ML043650003

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Request for Additional Information for the Review of Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application,
ML043650003
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 12/22/2004
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: ML043650003 (7)


Text

December 22, 2004 Mr. James A. Spina Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

SUBJECT:

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

Dear Mr. Spina:

By letter dated May 26, 2004, Constellation Energy Group Inc., submitted 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 license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review.

Based on discussions with Mr. Peter Mazzaferro 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 at 301-415-1458 or by 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

ML043650003 DISTRIBUTION: See next page Document Name: E:\\Filenet\\ML043650003.wpd OFFICE RLEP:PM RLEP:SC-A NAME N. Le S. Lee DATE 12/22/04 12/22/04

DISTRIBUTION: Ltr. To J. Spina, Re: Nine Mile Nuclear Station, Units 1 and 2 Dated: December 22, 2004 Accession No.: ML043650003 HARD COPY RLEP RF N. Le (PM)

E-MAIL:

RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski M. Yodder RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis C. Li M. Itzkowitz (RidsOgcMailCenter)

T. Smith M. Lemoncelli 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 OPA

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

LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

RELATED TO:

TLAAs for 4.7.2 MSIV Corrosion Allowance (Unit 2 Only) And Aging Management Program B2.1.11 Closed Cycle Cooling Water System Time Limited Aging Analysis 4.7.2 MSIV Corrosion Allowance (Unit 2 Only)

RAI 4.7.2-1 In the LRA, the applicant stated that flow accelerated corrosion (FAC) is considered negligible for low alloy steel in a dry steam environment, however the time-limited aging analysis (TLAA) includes a calculation for reduction in main steam isolation valve (MSIV) wall thickness due to FAC during plant operation. The applicant further stated that the predicted reduction in MSIV wall thickness due to FAC (7.12 mils) is more than twice the reduction in wall thickness that is predicted to occur while the valve is flooded and subjected to a treated water environment (3.3 mils). This predicted reduction in MSIV wall thickness due to FAC accounts for a significant contribution to the total calculated reduction in wall thickness in the TLAA. Please provide information to justify how FAC in a dry steam environment is considered negligible to the degree that MSIV wall thickness measurements are not specified in the formal FAC program, or identify the applicable program(s) for managing FAC for MSIV at NMP2.

RAI 4.7.2-2 In the LRA, the applicant included in the TLAA Section the use of predictive methods to calculate MSIV wall thinning. In order for the staff to evaluate the accuracy of these predictions, please provide actual measurements of the wall thickness of the MSIVs and the wall thinning that they have experienced. In addition, please provide a discussion of the actual reduction in wall thickness as compared to the reduction in wall thickness that would have been expected using the predictive methods applied in the TLAA.

Aging Management Program B2.1.11 Closed Cycle Cooling Water System RAI B2.1.11-1 The jacket water cooling portion of the NMP1 Emergency Diesel Generator (EDG) System utilizes chromate as a corrosion inhibitor. In contrast, NMP2 employs nitrite as a corrosion inhibitor. When used as a corrosion inhibitor, nitrite does not prevent microbiological growth and, in fact, it serves as a nutrient for certain types of bacteria. Bacteria and microbiologically influenced corrosion (MIC) are frequently found in EDG cooling water systems. Operating experience shows that MIC was previously identified in the NMP1 EDG cooling water. Please discuss why NMP1 and NMP2 utilize different corrosion inhibitors in the EDG jacket cooling water. Please also provide a discussion of the operating experience at both units including the history of MIC at NMP1 and the reasons that you believe the NMP2 EDG cooling system will remain free of microbiological growth while operating with nitrite inhibitors.

RAI B2.1.11-2 Given the operating experience with MIC in the NMP1 EDG jacket cooling water, please provide additional information to explain NMPs conclusion that NMP2 closed cooling water systems will not experience microbiological growth. Please provide a discussion of the testing of closed cooling water systems and the trending of the test results in those systems. For any closed cooling water systems that have experienced microbiological growth (including the NMP1 EDG cooling water system), please describe the corrective actions taken and any lessons learned that have been applied to the corrosion monitoring practices at both NMP1 and NMP2.

Nine Mile Point Nuclear Station, Unit Nos. 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 Winston & Strawn 1400 L Street, NW Washington, DC 20005-3502 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 Mr. James M. Petro, Jr., Esquire Counsel Constellation Energy Group 750 East Pratt Street, 5th 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. Fred Emerson 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 Rd.

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, Unit Nos. 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