ML042960081

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Summary of Meeting with Entergy Nuclear Operations, Inc. Re Application for License Amendment Regarding Stretch Power Uprate at IP3 (Tac No. MC3552)
ML042960081
Person / Time
Site: Indian Point 
Issue date: 10/27/2004
From: Milano P
NRC/NRR/DLPM/LPD1
To:
Milano P, NRR/DLPM , 415-1457
References
TAC MC3552
Download: ML042960081 (7)


Text

CONTACT:

Patrick D. Milano 301-415-1457 NRR/DLPM October 27, 2004 LICENSEE:

Entergy Nuclear Operations, Inc.

FACILITY:

Indian Point Nuclear Generating Unit No. 3 (IP3)

SUBJECT:

SUMMARY

OF SEPTEMBER 14, 2004, MEETING WITH ENTERGY NUCLEAR OPERATIONS, INC., ON APPLICATION FOR LICENSE AMENDMENT REGARDING STRETCH POWER UPRATE AT IP3 (TAC NO. MC3552)

On September 14, 2004, a Category 1 public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the licensees application dated June 3, 2004 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML041620508, ML041620616, and ML041630103), for an amendment to increase licensed power by 4.85% at IP3. A list of attendees is provided as Enclosure 1.

The licensee presented information on its June 3 application and the supporting analyses described in its licensing report. The presentation closely followed the information presented in its handout slides (see Enclosure 2). The information covered the basic content of the application and specific differences between the power uprate applications for IP2 and 3. The licensee discussed the systems, components, and analyses that would be affected or modified because of the uprate such as the modifications to the high-head safety injection flow control valves, high and low pressure turbines, and main transformer monitoring system. Those systems, components, or analyses that are unaffected remain within the current design and licensing bases for the facility. As was done for the IP2 application, the licensee indicated that, in certain cases, an engineering evaluation was conducted to ensure that the analysis of record did not require a revision. The licensee also described the large-break loss-of-coolant accident analyses that were performed, including the methodologies used, to support the uprated conditions. Further, the licensee detailed the proposed changes in key analyses assumptions, analytical methods, and Technical Specifications requirements.

The NRC staff queried the licensee in several areas. The staff asked questions about: (1) the inclusion in the application of any requested approvals from the NRC to accomplish the power uprate, (2) the methodology used to determine instrument setpoints, (3) the core design at the time of implementation, and (4) the staff questions identified during the review of the IP2 power uprate application that are applicable to IP3, in particular, issues associated with the analysis of a malfunction of the charging and volume control system (CVCS) and pressurizer fracture integrity evaluation.

In response to the questions from the NRC staff, the licensee provided the following information. First, the licensee discussed the approvals that were being requested in the power uprate application and the use of assumptions described in its separate alternate source term application. Second, the licensee stated that no new instrumentation was being added to accomplish the uprate. The instrument setpoints were evaluated using Method 3 of Instrument Society of America Standard 67.01, with additional conservatism added, and this method would bound the Method 2 approach for those values being changed by the uprate. In response, the NRC staff stated that it would need more data to support the licensees use of Method 3 versus Method 2 for determination of allowable values. Third, the licensee stated that because of the mixing grids used in the new fuel design, a mixed core penalty was taken in the analyses.

Fourth, in response to the staffs questions, the licensee stated that it would add some additional clarifications about the design basis for the CVCS analysis, conformance with 10 CFR 50.68, and the calculation of stress intensities in the pressurizer fracture integrity evaluation. Lastly, the licensee stated that it would review the applicability of the staffs questions raised during the review of the IP2 application to IP3. These questions would be addressed by the licensee separately from any staff questions specific to IP3.

Members of the public were not in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to Patrick D. Milano 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. 50-286

Enclosures:

As stated cc w/encls: See next page In response to the questions from the NRC staff, the licensee provided the following information. First, the licensee discussed the approvals that were being requested in the power uprate application and the use of assumptions described in its separate alternate source term application. Second, the licensee stated that no new instrumentation was being added to accomplish the uprate. The instrument setpoints were evaluated using Method 3 of Instrument Society of America Standard 67.01, with additional conservatism added, and this method would bound the Method 2 approach for those values being changed by the uprate. In response, the NRC staff stated that it would need more data to support the licensees use of Method 3 versus Method 2 for determination of allowable values. Third, the licensee stated that because of the mixing grids used in the new fuel design, a mixed core penalty was taken in the analyses.

