the relatively large number of chemical measurements already available on welds fabricated with the same weld wire heat numbers as the welds in the Palisades RV beltline, it is not expected that any additional measurements found in the future will substant i a 11 y change the existing best estimate chemistry yalues.
However, since the best estimate chemistry value is influenced by each measurement, and the subject material is located in other vessels and surveillance programs, we plan to continue to periodically review the surveillance program reports.of Palisades' "sister" reactor vessels (those reactor vessels at other plants that have material in their surveillance programs from the same heat as material in the Palisades RV beltllne) for additional chemical analyses.
CPCo is also attempting to maintain an open dialogue with other.vessel owners in order to remain cognizant of any adverse material trends or conditions.
2 CPCo plans to review the more recent surveillance reports from plants known to have surveillance material fabricated from the same weld wire heat numbers as the Palisades reactor vessel beltline welds~ CPCo also intends to promote at least one "sister" vessel meeting with other utilities that have reactor vessel welds fabricated from the same weld*wire heat numbers as the Palisades reactor vessel beltline welds for the purpose of sharing the available information.
CPCo will provi.de an update of the best estimate chemistry for all the reactor vessel beltline welds as part of our final response to this generic letter.
At that time we will include the results of additional chemical analysis performed on the weld material which was included in the Palisades reactor
- vessel supplemental surveillance program {those surveillance capsules which were installed during the 1995 refueling outage) and the results from any previously unreviewed surveillance reports. Also at that time, we will update the best esti.mate chemistry for welds fabricated with weld wire heat numbers
- 348009 and 27204 to reflect weighting the measurements in accordance with the fabrication process and test locations.
SUMMARY
OF COMMITMENTS There are no new commitments in this submittal because the actions described above are required to be included in the 6~month response to Generic Letter 92-01, Revision 1, Supplement 1.
I Kurt M. Haas Plant Safety and Licensing Director CC. Administrator, Region Ill, USNRC NRC Resident Inspector - Palisades Project Manager, NRR, USNRC 3
CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this 90-day response to Generic Letter 92-01, Revision 1, Supplement 1, are truthful and complete.
By Thorn~~
Plant General Manager
)1 ~
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Sworn and slibscri bed to before me this ___.__...;..__ day of ~
Alora M. Davis, Notary Public Berrien County, Michigan (Acting in Van Buren County, Michigan)
My commission expires August 26, 1999 1995.
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