ML18065A286

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Forwards RAI to Complete Review of Plant Thermal Annealing Rept,Section 3,Fracture Toughness Recovery & Reembrittlement Assurance Program.Provide Response within 30 Days of Ltr Date
ML18065A286
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/16/1995
From: Gamberoni M
NRC (Affiliation Not Assigned)
To: Smedley R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TAC-M92310, NUDOCS 9511210306
Download: ML18065A286 (4)


Text

Mr. Richard W. Smedley Manager, Licensing Palisades Plant 27780 Blue Star Memorial Highway Covert, MI 49043 November 16,

SUBJECT:

PALISADES PLANT - REQUEST FOR ADDITIONAL INFORMATION -

(TAC NO. M92310)

Dear Mr. Smedley:

Based on our review of Palisades' Thermal Annealing Report, Section 3, Fracture Toughness Recovery and Reembrittlement Assurance Program, we require additional information and clarification of information provided in the October 12, 1995, submittal.

Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions regarding this request, please contact me at 415-3024.

This requirement affects nine or fewer respondents and, therefore, is not subject to the Office of Management and Budget review 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:

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Mr. Richard W. Smedley 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 Pl ant 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 Vice President & 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's 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 Michigan Department of Attorney General Special Litigation Division 630 Law Building P.O. Box 30212 Lansing, Michigan 48909 Mr. Dennis Harrison U.S. Department of Energy NE 451 Washington, DC 20585 September 1995

CLARIFICATIONS/REQUEST FOR ADDITIONAL INFORMATION CONSUMERS POWER COMPANY PALISADES PLANT, DOCKET 50-255 THERMAL ANNEALING REPORT, SECTION 3 FRACTURE TOUGHNESS RECOVERY AND REEMBRITTLEMENT ASSURANCE PROGRAM Request for Additional Information

1. This Section of the report should address the issue of the potential for temper embrittlement (TE) or other forms of non-hardening embrittlement of the Palisades beltline materials resulting from the annealing heat treatment.

Particular emphasis should be placed on weld heat affected zone (HAZ) materials.

What research/analyses/procedures will be used to demonstrate that TE is not a concern?

o Chemistry considerations - particularly phosphorus levels.

Compare/contrast Palisades beltline materials with existing studies.

o Metallurgical considerations - grain size, width of coarse-grained HAZ region, welding parameters, plate fabrication parameters.

Compare/contrast Palisades beltline materials with existing studies.

o Have fracture surfaces from Palisades surveillance materials previously been examined for evidence of intergranular fracture? If so, what were the results?

o Will there be an experimental program to examine HAZ impact toughness for the Palisades beltline materials? If such a program is planned, the program should include surveillance materials with plate materials and weld materials and process parameters similar to those used for the vessel weldments.

o How will the annealing heat treatment affect the fracture toughness of the Palisades HAZ beltline materials?

ENCLOSURE

  • 2.

Section 3.1.4.2 states that reconstituted specimens will be tested in the same orientation as the original. What was the original orientation of the specimens in the weld metal? Please provide a drawing showing the orientation.

3.

Section 3.1.5.2.a states that CVN [Charpy V-notch] specimen halves with "extensive" evidence of plastic deformation will be eliminated from further consideration. How is "extensive" deformation defined?

4.

Section 3.2.2 states that the original surveillance capsules will be annealed and "if possible", reinserted prior to restart. Explain, what is meant by "if possible."

Clarifications

1.

The annealing temperature and uncertainty were specified in Section 3.1.5.2.b as 850°F + /-25°F. RG 1.162 requires that the recovery estimates (Table 3.1.6.1 and 3.1.6.3) would have been calculated using 825°F. Was this the case?

2.

The first note on Table 3.1.3-1 states that the W5214 welds used in the annealing verification program were taken from the higher copper or higher nicket chemistry region of the steam generator (SG) welds and "bound" the estimate for the reactor pressure vessel (RPV) welds. NRC interprets this statement to mean that the RPV welds are not expected to recover to as great a degree as the SG welds. Is this interpretation correct?

3.

Section 3.2.1.2 states that "application of the lateral shift method to the Charpy Upper Shelf Energy (USE) is more difficult because there is no generally accepted model of embrittlement.

  • NRC expects that the trend curves from Figure 2 in RG 1.99, Rev. 2 will still apply to describe USE decline after annealing.
4.

Section 3.2.2 correctly assumes that the procedures of 10 CFR 50.61 will be used for the chemistry factor calculation. The licensee discussed in this section the calculation of a "new" post-anneal chemistry factor. The staff recognizes the potential for annealing to alter the sensitivity to radiation embrittlement. This may be a potential consideration for a future revision of AG 1.99, Rev. 2 and/or the annealing RG (1.162).