ML18064A486
| ML18064A486 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/30/1994 |
| From: | Gamberoni M Office of Nuclear Reactor Regulation |
| To: | Haas K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TAC-M83227, NUDOCS 9412020181 | |
| Download: ML18064A486 (3) | |
Text
November 30, 1994
- Mr. Kurt M. Haas Plant Safety and Licensing Director Consumers Power Company Palisades Plant 27780 Blue Star Memorial Highway Covert, MI 49043 DISTRIBUTION
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MGamberoni PUBLIC ----
JRoe WKropp, RIII JHannon LLols CJamerson BElliot JStrosnider
SUBJECT:
PALISADES PLANT - REQUEST FOR ADDITIONAL INFORMATION RE:
COMPLIANCE WITH 10 CFR 50.61 SCREENING CRITERIA (TAC NO. M83227)
Dear Mr. Haas:
The staff is currently reviewing the information you provided in submittals of November 8, 10, and 18, 1994.
These submittals summarized the results of tests performed on weld samples from the Palisades retired steam generators and your conclusions regarding Palisades compliance with the 10 CFR 50.61 pressurized thermal shock screening criteria.
In addition you presented clarifying information at a meeting held at NRC headquarters on November 21, 1994.
We require additional information to complete our review on this subject.
The enclosed questions request both data and analysis.
We request that the data be submitted within 10 working days from the date of this letter and the analysis be submitted by January 3, 1995. This schedule has been set to ensure that a timely review is performed.
If you have any questions regarding this request, please contact me at 301-504-3024.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Docket No. 50-255 Sincerely, ORIGINAL SIGNED BY Marsha Gamberoni, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page FILENAME: G:\\WPDOCS\\PALISADE\\PAL83227.RAI OFFICE LA: PD3 l
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PM: PD3 l BC: EM~
OFFICIAL RECORD CO 026016
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PDR ADOCK 05000255 P
Mr. Kurt M. Haas Consumers Power Company cc:
Mr. Thomas J. Palmisano Plant General Manager Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 Mr. Robert A. Fenech Vice President, Nuclear Operations Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 M. I. Miller, Esquire Sidley & Austin 54th Floor One First National Plaza Chicago, Illinois 60603 Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road lisle, Illinois 60532-4351 Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 U.S. Nuclear Regulatory Commission Resident Inspector Office Palisades Plant 27782 Blue Star Memorial Highway Covert, Michigan 49043 Palisades Plant Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0. Box 30195 Lansing, Michigan 48909 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.
Washington DC 20037 Alora Davis Commitment Tracking System Coordinator Palisades Plant Consumers Power Company 27780 Blue Star Memorial Highway Covert, Michigan 49043-9530 Michigan Department of Attorney General Special Litigation Division 630 Law Building P.O. Box 30212 Lansing, Michigan 48909 November 1994
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REQUEST FOR ADDITIONAL INFORMATION FOR PALISADES PRESSURIZED THERMAL SHOCK ISSUE With regard to the following questions, provide any data requested within 10 working days and provide any assessment of the data by January 3, 1995, in order to support the staff review schedule.
I. Provide the actual time (above 500°F}, temperatures, and cooling method for stress relief of the Palisades reactor vessel axial beltline welds and the Palisades steam generators. Assess the potential effects any difference in the heat treatment could have on the unirradiated reference temperature of the steam generator and the reactor vessel beltline welds.
- 2. Compare the Charpy and drop weight data from the steam generators to the CE generic weld data base. Provide any data that demonstrates the variability of the nil ductility transition temperature (NDTT) and unirradiated reference temperature in a weld or within a heat of weld wire.
- 3. Provide a rigorous statistical evaluation of steam generator Charpy data to determine whether the data is statistically equivalent to the surveillance data from (a) the Indian Point-2 surveillance weld, (b) the Indian Point-3 surveillance weld, (c) the Robinson 2 surveillance weld, and (d) all three surveillance welds.
- 4. Provide unaged and aged Charpy data from the material thermally aged in the Palisades reactor vessel.
What is its percent copper, nickel and phosphorus? Provide its neutron flux and fluence, if its irradiation
,exceeded IE16 n/cm2 (E>lMeV).
Provide the time and temperature history of the Palisades reactor vessel at normal operating temperatures with the core critical. Provide the operating temperature and the total time at operating temperature for the welds in the steam generators.
- 5. Provide the approximate number of coils of weld wire in heat W5214.
Describe (a) the weld samples that make up the W5214 percent copper data base, (b) the locations within the samples where the percent copper was measured, and (c) the number of copper-coated filler coils used in the fabrication of the weld.
Provide the measured percent copper values from each sample and the average value from each sample.
Based on this information and data, provide your best-estimate value of the percent copper for the weld heat W5214 and the basis for the value.
Provide the best-estimate value of the percent phosphorus for welds fabricated with weld heat W5214.
- 6. Perform a statistical evaluation to determine if the copper values from the steam generator welds are from the same population as the copper values from the other W5214 welds.
Discuss the implications of the results of this analysis on your evaluation of the amount of copper in the Palisades reactor vessel beltline welds that were fabricated using heat W5214 weld wire.
Enclosure