ML070120196
| ML070120196 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/19/2007 |
| From: | Le N NRC/NRR/ADRO/DLR/RLRB |
| To: | Peter Dietrich Entergy Nuclear Operations |
| Le, Ngoc, NRR/DLR/RLRB, 415-1458 | |
| References | |
| TAC MD2666 | |
| Download: ML070120196 (9) | |
Text
January 19, 2007 Mr. Peter T. Dietrich Site Vice President James A. FitzPatrick Nuclear Power Plant Entergy Nuclear Operation, Inc.
P.O. Box 110 Lycoming, NY 13093-0110
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF THE LICENSE RENEWAL APPLICATION FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. MD2666)
By letter dated July 31, 2006, Entergy Nuclear Operations, Inc., submitted an application pursuant to Title 10 Code of Federal Regulations (CFR) Part 54, to renew the operating license for James A. FitzPatrick Nuclear Power Plant for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, an area where additional information is needed to complete the review.
Based on discussions with Mr. Rick Plasse 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 via e-mail at nbl@nrc.gov.
Sincerely,
/RA/
N. B. (Tommy) Le, Senior Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
As stated cc w/encl: See next page
ML070120196 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME SFigueroa NBLe SHoffman for RAuluck DATE 01/18/07 01/18/07 01/19/07
Letter to Peter Dietrich, from N B Le, dated January 19, 2007
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF THE LICENSE RENEWAL APPLICATION FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. MD2666)
DISTRIBUTION:
HARD COPY:
DLR R/F E-MAIL:
JFair RWeisman AMurphy RPettis GGalletti DShum GBagchi SSmith (srs3)
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION JAMES A. FITZPATRICK NUCLEAR POWER PLANT LICENSE RENEWAL APPLICATION (LRA)
SECTIONS 2.3.3.2, 2.3.3.9, 2.3.3.10, 2.3.3.11, 2.3.4 Section 2.3.3.2 Service Water RAI 2.3.3.2-1 License Renewal drawing LRA-FM-46A, at locations B6, B7, and B8, shows four isolation valves for the drain lines and four isolation valves on service water (SW) supply lines to the electrical bay cooling units. The License Renewal (LR) boundary for each section of piping ends at the Quality Assurance I (QA-I) boundary including the reducer, however, the isolation valves (isolation valve at each supply line and isolation at each drain line) upstream of the reducer and piping between the reducer and isolation valves labeled as SEISMIC I are not shown as within the scope for LR. Please provide additional information on why these piping and isolation valves are not within the scope for LR and justify the boundary locations with respect to the applicable requirements of Title 10 Code of Federal Regulations (CFR)
Part 54.4(a).
RAI 2.3.3.2-2 License Renewal drawing LRA-FM-20B, at location E5, shows SW piping 22-WS-151-57 as in scope for license renewal. The line is continued on drawing LRA-FM-46A, at location B5. The continuation on LRA-FM-46A does not indicate the piping is in scope nor does it include a license renewal boundary. The line is continued on a third drawing, LRA-FM-36A, which was not provided by the applicant. Please provide additional information on why this section of piping is not within the scope of LR and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a).
RAI 2.3.3.2-3 License Renewal drawing LRA-FM-46A, at location C4, shows SW piping 8 WCS-151-114 continued from drawing LRA-FM-15A, location C1. Valve ESW-23 and piping upstream is labeled QA-I. Neither of the continuation drawings (LRA-FM-15A and LRA-FM-36A) were submitted as part of the License Renewal Application. Please provide additional information as to why this section of QA-1 piping from valve ESW-23 and upstream is not within the scope of LR and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a).
Section 2.3.3.9 Fuel Pool Cooling and Cleanup RAI 2.3.3.9-1 License Renewal drawing LRA-FM-19A, at locations F3 and F4, shows lines W19-151-1A, 1B and 17 from skimmer surge tanks TK-8A and TK-8B to surge tank drain valve VGW-15A as not within the scope of license renewal. The piping and components upstream of VGW-15A are labeled SEISMIC I. Please provide additional information on why these sections of pipe and components are not within the scope for LR and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a).
Section 2.3.3.10 Service, Instrument, and Breathing Air RAI 2.3.3.10-1 License Renewal Drawing LRA-FM-29A-0, at location G7, shows that the in-scope nitrogen supply for reactor coolant pressure boundary air operated valves (AOV) 02AOV-17 and 02AOV-18 does not extend to the actuator but terminates at the downstream side of solenoid operating valves (SOV) SOV-17 and SOV-18, respectively. Please provide additional information clarifying why the in scope boundaries for the nitrogen supply lines to 02AOV-17 and 02AOV-18 do not extend to the actuator and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a).
