ML063200126
| ML063200126 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/29/2006 |
| From: | Le N NRC/NRR/ADRO/DLR/RLRB |
| To: | Peter Dietrich Entergy Nuclear Operations |
| Le N. B., NRR/DLR/RLRB, 415-1458 | |
| References | |
| TAC MD2667 | |
| Download: ML063200126 (8) | |
Text
November 29, 2006 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. MD2667)
By letter dated July 31, 2006, Entergy Nuclear Operations, Inc., submitted an application pursuant to 10 CFR Part 54, to renew the operating license for James A. FitzPatrick Nuclear Power Plant for renew 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 by 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
ML063200126 OFFICE PM:RLRB:DLR LA:RLRA:DLR BC:RLRB:DLR NAME NBLe IKing RAuluck DATE 11/24/06 11/22/06 11/29/06
Letter to Peter Dietrich from N B Le dated November 29, 2006
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF THE LICENSE RENEWAL APPLICATION FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. MD2667)
HARD COPY DLR R/F E-MAIL:
JFair RWeisman AMurphy RPettis GGalletti DShum GBagchi SSmith (srs3)
SDuraiswamy YL (Renee) Li RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrAdes DLR Staff G. Hunegs, SRI E. Cobey R. Lanifer J. Boska
Enclosure REQUEST FOR ADDITIONAL INFORMATION JAMES A. FITZPATRICK LICENSE RENEWAL APPLICATION SECTION 2.4 SCOPING AND SCREENING RESULTS: STRUCTURES RAI 2.4.1-1 Section 2.4-1, Reactor Building and Primary Containment of the LRA, under Inner Refueling Bellows and Bulkhead Assembly does not clearly state the makeup of the bulkhead assembly.
The staff requests the applicant to provide a list of bulkhead assembly components that are within the scope of license renewal and a drawing that depicts the bulkhead assembly.
RAI 2.4.1-2 Table 2.4-1, Reactor Building of the LRA, does not include drywell head closure bolts and double-gasketed drywell head. These components have the intended function of the drywell pressure boundary. The staff requests the applicant to provide justification for not including them in the scope of license renewal.
RAI 2.4.1-3 Table 2.4-1, Reactor Building of the LRA, does not incorporate refueling cavity seal components within the scope of license renewal. The proposed license renewal interim staff guidance LR-ISG-2006-01, Plant Specific Aging Management Program for Inaccessible Areas of Boiling Water Reactor Mark 1 Steel Containment Drywell Shell, which was published in the Federal Register on May 9, 2006, stated that the most likely cause of corrosion of the drywell shell in the sand-pocket areas (near the bottom of the drywell), and in the spherical portion of the drywell at higher elevations, was the water in the gap between the drywell and the concrete shield, and the source of the water was noted as leakage through the seal between the drywell and the refueling cavity and leakage through cracked stainless steel liner of the refueling cavity wall Therefore, the staff requests the applicant include all the refueling cavity seal components within the scope of license renewal and provide a drawing that depicts the refueling cavity seal components.
RAI 2.4.1-4 Table 2.4-1, Reactor Building of the LRA, does not include the metal drywell sump screens that provide functional support for safety-related equipment. The staff requests the applicant to provide justification for not including them in the scope of license renewal.
RAI 2.4.1-5 Table 2.4-1, Primary Containment of the LRA, does not include the reinforced concrete shield plugs that provide shielding over the top of the drywell. Exclusion of the reinforced concrete shield plugs from the scope of license renewal may lead to long-term unmanaged degradation of the plugs (e.g., full sectional concrete cracking, rebar corrosion, loss of bond, partial spalling or cracking of concrete due to handling, loss of load carrying capacity of plug attachments, etc.)
with a seismic II/I implication, potentially affecting the structural integrity of the drywell head.
The staff requests the applicant to provide justification for not including them in the scope of license renewal.