Fourth, in response to the staffs questions, the licensee stated that it would add some additional clarifications about the design basis for the CVCS analysis, conformance with 10 CFR 50.68, and the calculation of stress intensities in the pressurizer fracture integrity evaluation. Lastly, the licensee stated that it would review the applicability of the staffs questions raised during the review of the IP2 application to IP3. These questions would be addressed by the licensee separately from any staff questions specific to IP3.

Members of the public were not in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to Patrick D. Milano 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. 50-286 Attachments: As stated cc w/encls: See next page DISTRIBUTION:

PUBLIC PDI-1 Reading C. Holden J. Wermeil J. Hannon J. Calvo E. Imbro W. Bateman W. Ruland M. Tshiltz R. Laufer J. Uhle R. Dennig J. Dixon-Herrity L. Raghavan R. Jenkins E. Marinos S. Coffin P. Milano S. Little M. Barillas L. Lois Y. G. Hsii F. Orr M. Shuaibi D. Reddy H. Li J. Collins J. Cushing B. Elliott J. Terrell J. Hayes N. Trehan P. Qualls R. Lobel C-I Wu W. Lyon T. Mensah J. Jolicoeur, OEDO B. McDermott, R-I G. Matakas, R-I OGC ACRS ACCESSION NO.: ML042960081 OFFICE PDI-1:PM:

PDI-1:LA SRXB:SC SPLB:SC EMCB:SC EEIB:SC PDI-1:SC NAME PMilano SLittle JUhle JHerrity SCoffin EMarinos RLaufer DATE 10/ 20/04 10/20/04 10/05/04 10/14/04 10/19/04 10/15/04 10/25/04 Official Record Copy

Indian Point Nuclear Generating Unit No. 3 cc:

Mr. Gary J. 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 T. Herron Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Mr. Fred Dacimo Site Vice President 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. Danny L. Pace Vice President Engineering Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Mr. Brian OGrady 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 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. James Comiotes Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric Conroy Manager, Licensing Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 1 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. 3 cc:

Senior Resident Inspectors Office Indian Point 3 U. S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle 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. 3 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. 3 SEPTEMBER 14, 2004 NRC Staff:

Name William Ruland Stephanie Coffin Patrick Milano Y. Gene Hsii Martha Barillas Frank Orr Lambros Lois Devender Reddy John Hayes Jay Collins Joseph Terrell Hulbert Li Narinder Trehan John Wu Jack Cushing Title Director Section Chief Sr. Project Manager Sr. Reactor Engineer Reactor Systems Engineer Reactor Systems Engineer Sr. Nuclear Engineer Reactor Systems Engineer Sr. Health Physicist Materials Engineer Materials Engineer Sr. Electrical Engineer Electrical Engineer Mechanical Engineer Environmental Project Manager Organization NRR/Division of Licensing Project Management (DLPM)/Project Directorate III NRR/Division of Engineering(DE)/Materials and Chemical Engineering Branch (EMCB)

NRR/DLPM/Project Directorate I NRR/Division of Systems Safety and Analysis (DSSA)/Reactor Systems Branch (SRXB)

NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/Plant Systems Branch NRR/DSSA/Probablistic Safety Assessment Branch NRR/DE/EMCB NRR/DE/EMCB NRR/DE/Electrical and I&C Branch (EEIB)

NRR/DE/EEIB NRR/DE/Mechanical Engineering Branch NRR/Division of Regulatory Improvement Programs/Environmental Section Entergy Nuclear Operations:

Name David Morris Ardesar Irani Kevin Kingsley Walter Wittich John Curry John Jawor Floyd Gumble Title Project Manager, Power Uprates Supervisor, Nuclear Engineering NRR Project Manager Sr. Project Manager Project Manager Shift Manager Project Management Westinghouse Electric Company:

Name Robert Laubham Thomas Timmons William Higby James Grover Kent Bonadio George Konopka Charles Jackson Title Certified Sr. Project Manager Project Manager Principal Engineer Principal Engineer Sr. Engineer Sr. Engineer Consultant Stone and Webster Engineering Corporation:

Name Paul Cafarella Michael Scanlon Title Project Manager Project Engineer Other

Participants:

None