ML031130072

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RAI, Regarding the Application of Leak-Before-Break Technology to Replacement Steam Generator Design
ML031130072
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 04/23/2003
From: John Lamb
NRC/NRR/DLPM/LPD3
To: Solymossy J
Nuclear Management Co
Lamb J, NRR/DLPM, 415-1446
References
TAC MB7509
Download: ML031130072 (4)


Text

April 23, 2003 Mr. Joseph M. Solymossy Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE APPLICATION OF LEAK-BEFORE-BREAK TECHNOLOGY TO REPLACEMENT STEAM GENERATOR DESIGN (TAC NO. MB7509)

Dear Mr. Solymossy:

By letter dated January 29, 2003, the Nuclear Management Company, LLC (NMC), submitted a letter regarding the application of leak-before-break (LBB) technology to the replacement steam generator design for the Prairie Island Generating Plant, Unit 1. The Nuclear Regulatory Commission (NRC) staff finds that the additional information identified in the enclosure is needed.

A draft of the request for additional information was e-mailed to Mr. T. Higgins (NMC) on March 7, 2003. A phone call was held between K. Albright (NMC), R. Pearson (NMC),

O. Nelson (NMC), M. Baker (Framatone), C. McCauley (Framatone), J. Wu (NRC), and myself on March 28, 2003, to discuss the questions and to gain a mutual understanding. Also, the phone call established a mutually agreeable response date of 45 days from the date of this letter.

Please contact me at (301) 415-1446 if future circumstances should require a change in this response date.

Sincerely,

/RA/

John G. Lamb, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-282

Enclosure:

Request for Additional Information cc w/encl: See next page

ML031130072 OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME JLamb RBouling LRaghavan DATE 04/22/03 04/22/03 04/23/03

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING THE APPLICATION OF LEAK-BEFORE-BREAK TECHNOLOGY TO STEAM GENERATOR REPLACEMENT DESIGN PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 DOCKET NO. 50-282 By letter dated January 29, 2003, the Nuclear Management Company, LLC (NMC), submitted a letter regarding the application of leak-before-break (LBB) technology to the replacement steam generator design for the Prairie Island Generating Plant, Unit 1. The NRC staff has the following questions:

1. Does "reanalysis" mean: (a) reactor coolant loop (RCL) reanalysis and requalification? OR (b) leak-before-break (LBB) re-demonstration by reevaluation or validation of the original evaluation?
2. Does NMC plan to submit results of 1(b) above for the NRC staffs review and approval whether new LBB loads are enveloped by the original LBB loads, or LBB is reevaluated and re-demonstrated?
3. Does NMC plan to make a statement in response to (2) above that there are no new breaks due to cutting and welding of the steam generator replacement project?
4. The submittal stated that the RCL will be designed for the postulated breaks in the largest branch lines (surge, residual heat removal, safety injection system/accumulator injection).

Are postulated breaks in the main feedwater and main steam lines going to be reanalyzed?

Will they be reanalyzed for the same break locations and conditions?

5. Are there any support changes associated with the steam generator replacement project?
6. Relating to the reactor coolant system (RCS) reanalysis, question 1(a) above, for thermal and seismic conditions, are there any stiffness changes which may impact the natural frequencies of the RCS and structural responses at controlling locations for LBB demonstration? Please explain how these impacts are addressed in question 1(b) above.
7. How does NMC plan to document the RCL reanalyses associated with the replacement steam generator? Will the reanalyses be governed by the same design specifications as the original steam generator?

Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esquire General Counsel Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Manager, Regulatory Affairs Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089 Adonis A. Neblett Assistant Attorney General Office of the Attorney General 455 Minnesota Street Suite 900 St. Paul, MN 55101-2127 U.S. Nuclear Regulatory Commission Resident Inspectors Office 1719 Wakonade Drive East Welch, MN 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 121 Seventh Place East Suite 200 St. Paul, MN 55101-2145 Tribal Council Prairie Island Indian Community ATTN: Environmental Department 5636 Sturgeon Lake Road Welch, MN 55089 Mr. Roy A. Anderson Executive Vice President Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Nuclear Asset Manager Xcel Energy, Inc.

550 15th St., Suite 1000 Denver, CO 80202 John Paul Cowan Chief Nuclear Officer Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Mano K. Nazar Senior Vice President Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 March 2003