ML053070131

Request for Additional Information for the Review of Nine Mile Point Nuclear Station, Units 1 and 2, Amended License Renewal Application

ML053070131
Person / Time
Site:	Nine Mile Point
Issue date:	11/02/2005
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: ML053070131 (8)

Text

November 2, 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. (CEG), 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

ML053070131 DISTRIBUTION: See next page Document Name: E:\\Filenet\\ML053070131.wpd OFFICE RLEP:PM RLEP:LA RLEP:SC-A NAME N. Le M. Jenkins L. Lund DATE 10/ /05 11/01/05 11/2/05

DISTRIBUTION: Ltr. To J. Spina, Re: Nine Mile Nuclear Station, Units 1 and 2, Dated: November 2, 2005, Accession No.: ML053070131 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 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

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

AMENDED LICENSE RENEWAL APPLICATION (ALRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

PART 1 - AGING MANAGEMENT OF AUXILIARY SYSTEMS PART 2 - NMP UNIT 1 AMENDED LICENSE RENEWAL (ALRA) ISSUE REGARDING CONTROL ROD DRIVE STUB TUBE PENETRATIONS PART 3 - TIME-LIMITED AGING ANALYSES PART 1 - AGING MANAGEMENT OF AUXILIARY SYSTEMS 3.3 Aging Management of Auxiliary Systems General RAI a-RAI 3.3.2-1 One-Time Inspection (OTI) is appropriate where either an aging effect is not expected to occur but there is insufficient data to completely rule it out, or the aging effect is expected to occur very slowly so as not to affect the component intended function. In the Amended LRA (ALRA) submitted to the staff by letter dated July 14, 2005, the applicant proposed to use the OTI program to manage aging effects for various materials exposed to various environments for the majority of the components in the following two systems:

(a)

ALRA Table 3.3.2.A-14, NMP1 Radioactive Waste System (b)

ALRA Table 3.3.2.B-14, NMP2 Floor and Equipment Drains System (1)

Explain from system characteristics standpoint, why the OTI program [rather than periodic inspections] is proposed to manage the aging effects for those material/environment combinations having OTI as the sole AMP in these two systems.

(2)

Justify the use of OTI program for the following cases:

(a)

In ALRA Table 3.3.2.A-14, Aging Effect Requiring Management (AERM) of cracking for Wrought Austenitic Stainless Steel (WASS) Heat Exchangers exposed to air, moisture or wetting, temperature greater or equal to 140NF, and for WASS valves exposed to treated water, temperature greater or equal to 140NF but less than 212NF.

(b)

In ALRA Table 3.3.2.A-14, AERM of loss of material (LOM) for carbon or low alloy steel (yield strength less than 100 ksi), or WASS valves, and piping and fittings exposed to Demineralized Untreated Water (DUW).

(c)

In ALRA Table 3.3.2.A-14, AERM of LOM for carbon or low alloy steel (yield strength less than 100 ksi) valves exposed to either the DUW, low flow, or treated water, temperature greater or equal to 140NF but less than 212NF.

(d)

In ALRA Table 3.3.2.B-14, AERM of cracking for WASS Drainers exposed to treated water, temperature greater or equal to 140NF but less than 212NF.

(e)

In ALRA Table 3.3.2.B-14, AERM of LOM for aluminum pump, or carbon or low alloy steel (yield strength less than 100 ksi) strainers exposed to raw water.

System Specific RAI a-RAI 3.3.2.A-5-1 In ALAR Table 3.3.2.A-5, please explain what the Note ?K represents for Heat Exchangers, and valves and dampers. Also explain why the LOM was not identified as an AERM for WASS Heat Exchangers, which are exposed to DUW similar to the WASS Heat Exchangers in Table 3.3.2.A-

14.

PART 2 - NMP UNIT 1 AMENDED LICENSE RENEWAL (ALRA) ISSUE REGARDING CONTROL ROD DRIVE STUB TUBE PENETRATIONS a-RAI 3.1.2-1 In Table 3.1.1.A-1 of the Nine Mile Point (NMP) Amended License Renewal Application (ALRA),

dated July 14, 2005, the applicant states, Aging management of the CRD stub tube penetrations is managed in accordance with BWRVIP-47 of the BWR Vessel Internals Program, XI.M9, and plant-specific commitments contained in the NRC safety evaluation (SE) dated March 25, 1987.

Then, by another letter dated July 14, 2005, the applicant provided its response to RAI 3.1.2-1, stating that, NMP committed to implement a strategy whereby during the period of extended operation a leaking control rod drive (CRD) stub tube penetration would be roll repaired. If, following the roll repair, this stub tube were to leak within acceptable limits, then a weld repair would be effected no later than one operating cycle following discovery of the leakage.

The wording in Table 3.1.1.A-1 and in the applicants response to RAI 3.1.2-1 imply that NMP Unit 1 will operate with CRD stub tube leakage for one operating cycle (2 years). The staff does not consider this is acceptable for the period of extended operation. The SE, dated March 25, 1987, as cited above, which allows NMP Unit 1 to operate with CRD stub tube leakage, was only acceptable as a temporary repair. Specifically, Item (6) of the staffs conclusions of the aforementioned SE, states that, The proposed leakage criteria provides sufficient time to complete the final development of the prototype mechanical seal and associated tooling and investigate other methods such as weld repair.

Based on the information above, the staff requests that the applicant revise the Corrective Action statement on Page B2-25 and Commitment 36, in Table A1.4, of the NMP1 ALRA to commit to immediately repair any leaking CRD stub tubes, during the proposed period of extended operation, by the implementation of a permanent weld repair per approved ASME Code Cases with staff conditions, if any. In addition, the staff requests that the applicant revise the Discussion section of Item Number 3.1.1.A-30, Penetrations, in Table 3.1.1.A for NMP1 (Page 3.1-29 of the ALRA) by deleting, plant-specific commitments contained in the NRC safety evaluation dated March 25, 1987, and by adding, plant-specific commitments for license renewal as indicated in Commitment 36 of Table A1.4.

PART 3 - TIME-LIMITED AGING ANALYSES a-RAI 4.2-1 Under TLAA 4.2 on Reactor Vessel Neutron Embrittlement Analysis, the applicant needs to provide a description of the Reflood Thermal Shock Analysis of the Reactor Vessel and the Reflood Thermal Shock Analysis of the Reactor Vessel Core Shroud for both NMP 1 and NMP 2.

If not, then the applicant needs to provide a justification in the application of why these analyses are not needed (i.e. for NMP Unit 1-no jet pumps).

a-RAI 4.7-1 The applicant needs to include a TLAA in Section 4.7 for the Irradiation Assisted Stress Corrosion Cracking of Reactor Vessel Internals.

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