Section 2.3.3.11 Reactor Building Closed Loop Cooling Water (RBCLCW)
RAI 2.3.3.11-1 License Renewal drawing LRA-FM-15-B, at locations C4, C7, F4, and F7, shows four RBCLCW containment isolation valves on supply lines to the drywell. The LR boundary for each section of piping ends at the AOV, however, piping and components upstream of the boundary are labeled SEISMIC I. Please provide additional information on why the sections of pipe and components listed below are not within the scope for LR and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a):
LR drawing LRA-FM-15-B, location C4, upstream of AOV 130B through valve 23B.
LR drawing LRA-FM-15-B, location C7, upstream of AOV 130A through valve 23A.
LR drawing LRA-FM-15-B, location F4, upstream of AOV 132A through valve 20A.
LR drawing LRA-FM-15-B, location F7, upstream of AOV 132B through valve 20B.
Section 2.3.4.1 Condensate RAI 2.3.4.1-1 Two condensate storage tanks provide the preferred source of water to high-pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) during postulated small pipe breaks.
Each tank must contain a reserve storage capacity of 100,000 gallons and have the capability of being isolated from serving other systems. The tanks are designed to provide the required flow even if the above ground portions of the tanks are destroyed by tornado or earthquake. LR drawing LRA-FM-33-D indicates the LR boundary for system piping other than HPCI and RCIC is the nozzle penetration at the storage tanks, creating the possibility of a non-isolable leak from the tank. Please provide additional information on why the following sections of pipe and components are not within the scope for LR and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a):
LR drawing LRA-FM-33-D, location G7, piping from N-2 to and including valve 37A.
LR drawing LRA-FM-33-D, location G7, piping from N-3 to and including valve 38A.
LR drawing LRA-FM-33-D, location G6, piping from N-11 to and including valve WTR-117A.
LR drawing LRA-FM-33-D, location G6, piping from N-7 to and including valve FPC-724A.
LR drawing LRA-FM-33-D, location G6, piping from N-9 to and including valve CSP-01A.
LR drawing LRA-FM-33-D, location G6, piping from N-8 to and including valve CRD-01A.
LR drawing LRA-FM-33-D, location G6, piping from C-3 to and including valve CRD-02A.
LR drawing LRA-FM-33-D, location H6, piping from N-5 to and including valve 100A.
LR drawing LRA-FM-33-D, location H6, piping from N-10 to and including valve 01A.
LR drawing LRA-FM-33-D, location H6, piping from C-2 to and including valve 101A.
LR drawing LRA-FM-33-D, location G3, piping from N-2 to and including valve 37B.
LR drawing LRA-FM-33-D, location G3, piping from N-3 to and including valve 38B.
LR drawing LRA-FM-33-D, location G4, piping from N-11 to and including valve WTR-117B.
LR drawing LRA-FM-33-D, location G4, piping from N-7 to and including valve FPC-724B.
LR drawing LRA-FM-33-D, location G4, piping from N-9 to and including valve CSP-01B.
LR drawing LRA-FM-33-D, location G4, piping from N-8 to and including valve CRD-01B.
LR drawing LRA-FM-33-D, location G4, piping from C-3 to and including valve CRD-02.
LR drawing LRA-FM-33-D, location H4, piping from N-5 to and including valve 100B.
LR drawing LRA-FM-33-D, location H4, piping from N-10 to and including valve 01B.
LR drawing LRA-FM-33-D, location H4, piping from C-2 to and including valve 101B.
RAI 2.3.4.1-2 Two condensate storage tanks provide the preferred source of water to HPCI and RCIC during postulated small pipe breaks. The tanks are designed to provide the required flow even if the above ground portions of the tanks are destroyed by tornado or earthquake. LR drawing LRA-FM-25-A indicates the LR boundaries on the crosstie line for the two tanks are the nozzle penetrations at the storage tanks, creating the possibility of a non-isolable leak from the tanks.
Please provide additional information on why the following sections of pipe and components are not within the scope for LR and justify the boundary locations with respect to the applicable requirements of 10 CFR Part 54.4(a):
LR drawing LRA-FM-25-A, location H5, piping from N-1 on CST A to and including valve 02A LR drawing LRA-FM-25-A, location H5, piping from N-1 on CST B to and including valve 02B
FitzPatrick Nuclear Power Plant cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Peter T. Dietrich Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Kevin J. Mulligan General Manager, Plant Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwarz Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. David Wallace Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Costedio Manager, Regulatory Compliance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271
FitzPatrick Nuclear Power Plant cc:
Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Steven Lyman Oswego County Administrator 46 East Bridge Street Oswego, NY 13126 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306 Mr. Garrett D. Edwards 814 Waverly Road Kennett Square, PA 19348 Mr. Rick Plasse Project Manager, License Renewal Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708