ML040890033
| ML040890033 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/29/2004 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | |
| Milano P, NRR/DLPM 415-1457 | |
| References | |
| Download: ML040890033 (9) | |
Text
March 29, 2004 LICENSEE:
Entergy Nuclear Operations, Inc.
FACILITY:
Indian Point Nuclear Generating Unit No. 2
SUBJECT:
SUMMARY
OF MARCH 9, 2004, MEETING REGARDING STRETCH POWER UPRATE LICENSE AMENDMENT APPLICATION On March 9, 2004, a public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives from Entergy Nuclear Operations, Inc., at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the licensees application dated January 29, 2004, for an amendment to increase the licensed power level by 3.26% at Indian Point Nuclear Generating Unit No. 2 (IP2).
The licensee presented information on the January 29 application and the supporting analyses described in its licensing report. The presentation closely followed the information presented in its handout slides. The information covered the basic organization and content of the application, the licensee processes that were undertaken to identify the systems, components, and analyses that would be affected or modified because of the uprate. Those systems, components, or analyses that are unaffected remain within the current design and licensing bases for the facility. The licensee indicated that, in certain cases, an engineering evaluation was conducted to ensure that the analysis of record did not require a revision. Specifically, the licensee detailed the proposed changes in key analyses assumptions, analytical methods, and Technical Specifications requirements. Finally, the licensee discussed the plant equipment and procedural modifications needed to support the power uprate.
The staff queried the licensee about several issues. The staff's questions related to (1) the material degradation program and licensee's assessment of the effects from uprate conditions, (2) changes in the fuel design and mixed core penalties, (3) spent fuel pool analysis because of the revised fuel design, (4) more clarity and specificity about: satisfying existing licensing basis criteria and regulatory commitments and identification of any exceptions that are proposed, the safety impact of the power uprate on balance-of-plant systems, and the scope and justification of changes in the balance-of-plant area that require NRC review and approval, (5) the method used to determine allowable values for reactor protection system (RPS) and engineered safety features actuation system (ESFAS) parameters being revised for the uprate, (6) plans for vibration monitoring, and (7) plans for startup testing.
In response to the questions from the NRC staff, the licensee provided the following information. First, the licensee indicated that it will continue to monitor any industry initiatives and will identify any differences in the material degradation program results that may be different from those expected. Second, all of the applicable analyses for the power uprate were based on the upgraded fuel design characteristics that bound the existing fuel and the upgraded fuel planned for operating cycle 17. The upgraded fuel includes such aspects as a new grid design to provide additional margin for grid-to-rod fretting. Westinghouse indicated that the hydraulic resistance of the upgraded fuel is not significantly different from the hydraulic resistance of the existing IP2 fuel. The licensee agreed to provide a description of the upgraded fuel design, explain the impact of a mixed core under uprate conditions, and clarify what NRC approval is needed to implement the new fuel. The staff found that the submittal was not clear about the transition to the upgraded fuel. The licensee recognized that a core penalty may be needed when fuel designs are mixed. The licensee also agreed to evaluate the need for a new loss-of-coolant accident (LOCA) analysis addressing >50 F changes per 10 CFR 50.46(a)(3)(i). In this regard, the licensee would need to provide the methodology used to perform the LOCA analysis. If the fuel rod design computer code PAD-4 was used, this fact should be stated in the title. Third, the licensee acknowledged that spent fuel pool criticality should be addressed in the submittal, including how it is affected, if at all, by the upgraded fuel.
The licensee should also define if the requirements of 10 CFR 70.24 or 50.68 apply. Fourth, the licensee stated that it would provide clarifying information to better identify the extent to which systems, components, and analyses are affected by the uprate conditions. This information would focus on the licensees review of its design and licensing basis criteria, including prior commitments and responses to NRC generic communications, to identify the needed changes, any effects on safety, and the rationale for acceptance. In this regard, the licensee would also provide a means to identify references included in other sections of the report. For unaffected areas, the licensee would explain why there was no impact or the performance was bounded. Fifth, the licensee agreed to provide a description of the methodology that will be used to determine allowable values for RPS and ESFAS parameters.
Sixth, the licensee would provide additional details about its plans for vibration monitoring during the implementation period for the power increase. Lastly, the licensee indicated that it would clarify those areas where its analyses indicate that design and operating margins are impacted and describe in more detail the program to test acceptability during startup.
In addition to the general discussion above, the NRC staff is supplying the following details to support its concern regarding an issue that was addressed in a limited manner during the meeting:
1.
The primary and secondary systems safety valve capacities for IP2 were probably originally justified using WCAP-7769, Revision 1, Overpressure Protection for Westinghouse PWRs [pressurized-water reactors], dated 1972. Since the surge rates for the safety valves under pressurization transient conditions would likely be affected, it should be confirmed that this report still applies to IP2.
A member of the public was in attendance. Public Meeting Feedback forms were not received.
Enclosure 1 is a list of meeting attendees, and Enclosure 2 is a copy of the licensees slides presented at the meeting.
