ML052310055

Request for Additional Information for the Review of the Monticello Nuclear Generating Plant License Renewal Application

ML052310055
Person / Time
Site:	Monticello
Issue date:	08/18/2005
From:	Daniel Merzke NRC/NRR/DRIP/RLEP
To:	Conway J Nuclear Management Co
Merzke, D., NRR/DRIP/RLEP, 415-3777
References
TAC MC6440
Download: ML052310055 (8)

Text

August 18, 2005 Mr. John T. Conway Site Vice President Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION (TAC NO. MC6440)

Dear Mr. Conway:

By letter dated March 16, 2005, Nuclear Management Company, LLC, (NMC or the applicant) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) to renew the operating license for Monticello Nuclear Generating Plant (MNGP) for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review.

These questions were discussed with your staff, Mr. Patrick Burke, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3777 or by e-mail at DXM2@nrc.gov.

Sincerely,

/RA/

Daniel J. Merzke, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-263

Enclosure:

As stated cc w/encl: See next page

August 18, 2005 Mr. John T. Conway Site Vice President Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION (TAC NO. MC6440)

Dear Mr. Conway:

By letter dated March 16, 2005, Nuclear Management Company, LLC, (NMC or the applicant) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) to renew the operating license for Monticello Nuclear Generating Plant (MNGP) for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review.

These questions were discussed with your staff, Mr. Patrick Burke, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3777 or by e-mail at DXM2@nrc.gov.

Sincerely,

/RA/

Daniel J. Merzke, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-263

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION: See next page ADAMS Accession no.:ML052310055 Document Name: E:\\Filenet\\ML052310055.wpd OFFICE PM:RLEP LA:RLEP SC:RLEP NAME DMerzke MJenkins SLee DATE 8/16/05 8/15/05 8/18/05 OFFICIAL RECORD COPY

Monticello Nuclear Generating Plant cc:

Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 U.S. Nuclear Regulatory Commission Resident Inspector's Office 2807 W. County Road 75 Monticello, MN 55362 Manager, Regulatory Affairs Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637 Robert Nelson, President Minnesota Environmental Control Citizens Association (MECCA) 1051 South McKnight Road St. Paul, MN 55119 Commissioner Minnesota Pollution Control Agency 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 Commissioner Minnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198 Manager - Environmental Protection Division Minnesota Attorney Generals Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Nuclear Asset Manager Xcel Energy, Inc.

414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Patrick Burke License Renewal Project Manager Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637 Mr. Douglas F. Johnson Director, Plant Life Cycle Issues Nuclear Management Company, LLC 700 First Street Hudson, WI 54016

DISTRIBUTION: Letter to: J. Conway, re: RAI for review of Monticello LRA, Dated: August 18, 2005 ADAMS Accession No.: ML052310055 HARD COPY RLEP RF E-MAIL:

RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li K. Winsberg (RidsOgcMailCenter)

R. Weisman M. Mayfield A. Murphy S. Smith (srs3)

S. Duraiswamy Y. L. (Renee) Li RLEP Staff L. Raghavan M. Padovan A. Stone, RIII B. Burgess, RIII P. Lougheed, RIII R. Orlikowski, RIII T. Mensah OPA

Enclosure MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

Fire Protection RAI 2.3.3.9-1 The diesel fire pump, diesel fire pump day tank, and interconnecting piping are highlighted on LRA Drawing LR-36051 within the scope of license renewal. However, the diesel fire pump day tank fill line is not highlighted. Verify whether the diesel fire pump day tank fill line is within the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an Aging Management Review (AMR) in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.

RAI 2.3.3.9-2 On LRA Drawing LR-36664 (coordinates C-7), the KB/GB boundary and the system boundary break (Fire Protection Emergency Service Water) are at opposite ends of Valve RHRSW-46.

This is the only valve on the drawing where they are at opposite ends. Verify if this is correct.

RAI 2.3.3.9-3 On LRA Drawing LR-36664, the piping on the KB side (outlet) of Valve RHRSW-46 (coordinates C-7) is highlighted as being within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). On the continuation LRA Drawing LR-36048, the same piping is shown highlighted as being within the scope of license renewal per 10 CFR 54.4(a)(1) and (a)(3).

Verify which paragraph of 10 CFR 54.4 is applicable to this piping for the LRA.