RAI 2.4.1-6 Table 2.4-1, Primary Containment of the LRA, does not incorporate spent fuel racks neutron absorbing material within the scope of license renewal. Long-term unmanaged degradation of the component may excessively reduce the margin of nuclear subcriticality in the fuel pool. The staff requests the applicant to provide justification for not including them in the scope of license renewal.
RAI 2.4.2-1 Section 2.4-2, Water Control Structures of the LRA, under Discharge Tunnel states that failure of this Class II structure could impact the proper operation of the emergency service water system. The staff needs additional information regarding the potential consequences of the Screenwell-Pumphouse (Class II structure) failure. Specifically, the licensee is requested to confirm that appropriate measures have been taken to preclude the failure of this structure which might have adverse effects on the proper operation of the emergency service water system.
RAI 2.4.2-2 Table 2.4-2, Water Control Structures of the LRA, do not include anchors, and post-tensioned tendons for the Intake Structure that anchor the main structure to the natural bedrock below the lake bottom. The staff requests the applicant to provide justification for not including them in the scope of license renewal and also provide a summary of operating experience regarding settlement of the intake structure.
RAI 2.4.2-3 Table 2.4-2, Water Control Structures of the LRA, lists Beams, columns, floor slabs and walls as a component and Exterior walls as another component. The staff requests the applicant to provide clarifications for the two different components by listing all structural members under each component.
RAI 2.4.3-1 Section 12.3.9, Main Stack of the UFSAR, states that The stack is not specifically designed to resist a tornado. The staff needs additional information regarding the potential interaction between some seismic Class II SSCs and the tornado-induced failure of the main stack.
Specifically, the licensee is requested to confirm that appropriate measures have been taken to preclude potential interactions between the main stack and some other nearby seismic Class I and Class II SSCs, whose failure might have adverse effects on seismic Class I SSCs.
RAI 2.4.3-2 Section 2.4-3, Turbine Building Complex and Yard Structures, of the LRA under Turbine Building (TB), including Feedwater Heater Bay (HBAY) states that The main steam lines to the turbine generator from the reactor are housed in a reinforced concrete tunnel that enters the turbine building after passing under the adjacent administration building. The staff needs additional information regarding the potential interaction between the administration building and the failure of main steam lines. Specifically, the licensee is requested to confirm that appropriate measures have been taken to preclude the failure of the main steam lines that might have adverse effects on the administration building.
RAI 2.4.3.-3 Table 2.4-3, Turbine Building Complex and Yard Structures of the LRA, lists Exterior walls as a component. The staff is unable to determine whether this component include main stack, main steam line tunnel, and electric bay tunnel. If not, the staff requests the applicant to include these components in the scope of license renewal.
RAI 2.4.3-4 Table 2.4-3, Turbine Building Complex, and Yard Structures of the LRA, does not include sumps that provide functional support for safety and nonsafety-related equipment. The staff requests the applicant to provide justification for not including them in the scope of license renewal.
RAI 2.4.4-1 Table 2.4-4, Bulk Commodities of the LRA, provides a list of bulk commodities for the Fitzpatrick Nuclear Power Plant. The location of each component is unclear to the staff. The staff requests the applicant to describe all commodities on the list as well as to provide a comprehensive listing of components, component supports and locations for each commodity.
RAI 2.4.4-2 Table 2.4-4, Bulk Commodities of the LRA, lists Insulation with its intended functions. It is unclear to the staff why Support for Criterion (a)(1) equipment is not part of the intended functions when Table 2.0-1defines the intended function of insulation as provide insulating characteristics to reduce heat transfer, which is meant to apply to safety related and non-safety related components. The staff requests the applicant to provide additional information on insulation and a list of in-scope components that have insulation included with their intended functions.
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 U. S. Nuclear Regulatory Commission Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant 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:
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. James Ross Nuclear Energy Institute 1776 I Street, N.W. Suite 400 Washington, D.C. 20006-3708 Mr. Rick Plasse Project Manager, License Renewal Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Oswego County Administrator Mr. Steven Lyman 46 East Bridge Street Oswego, NY 13126 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406