ML053290143
| ML053290143 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/22/2005 |
| From: | Le N NRC/NRR/ADRO/DLR/RLRA |
| To: | Spina J Nine Mile Point |
| Le, Ngoc, NRR/DLR/RLRA, 415-1458 | |
| References | |
| TAC MC3272, TAC MC3273 | |
| Download: ML053290143 (8) | |
Text
November 22, 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 Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos.: 50-220 and 50-410
Enclosure:
As stated cc w/encl: See next page
ML053290143 DISTRIBUTION: See next page Document Name: E:\\Filenet\\ML053290143.wpd OFFICE RLRA:PM DLR:LA RLRA:BC NAME N. Le MJenkins L. Lund DATE 11/16/05 11/16/05 11/22/05
DISTRIBUTION: Ltr. To J. Spina, Re: Nine Mile Nuclear Station, Units 1 and 2, Dated: November 22, 2005, Accession No.: ML053290143 HARD COPY DLR 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 RLRA Staff C. Holden R. Laufer P. Tam B. Fuller, RI E. Knutson, RI J. Trapp, RI T. Mensah T. Koshy P.Y. 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) - BATCH 4 PART I - ENGINEERED SAFETY FEATURES AND STEAM AND POWER CONVERSION SYSTEMS (UNIT 2) a-RAI 3.4.2.B-1 In ALRA Table 3.4.2.B-2, the applicant states that the aging effects, cracking and loss of materials in the fiberglass tanks exposed to a treated water, temperature <140oF and low flow environment, would be managed with a One-Time Inspection Program. Please provide justification to assure that a one-time inspection alone is adequate to manage the aging effects identified. It also is the staffs understanding that the tank nozzles are connected to rubber expansion joints or flanges. Please discuss how the aging effects of these joints or flanges would be managed. In addition, please provide the NMP operational experience with these tanks and the bases for identifying the aging effects for the specific fiberglass (Altac 382 resin) in this environment.
a-RAI 3.4.2.B-2 In ALRA Table 3.4.2.B-4, the applicant states that loss of material in wrought austenitic stainless steel T quenchers, piping and fittings, exposed to demineralized untreated water, and low flow environment would be managed with a One-Time Inspection Program. Please provide justification to assure that a one-time inspection alone is adequate to manage the aging effect. Also discuss the specifics of the tests and inspections for these components.
a-RAI 3.2.2.B-1 In ALRA Table 3.2.2.B-6, the applicant states that loss of material in wrought austenitic stainless steel heaters, valves, piping and fittings and aluminum, aluminum alloyed with manganese, magnesium and magnesium plus silicon valves exposed to air with moisture or wetting temperature <140oF, would be managed with a One-Time Inspection program. Please provide justification to assure that a One-Time Inspection alone is adequate to manage the aging effect. In addition, please discuss the specifics of the tests and inspections for these components.
PART II - CORE PLATE HOLD-DOWN BOLTS (UNIT 2)
Please provide commitment for the Core Plate Hold-Down Bolts for NMP2. The staff considers that the applicant shall either: (1) Install core plate wedges (as part of a proposed core shroud tie-rod repair) to eliminate the need for the enhanced inspections of the core plate hold-down bolts recommended by BWRVIP-25; or (2) Perform an analysis (incorporating detailed flux/fluence analyses and improved stress relaxation correlations) in accordance to BWRVIP-25 to demonstrate that the core plate hold-down bolts and the core plate can withstand all normal, emergency, and faulted loads considering the effects of stress relaxation, until the end of the period of extended operation. The analysis shall be submitted for staff review and approval 2 years prior to entering the license renewal period.
PART III - CONFIRMATION REGARDING AMR TABLES ON REACTOR VESSEL a-RAI 3.1.2.A-1 For the AMR in Tables 3.1.2.A-1 (ALRA Page 3.1-44) and 3.1.2.B-1 (ALRA Page 3.1-75) on loss of material for penetrations (core differential pressure, CRD stub tube, flux monitor, etc.)
crediting the Flow-Accelerated Corrosion Program, confirm that the mechanism for loss material is flow-accelerated corrosion only. If other loss of material mechanisms are applicable, please identify them.
a-RAI 3.1.2.A-2 For the AMR in Tables 3.1.2.A-1 (ALRA Page 3.1-45) and 3.1.2.B-1 (ALRA Page 3.1-75) on loss of material for support skirt and attachment welds, crediting the ASME Section XI ISI Program, confirm that the mechanism for loss material is general, pitting, or crevice corrosion only. If other loss of material mechanisms are applicable, please identify them.
a-RAI 3.1.2.A-3 For the AMR in Tables 3.1.2.A-1 (ALRA Page 3.1-46) and 3.1.2.B-1 (ALRA Page 3.1-76) on loss of material for top head (closure studs and nuts), crediting the Reactor Head Closure Studs Program, confirm that the mechanism for loss material is general, pitting, or crevice corrosion only. If other loss of material mechanisms are applicable, please identify them.
a-RAI 3.1.2.A-4 For the AMR in Table 3.1.2.B-2 (ALRA Page 3.1-83) on cracking for the core shroud head bolts, crediting the BWRVIP program and the Water Chemistry Program, confirm that the mechanism for cracking is SCC/IGSCC only. If other cracking mechanisms are applicable, please identify them.
a-RAI 3.1.2.B-1 For the AMR in Tables 3.1.2.B-2 (ALRA Page 3.1-84) on cracking for the core shroud support structures (bolts, brackets, cap screws, etc) crediting the BWRVIP program and the Water Chemistry Program, confirm that the mechanism for cracking is SCC/IGSCC only. If other cracking mechanisms are applicable, please identify them.
a-RAI 3.1.1-1 For Tables 3.1.1.A-1 and 3.1.1.B-1, the applicant credits the ASME Section XI Inservice Inspection (Subsections IWB, IWC, and IWD) Program to manage loss of material for the RPV support skirt. The staff believes that the RPV support skirt is an ASME Class MC support and therefore should be managed under the ASME Section XI ISI Subsection IWF Program.
Please verify whether the aging effect of loss of material of the RPV support skirt should be managed by the ASME Section XI Inservice Inspection (Subsections IWB, IWC, and IWD)
Program or by the ASME Section XI Inservice Inspection (Subsection IWF) Program for NMPNS, Units 1 and 2.
PART IV - SECTION 4.0, TIME-LIMITED AGING ANALYSIS a-RAI 4.2.2-1 During its review of ALRA Section 4.0, Time-Limited Aging Analysis (TLAA), the staff finds that the proper disposition of TLAA 4.2.2 should be that of 54.21 ( c)(1)(iii) instead of the 54.21(
c)(1)(ii) as identified by the applicant in that section. Please clarify.
a-RAI 4.7.4-1 During its review of ALRA Section 4.0, Time-Limited Aging Analysis (TLAA), the staff finds that the commitment as stated by the applicant on page 4.7-7 to be vague. Please provide a commitment to state that the Analysis is to be submitted for the staff review and approval no later than two years prior to entry into the period of extended operation.
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