RAI 2.3.3.9-4 NUREG-1801, GALL Report,Section XI.27, Fire Water System, describes the requirement for aging management of the Fire Protection (FP) Water System. It recommends that an Aging Management Program (AMP) be established to evaluate the aging effects of corrosion, microbiologically influenced corrosion (MIC), and biofouling of carbon steel and cast iron components in FP systems exposed to water.

LRA Section 2.3.3.9 discusses requirements for the fire detection and protection program, but does not mention trash racks and traveling screens for the fire pump suction water supply.

Trash racks and traveling screens are not mentioned in LRA Section 2.3.3.3, Circulating Water System, or Section 2.4.8, Intake Structure.

The USAR states in part, River water is turned through an angle of 81E to approach the plant along a channel excavated to elevation 898 feet. It enters the Intake Structure through a trash rack before dividing into two separate streams to the circulating water pump chambers. Each stream passes through two parallel automatically-operated traveling screens, the service water pump bay and two parallel motor-operated sluice gates before reaching a circulating water pump. The center dividing wall permits dewatering of either pump bay.

A normally closed gate in the wall can be manually opened during normal operation if a traveling screen is out of service for maintenance. Taking suction from the service pump bay are two 14,000 gpm make-up pumps and pumps for the station cooling, screen wash, and fire protection.

Trash racks and traveling screens are necessary to remove debris and prevent clogging for the FP water supply system. Trash racks and traveling screens are typically considered passive, long-lived components. Trash racks are located in a freshwater environment. Traveling screens are located in a freshwater/air environment. Although not specifically discussed in the USAR or LRA, trash racks and traveling screens are typically constructed of carbon steel material. Carbon steel in a fresh water environment or a freshwater/air environment is subject to corrosion. Explain the apparent exclusion of the trash racks and traveling screens that are located upstream of the fire pump suctions from the scope of license renewal and from requiring an AMR.

RAI 2.3.3.9-5 The NRCs Fire Protection Safety Evaluation Report (undated), Section 3.1.2(3) states that a sprinkler system will be installed to provide a means to cool hot gases that enter the cable tray area in the water treatment and ESF motor control center area. This sprinkler system is not shown on the License Renewal Boundary Drawings. Verify that this sprinkler system is within the scope of license renewal per 10 CFR 54.4(a)(3).

RAI 2.3.3.9-6 The NRCs Fire Protection Safety Evaluation Report (undated), Section 4.3.1(7) states that The licensee will provide foam application equipment for use in fighting potential lube oil fires in the turbine building. This foam application equipment is not shown on the License Renewal Boundary Drawings. Verify that this foam application equipment is within the scope of license renewal per 10 CFR 54.4(a)(3).

RAI 2.3.3.9-7 The NRCs Fire Protection Safety Evaluation Report (undated), Section 5.2.6 states that the Cable Spreading Room will be provided with an automatic gas suppression system. This automatic gas suppression system is not shown on the License Renewal Boundary Drawings.

Verify that this automatic gas suppression system is within the scope of license renewal per 10 CFR 54.4(a)(3).

RAI 3.3.2.1.9-1 LRA Table 3.3.2-9 FIR refers to Notes J and 319 which describe the AMRs for copper alloy in heat exchangers. Provide justification for the conclusion specified in Note 319 that the aging management program referenced is appropriate for the aging effects/mechanisms identified and provides assurance that the aging effects/mechanisms are effectively managed through the period of extended operation.

RAI 3.3.2.1.9-2 LRA Table 3.3.2-9 FIR shows that there is no AMP for stainless steel fasteners/bolting. Please explain why these fasteners/bolting do not require an AMP, such as defined by NUREG-1801 Vol. 2,Section XI.M18, Bolting Integrity.

RAI 3.5.2.1.5-1 LRA Table 3.5.2-05 refers to the Fire Protection Program as the AMP for carbon steel in air/gas. Provide justification for this conclusion.

RAI 3.5.2.1.5-2 LRA Tables 3.5.2-05, 3.5.2-15, and 3.5.2-17 refer to the Fire Protection Program as the AMP for fibrous fire raps (thermal insulating wool/fiber), cementitious fireproofing (thermal insulating mastic), and rigid board (thermal insulating board) in air/gas. Provide justification for this conclusion.

RAI 3.5.2.1.5-3 LRA Tables 3.5.2-15 and 3.5.2-17 refer to the Structures Monitoring Program as the AMP for rigid board (thermal insulating board) in air/gas. Provide justification for this conclusion.