ML050910217

Request for Additional Information for the Review of the Point Beach Nuclear Plant, Units 1 and 2, License Renewal Application

ML050910217
Person / Time
Site:	Point Beach
Issue date:	03/31/2005
From:	Veronica Rodriguez NRC/NRR/DRIP/RLEP
To:	Koehl D Nuclear Management Co
Rodriguez V, RLEP/DRIP/NRR, 415-2232
References
TAC MC2099, TAC MC2100
Download: ML050910217 (6)

Text

March 31, 2005 Mr. Dennis L. Koehl Site Vice President Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MC2099 AND MC2100)

Dear Mr. Koehl:

By letter dated February 25, 2005, Nuclear Management Company, LLC, (NMC or the applicant) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Point Beach Nuclear Plant (PBNP), Units 1 and 2, 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 RAIs were discussed with your staff, Mr. Jim Knorr, 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 301-415-3703 or e-mail VMR1@nrc.gov.

Sincerely,

/RA/

Veronica M. Rodriguez, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosure:

As stated cc w/encls: See next page

March 31, 2005 Mr. Dennis L. Koehl Site Vice President Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MC2099 AND MC2100)

Dear Mr. Koehl:

By letter dated February 25, 2005, Nuclear Management Company, LLC, (NMC or the applicant) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Point Beach Nuclear Plant (PBNP), Units 1 and 2, 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 RAIs were discussed with your staff, Mr. Jim Knorr, 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 301-415-3703 or e-mail VMR1@nrc.gov.

Sincerely,

/RA/

Veronica M. Rodriguez, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosure:

As stated cc w/encls: See next page DISTRIBUTION: See next page ADAMS Accession no.: ML050910217 Document Name: E:\\Filenet\\ML050910217.wpd OFFICE PM:RLEP PM:RLEP LA:RLEP SC:RLEP NAME VRodriguez GSuber (VRodriguez for)

MJenkins SLee DATE 03 / 31 / 05 03 / 31 / 05 03 / 31 / 05 03 / 31 /05 OFFICIAL RECORD COPY

Point Beach Nuclear Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esq.

Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. Frederick D. Kuester President and Chief Executive Officer We Generation 231 West Michigan Street Milwaukee, WI 53201 James Connolly Manager, Regulatory Affairs Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Mr. Jeffrey Kitsembel Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 David Weaver Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Douglas E. Cooper Senior Vice President - Group Operations Palisades Nuclear Plant Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Fred Emerson Nuclear Energy Institute 1776 I Street, NW., Suite 400 Washington, DC 20006-3708 Roger A. Newton 3623 Nagawicka Shores Drive Hartland, WI 53029 James E. Knorr License Renewal Project Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241

DISTRIBUTION: Letter to D. Koehl, Re: RAI for the review of Pt. Beach Nuclear Plant, Units 1 and 2, Dated: March 31, 2005 Adams Accession No.: ML050910217 HARD COPY RLEP RF E-MAIL:

RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski 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 P. Lougheed, RIII J. Strasma, RIII A. Stone, RIII H. Chernoff W. Ruland L. Raghavan T. Mensah OPA

Enclosure POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

Aging Management of Auxiliary Systems RAI 3.3-7 In LRA Table 3.3.2-2 (Page 3-221), the applicant proposed to manage cracking due to IGA/IGSCC of stainless steel in heat exchanges exposed to primary treated water with T>480oF (internal) using the Water Chemistry Control Program. This line item cites Note 35, which states Component/material/environment is not addressed in the corresponding NUREG-1801 Chapter, but the component/material/environment is addressed in another NUREG-1801 Chapter. The AMR line item references AMR line Item 3.1.1-36 which provides the following discussion:

Crack initiation and growth due to SCC and flaw growth are identified as aging effects requiring management for the reactor vessel nozzle safe ends, CRD housing, and RCS components. Aging management programs credited for managing these effects are the Water Chemistry Control Program and ASME Section XI, Subsections IWB, IWC, and IWD Inservice Inspection Program.

The Note implies that ASME Section XI, Subsections IWB, IWC, and IWD Inservice Inspection Program should have also been applied to LRA Table 3.3.2-2. The staff requests the applicant to explain this discrepancy or make a commitment to revise the line item in LRA Table 3.3.2-2 to include the Inservice Inspection Program.

Aging Management of Containments, Structures and Component Supports RAI 3.5-14 (1) In LRA Table 3.5.1, Item 3.5.1-33, the applicant stated that the Bolting Integrity Program includes the use of Inservice Inspections to evaluate and monitor crack initiation and growth due to SSC, if present, in high strength low-alloy steel bolts used in NSSS component support.

In LRA Tables 3.5.2-1 through 3.5.2-14, the applicant does not address Group B1.1, high strength low-alloy bolts.

In LRA Section B2.1.4, the applicant indicated that high strength component support bolting is used in pinned connections associated with steam, reactor coolant pumps and reactor vessel supports and is loaded only in shear with no preload stress.

No preload stress indicates that PBNP NSSS components bolting were installed with snug-tight only, without using any torque or turn-of nuts method during installation. The staff requests the applicant to provide justification for the statement of no preload stress for NSSS components bolting. The applicant is requested to clarify if there are any Group B1.1, high strength low-alloy bolts, not used for pinned connection only.

Additionally, the applicants Bolting Integrity Program does not support the discussion in LRA Table 3.5.1, Item 3.5.1-33. The staff requests the applicant to identify the aging management for the Group B1.1, high strength low-alloy bolts.