Please direct any inquiries to Patrick Milano, Sr. Project Manager, at 301-415-1457, or pdm@nrc.gov.
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosures:
As stated cc w/encls: See next page Enclosure 1 is a list of meeting attendees, and Enclosure 2 is a copy of the licensees slides presented at the meeting.
Please direct any inquiries to Patrick Milano, Sr. Project Manager, at 301-415-1457, or pdm@nrc.gov.
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosures:
As stated cc w/encls: See next page DISTRIBUTION:
PUBLIC PDI-1 Reading A. Howe J. Wermeil J. Hannon J. Calvo E. Imbro W. Bateman R. Laufer J. Uhle D. Solorio L. Raghavan E. Marinos P. Milano S. Little M. Barillas L. Lois F. Orr A. McMurtray J. Tatum H. Li G. Georgiev J. Cushing J. Quichocho J.Terrell J. Cai M. Hart N. Trehan R. Gallucci R. Lobel T. Mensah J. Jolicoeur, OEDO B. McDermott, R-I C. Bixler, R-I OGC ACRS ACCESSION NO.: ML
- See previous concurrence OFFICE PDI-1:PM:
PDI-1:LA SRXB:SC SPLB:SC EMCB:SC&*
EEIB:SC PDI-1:SC NAME PMilano SLittle JUhle DSolorio GGeorgiv for TChan HGarg for EMarinos RLaufer DATE 03/ 22/04 03/22/04 03/27/04 03/25/04 03/18/04 03/22/04 03/29/04 Official Record Copy
Indian Point Nuclear Generating Unit No. 2 cc:
Mr. Gary Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John Herron Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Fred Dacimo Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Christopher Schwarz General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Dan Pace Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Randall Edington Vice President Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John McCann Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Comiotes Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric Conroy Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P. O. Box 249 Buchanan, NY 10511-0249 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Indian Point Nuclear Generating Unit No. 2 cc:
Senior Resident Inspector, Indian Point 2 U. S. Nuclear Regulatory Commission 295 Broadway, Suite 1 P.O. Box 38 Buchanan, NY 10511-0038 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy Electric Division New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Ray Albanese Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. William DiProfio PWR SRC Consultant 139 Depot Road East Kingston, NH 03827 Mr. Dan C. Poole PWR SRC Consultant 20 Captains Cove Road Inglis, FL 34449 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Mr. Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Mr. Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Mr. Karl Coplan Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Robert D. Snook Assistant Attorney General State of Connecticut 55 Elm Street P.O. Box 120 Hartford, CT 06141-0120
Indian Point Nuclear Generating Unit No. 2 cc:
Mr. David Lochbaum Nuclear Safety Engineer Union of Concerned Scientists 1707 H Street NW, Suite 600 Washington, DC 20006
MEETING ATTENDEES ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 MARCH 9, 2004 NRC Staff:
Name R. Laufer L. Raghavan Jennifer Uhle James Tatum Martha Barillas Frank Orr Lambros Lois George Georgiev P. Milano Anthony McMurtray Hulbert Li Michelle Hart Jessie Quichocho Joseph Terrell Narinder Trehan John Wu Jack Cushing Title Section Chief Section Chief Section Chief Sr. Systems Engineer Reactor Engineer Reactor Engineer Sr. Nuclear Engineer Sr. Materials Engineer Sr. Project Manager Sr. Project Manager Sr. Electrical Engineer Health Physicist Nuclear Engineer Materials Engineer Electrical Engineer Mechanical Engineer Environmental Project Manager Organization NRR/Division of Licensing Project Management (DLPM)/Project Directorate I (PDI)
NRR/DLPM/PDIII NRR/Division of Systems Safety and Analysis (DSSA)/Reactor Systems Branch (SRXB)
NRR/DSSA/Plant Systems Branch NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/Division of Engineering (DE)/
Materials and Chemical Engineering Branch (EMCB)
NRR/DLPM/PDI NRR/DLPM/PDIII NRR/DE/Electrical and I&C Branch (EEIB)
NRR/DSSA/Probablistic Safety Assessment Branch NRR/DE/EMCB NRR/DE/EMCB NRR/DE/EEIB NRR/DE/Mechanical Engineering Branch NRR/Division of Regulatory Improvement Programs/RLEP Entergy Nuclear Operations:
Name John McCann Charles Richardson David Morris Ardesar Irani Kevin Kingsley Walter Wittich John Curry John Jawor Title Director, Licensing Manager, Project Management Project Manager, Power Uprates Supervisor, Nuclear Engineering NRR Project Manager Sr. Project Manager Project Manager Shift Manager Westinghouse Electric Company:
Name Robert Laubham Thomas Timmons David Fink Kent Bonadio Jill Monahan Ray Calvo Neil Florentine Charles Jackson Title Certified Sr. Project Manager Project Manager Principal Engineer Sr. Engineer Project Engineer Project Engineer Project Engineer Consultant Stone and Webster Engineering Corporation:
Name Paul Cafarella Michael Scanlon Title Project Manager Project Engineer Other
Participants:
Per Bystedt Project Manager, SKI Sweden