ML052850264

Request for Additional Information for the Review of Nine Mile Point Nuclear Station, Units 1 and 2, Amended License Renewal Application (Tac Nos. MC3272 and MC3273)

ML052850264
Person / Time
Site:	Nine Mile Point
Issue date:	10/11/2005
From:	Le N NRC/NRR/DRIP/RLEP
To:	Spina J Nine Mile Point
Le N. B., NRR/DRIP/RLEP, 415-1458
References
TAC MC3272, TAC MC3273
Download: ML052850264 (7)

Text

October 11, 2005 Mr. James A. Spina Vice President Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2, AMENDED LICENSE RENEWAL APPLICATION (TAC NOS. MC3272 AND MC3273)

Dear Mr. Spina:

By letter dated July 14, 2005, Constellation Energy Group Inc., resubmitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating licenses for the Nine Mile Point Nuclear Station (NMP), Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the amended license renewal application (ALRA) and has identified, in the enclosure, areas where additional information is needed to complete the review.

Based on discussions with Mr. David Dellario of your staff, a mutually agreeable date for your response is within 30 days from the date of this letter. If you have any questions regarding this letter or if circumstances result in your need to revise the response date, please contact me by telephone at 301-415-1458 or via e-mail at nbl@nrc.gov.

Sincerely,

/RA/

N. B. (Tommy) Le, Senior Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos.: 50-220 and 50-410

Enclosure:

As stated cc w/encl: See next page

ML052850264 DISTRIBUTION: See next page Document Name: E:\\Filenet\\ML052850264.wpd OFFICE RLEP:PM RLEP:LA RLEP:SC-A NAME N. Le M. Jenkins L. Lund (R. Auluck for)

DATE 10/ 11 /05 10/ 11 /05 10/ 11 /05

DISTRIBUTION: Ltr. To J. Spina, Re: Nine Mile Nuclear Station, Units 1 and 2, Dated: October 11, 2005, Accession No.: ML052850264 HARD COPY RLEP RF N. Le (PM)

E-MAIL:

RidsNrrDrip RidsNrrDe RidsOgcMailCenter G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li R. Weisman M. Mayfield A. Murphy S. Smith (srs3)

S. Duraiswamy Y. L. (Renee) Li RLEP Staff C. Holden R. Laufer P. Tam B. Fuller, RI E. Knutson, RI J. Trapp, RI T. Mensah T. Koshy PY Chen H. Ashar D. Jeng J. Burns M. Lemoncelli OPA

NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 (NMP1 and NMP2)

AMENDED LICENSE RENEWAL APPLICATION (ALRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

ALRA Section 2.3 - Scoping and Screening Results: Mechanical Systems RAI 2.3-1 For Unit 1, please indicate whether the liquid poison pressure nozzle is considered a reactor pressure vessel penetration requiring an Aging Management Review (AMR).

RAI 2.3-2 For Unit 2, please indicate whether temperature equalizing columns should be identified as reactor pressure vessel instrumentation system components requiring an AMR.

RAI 2.3-3 For Unit 1, the Liquid Poison System contains two elements that monitor the Liquid Poison Storage Tank temperature. One of these components is in-scope for license renewal since it is a safety-related component. The other component is non-safety-related and has no license renewal intended function. The in-scope temperature element itself is an active component and, therefore, not subject to AMR. However, the temperature sensor is housed in a thermowell that is subject to AMR. Which temperature element (TE) is the in-scope element, is it TE 41-35 or TE 41-28?

RAI 2.3-4 For Unit 2, please indicate whether the diffuser seal ring and shroud support plate should be identified as a reactor pressure vessel internal component requiring an AMR.

ALRA Section 2.4 - Scoping and Screening Results: Structures and Component Supports RAI 2.4.A-1 The ALRA Section 2.4.A.1 incorporates the thrust of this RAI, except it is not clear if the refueling seal between the refueling cavity and the drywell is within the scope or not. The staffs concern is as follows:

Leakage through the refueling seals located at the top of the drywell potentially exposes the carbon steel drywell shell inner and outer surfaces to loss of material due to corrosion. This is a particular concern for the embedded portion of the drywell shell.

Corrosion detected on the outer shell surface in the sand pocket region in a number of Mark I steel containments has been attributed to leakage past the drywell-to-reactor building refueling seal, coupled with clogging of the sand pocket drains. Leakage into the drywell, past the reactor vessel-to-drywell refueling seal, creates the potential for corrosion of the inaccessible portion of the inner surface of the drywell shell, embedded in the concrete floor.

From the information contained in ALRA Table 2.4.A.1-1, it is not clear to the staff:

(1) whether the refueling seals have been included in the license renewal scope, and (2) if included, how aging management is being addressed. Please provide the following information:

Verification that the refueling seals are included in the license renewal scope, or a detailed explanation for their exclusion.

A detailed description of the plant-specific operating experience for the refueling seals, including incidences of degradation, method of detection, root cause, corrective actions, and current inspection procedures.

A detailed description of the scoping, screening, and AMR for the refueling seals.

The aging management programs credited to manage aging of the refueling seals.

RAI 2.4.C.1-1 In Table 2.4.C-1 of the ALRA, the applicant includes ASME Class 1, 2, 3 and MC hangers and supports. The staff assumes that the drywell and torus external supports are included within the Class MC supports. The applicant is requested to confirm the staffs assumption.

Nine Mile Point Nuclear Station, Units 1 and 2 cc:

Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James R. Evans LIPA P.O. Box 129 Lycoming, NY 10393 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy Electric Division NYS Department of Public Service Agency Building 3 Empire State Plaza Albany, NY 12223 C. Adrienne Rhodes Chairman and Executive Director State Consumer Protection Board 5 Empire State Plaza, Suite 2101 Albany, NY 12223-1556 Kathryn M. Sutton, Esquire Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street, NW Washington, DC 20005-3502 Mr. Michael J. Wallace President Nine Mile Point Nuclear Station, LLC c/o Constellation Energy Group, Inc.

750 East Pratt Street Baltimore, MD 21202 Carey W. Fleming, Esquire Sr. Counsel - Nuclear Generation Constellation Generation Group, LLC 750 E. Pratt Street, 17th Floor Baltimore, MD 21202 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. James Ross Nuclear Energy Institute 1776 I St., NW, Suite 400 Washington, DC 20006-3708 Mr. Mark Flaherty Manager - Fleet Licensing R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, NY 14519 Mr. M. Steven Leonard General Supervisor - Nuclear Regulatory Matters Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

Nine Mile Point Nuclear Station, Units 1 and 2 cc:

Mr. Peter Mazzaferro Site Project Manager - License Renewal Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 Mr. Mike Heffley Senior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401