ML022130633

Request for Additional Information Related to License Amendment Request

ML022130633
Person / Time
Site:	Monticello
Issue date:	08/13/2002
From:	Miranda S NRC/NRR/DLPM/LPD3
To:	Forbes J Nuclear Management Co
References
TAC MB4976
Download: ML022130633 (4)

Text

August 13, 2002 Mr. Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST (TAC NO. MB4976)

Dear Mr. Forbes:

By application dated April 22, 2002, the Nuclear Management Company (the licensee), LLC, requested an amendment to Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant. The proposed amendment would revise the reactor vessel pressure and temperature limit curves in the Monticello Technical Specifications in order to allow required hydrostatic and leak tests to be performed at a significantly lower temperature. This is expected to reduce challenges to plant operators associated with maintaining the reactor coolant system within a narrow temperature band during testing.

To complete its review of the proposed amendment, the Nuclear Regulatory Commission staff requests the licensees response to the enclosed questions. After discussing this request with Mr. D. Neve of your staff, a mutually agreeable due date of September 16, 2002, for your response was established. If you need to revise the due date, please contact me at (301) 415-2303 at the earliest opportunity.

Sincerely,

/RA/

Samuel Miranda, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosure:

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

ML022130633 OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME SMiranda RBouling LRaghavan DATE 08/13/02 08/13/02 08/13/02 Monticello Nuclear Generating Plant cc:

J. E. Silberg, Esquire Commissioner Shaw, Pittman, Potts and Trowbridge Minnesota Department of Commerce 2300 N Street, N. W. 121 Seventh Place East Washington, DC 20037 Suite 200 St. Paul, MN 55101-2145 U.S. Nuclear Regulatory Commission Resident Inspectors Office Adonis A. Neblett 2807 W. County Road 75 Assistant Attorney General Monticello, MN 55362 Office of the Attorney General 445 Minnesota Street Site Licensing Manager Suite 900 Monticello Nuclear Generating Plant St. Paul, MN 55101-2127 Nuclear Management Company, LLC 2807 West County Road 75 Mr. Roy A. Anderson Monticello, MN 55362-9637 Executive Vice President and Chief Nuclear Officer Robert Nelson, President Nuclear Management Company, LLC Minnesota Environmental Control 700 First Street Citizens Association (MECCA) Hudson, WI 54016 1051 South McKnight Road St. Paul, MN 55119 Nuclear Asset Manager Xcel Energy, Inc.

Commissioner 414 Nicollet Mall Minnesota Pollution Control Agency Minneapolis, MN 55401 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.

Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 March 2002

REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST DATED APRIL 22, 2002 MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 The Nuclear Regulatory Commission staff requires the following information to complete its review of the license amendment request for the Monticello pressure-temperature (P-T) limit curves, dated April 22, 2002, that was proposed based on the methods of Code Case N-640, Alternative Reference Fracture Toughness for Development of P-T Limit Curves,Section XI, Division 1":

1. Submit all P-T limit point inputs used to generate the proposed unirradiated core beltline curves and reactor vessel (RV) non-beltline curves for pressure testing conditions, normal operating conditions with the core-not-critical (including times during heatups and cooldowns of the reactor and transient operating conditions), and normal operating conditions with the core-critical. Include in the submittal the following parameter inputs that contributed to the calculation of the P-T limit data points:

a. KIT values and temperature gradient values (i.e., the T values between the temperatures for RCS coolant and those at the 1/4T thickness location of the RV) used for calculation of the P-T limit data points.

b. Identification of the limiting unirradiated RTNDT values and limiting materials for the beltline and non-beltline curves. With respect to submittal of this information, confirm that the Monticello RV beltline region is plate-limited and that Heat No. C2220 (used for fabrication of RV plates I-14 and I-15) is the limiting material for the beltline region of the RV.

2. Submit the P-T limit data points for the irradiated beltline curves that will be used by the Monticello control room operators during pressure testing conditions, normal operating conditions with the core-not-critical (including times during heatups and cooldowns of the reactor and transient operating conditions), and normal operating conditions with the core-critical.