ML20133J493

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Forwards RAI on Plant Third 10-year Interval Inservice Insp Program Plan Request for Relief.Info Needed in Order for Staff to Complete Review of Request
ML20133J493
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 01/15/1997
From: Wetzel B
NRC (Affiliation Not Assigned)
To: Richard Anderson
NORTHERN STATES POWER CO.
References
TAC-M934037, TAC-M934038, NUDOCS 9701210038
Download: ML20133J493 (4)


Text

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January 15, 1996 Mr. Roger 0. Anderson, Director Licensing and Management Issues Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF (TAC NOS. M934037 AND M94038)

Dear Mr. Anderson:

By letter dated November 1, 1995, and supplemented August 9, 1996, and November 26, 1996, Northern States Power Company (NSP) submitted a request for authorization to use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-521. Additional information is required from NSP in order for the staff to complete its review of your request.

Our request for additional information (RAI) is enclosed.

The staff. requests that you submit your responses to the enclosed RAI within 30 days to meet'the staff's review schadule.

If you have any questions regarding the content of the RAI, please contact me at (301) 415-1355.

Sincerely, Original. signed by:

Beth A. Wetzel, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation 4

Docket Nos. 50-282 and 50-306

Enclosure:

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January 15, 1997 Mr. Roger 0. Anderson, Director Licensing and Management Issues Northern States Power Company 414 Nicollet Mall

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Minneapolis, Minnesota 55401

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF (TAC NOS. M934037 AND M94038)

Dear Mr. Anderson:

By letter dated November 1, 1995, and supplemented August 9, 1996, and November 26, 1996, Northern States Power Company (NSP) submitted a request for authorization to use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-521. Additional information is required from NSP in order for the staff to complete its review of your request. Our request for additional information (RAI) is enclosed.

The staff requests that you submit your responses to the enclosed RAI within 30 days to meet the staff's review schedule.

If you have any questions regarding the content of the RAI, please contact me at (301) 415-1355.

Sincerely, A

.M Beth A. Wetzel, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

RAI cc w/ enc 1: See next page

4 REQUEST FOR ADDITIONAL INFORMATION l

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 & 2, ASME C00E CASE N-521 1.

Critical flaw size is discussed in paragraph 3.2, and the results are presented in Figure 3 of the licensee's submittal.

It is not clear if the calculations for critical flaw depth included the Code-required safety factors.

If so, provide an explicit statement which also includes a brief description of the required safety factors.

2.

Identify what minimum flaw size, with a high probability of detection, the NDE technique has and relate the size to the amount of crack growth that will occur for the required time frame (up to 20 years). A comparison between this determination and the data presented in Figure 3 should be made to ensure that an acceptable level of quality and safety are maintained.

I 3.

Fatigue crack growth and stress corrosion cracking are discussed in the evaluation, however, corrosion fatigue is not mentioned. Was corrosion fatigue evaluated?

If so, what conditions were considered and why?

4.

Provide a brief discussion on how negative "R" values were handled in calculating the effective "K" value.

5.

Explain how a change in aspect ratio (a/1) was handled during crack growth and why.

ENCLOSURE 4

i Mr. Roger 0. Anderson, Director Prairie Island Nuclear Generating Northern States Power Company Plant cc:

J. E. Silberg, Esquire Tribal Council Shaw, Pittman, Potts and Trowbridge Prairie Island Indian Comunity 2300 N Street, N. W.

ATTN:

Environmental Department Washington DC 20037 5636 Sturgeon Lake Road Welch, Minnesota 55089 Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company 1717 Wakonade Drive East Welch, Minnesota 55089 Adonis A. Nebiett Assistant Attorney General Office of the Attorney General 455 Minnesota Street Suite 900 St. Paul, Minnesota 55101-2127 U.S. Nuclear Regulatory Comission Resident Inspector's Office 1719 Wakonade Drive East Welch, Minnesota 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Jeff Cole, Auditor / Treasurer Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota S5101-2145 Site Licensing Prairie Island Nuclear Generating Plant Northern States Power Company 1717 Wakonade Drive East Welch, Minnesota 55089 November 1996