ML20236U984

Requests Addl Info Re License Amend Request for Plant,Units 1 & 2 to Change Cooling Water Sys Emergency Intake Design Basis

ML20236U984
Person / Time
Site:	Prairie Island
Issue date:	07/23/1998
From:	Wetzel B NRC (Affiliation Not Assigned)
To:	Richard Anderson NORTHERN STATES POWER CO.
References
TAC-M97816, TAC-M97817, NUDOCS 9807310217
Download: ML20236U984 (3)

Text

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.Tuly 23, 1998 L Mr. Roger O. Anderson, Director L Nuclear Energy Engineering 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, AMENDMENT OF - l COOLING WATER SYSTEM EMERGENCY INTAKE DESIGN BASIS

, (TAC NOS.-M97816 AND M97817) l

Dear Mr. Anderson:

l By letter dated January 29,1997,'as supplemented February 11,12, March 7,10,11,19,20, April 29, June 16, 30, July 10, August 29, October 28,1997., February 18 and June 22,1998, Northem States Power Company (NSP) submitted a license amendment request for the Prairie Island Nuclear Generating Plant, Units 1 and 2 to change the cooling water system emergency intake design basis. The staff requires further information pertaining to the Class 1*

classification of the intake canal in order to complete our review of your amendment request.

Thesa questions were previously discussed via telephone with Mr. Anderson, Mr. Eckholt, and L Mr. Albrecht of the NSP staff on July 16,1998. Our request for additional information (RAl) is enclosed.

l l

Please provide your response to the staffs RAI as soon as practical. 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, Senior Project Manager Project Directorate Ill-l .

Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282, 50-306 .I

Enclosure:

As stated cc w/ encl: See next page DISTRIBUTION: ffjh ,bb M,.,m; min 71fj Docket File PUBLIC . PD3-1 Reading l

EAdensam (EGA1) OGC' ACRS

_ JMcCormick-Barger, Rlll DOC'UMENT NAME: G:\WPDOCS\ PRAIRIE \Pl97817.RAI To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy -

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OFFICE PM:PD31 E 3 LA:PD31 _E ECGB [HOMB / D:PD31 / w ,oS NAME BWetzel:dbh CJamersod/ / / CACarpenter DATE Y /M /g8 7 / M /9f /98 /98 l / N/98

- - e. OFFICIAL RECORD COPY 9807310217'990723 PDR ADOCK 05000292 P PDR L

e I

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

J. E. Silberg, Esquire Site Licensing j Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W. Plant Washington DC 20037 Northem States Power Company 1717 Wakonade Drive East Plant Manager Welch, Minnesota 55089 Prairie Island Nuclear Generating Plant Tribal Council Northem States Power Company Prairie Island Indian Community 1717 Wakonade Drive East ATTN: Environmental Department l Welch, Minnesota 55089 5636 Sturgeon Lake Road l Welch, Minnesota 55089 l Adonis A. Nebiett

Assistant Attorney General l Office of the Attorney General 455 Minnesota Street Suite 900

St. Paul, Minnesota 55101-2127 U.S. Nuclear Regulatory Commission l Resident inspector's Office 1719 Wakonade Drive East Welch, Minnesota 55089-9642 Regional Administrator, Region lli U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 4

Mr. Stephen Bloom, Administrator -

l 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 55101-2145 I

June 1998 l

! j

l a

j v' REQUEST FOR ADDITIONAL INFORMAT[QB

1. What is Prairie Island's commitment to Regulatory Guide 1.29 (Seismic Design Classification) with respect to applying Appendix B criteria to Class 1 items? Will the canal l

be covered in the future by the Appendix B program?

2. How was the testing and analysis controlled that demonstrated the necessary functionality of the canal? Were analyses controlled under Appendix B design control provisions? Was testing and laboratory aspects similarly controlled?

3. Will the canal be included in some type of monitoring or surveillance program to ensure continued functionality and conformance with Class 1* analysis?

4. Will future design control provisions for the intake canal be part of an Appendix B program?

Please explain.

5. Is the intake canal part of the " Maintenance Rule Program," 10 CFR 50.65? Please explain.

6. 10 CFR 50.2 defines safety-related structures, systems and components to mean those structures, systems and components that are relied upon to remain functional during and following design basis events to assure: (1) The integrity of the reactor coolant pressure boundary; (2) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the applicable guideline exposures set forth in [10 CFR] 50.34(a)(1) or 100.11...as applicable. Does the intake canal meet any part of this definition (especially part 2)? In other words, is the intake canal relied upon to remain functional during and following design basis events to assure the capability to shut down the reactor and maintain it in a safe shutdown condition? Please explain.

4 ENCLOSURE l l