ML052920510
| ML052920510 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/24/2005 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Ginna |
| Milano P, NRR/DLPM 415-1457 | |
| References | |
| TAC MC7382 | |
| Download: ML052920510 (6) | |
Text
October 24, 2005 LICENSEE:
R.E. Ginna Nuclear Power Plant, LLC FACILITY:
R.E. Ginna Nuclear Power Plant
SUBJECT:
SUMMARY
OF SEPTEMBER 15, 2005, MEETING WITH R.E. GINNA NUCLEAR POWER PLANT, LLC, REGARDING EXTENDED POWER UPRATE APPLICATION (TAC NO. MC7382)
On September 15, 2005, the Nuclear Regulatory Commission (NRC) staff met with representatives of R.E. Ginna Nuclear Power Plant, LLC (the licensee) and its contractor, Westinghouse Electric Company, in a Category 1 public meeting held at the Westinghouse offices at 12300 Twinbrook Parkway, Rockville, Maryland. The purpose of the meeting was to discuss information regarding the licensees application dated July 7, 2005, for a 16.8 percent increase in the maximum steady-state thermal power level at the R.E. Ginna Nuclear Power Plant (Ginna). This level of power increase is generally referred to as an extended power uprate (EPU). A list of attendees is provided as Enclosure 1.
The agenda for this meeting consisted of discussion regarding the small-break loss-of-coolant accident (SBLOCA), long-term cooling, and anticipated transient without scram analyses supporting the EPU application. In particular, the discussion centered on issues presented in the NRC staffs request for additional information on August 24, 2005. The presentation handout slides are provided as Enclosure 2.
For the SBLOCA analyses, information was presented regarding the analyses and modeling that were conducted. Westinghouse stated that the scenarios assumed no upper plenum injection flow. In addition, auxiliary feedwater (AFW) flow was not modeled because it was not required for break sizes down to 1.5 inches and no core uncovery occurred for about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The NRC staff asked the licensee to state when AFW flow would occur, the assumed flow rate, and the plant response at the time of AFW actuation (i.e., decay heat, steam generator tube uncovery). The staff also questioned whether the AFW flow requirements for an SBLOCA were more restrictive than for other postulated events. The NRC staff also requested that the licensee consider the best approach when performing an analysis of an injection line break.
Lastly, the staff asked the licensee to describe the reactor coolant system (RCS) loop seals in terms of plant elevation and the top of the active core.
Regarding the effects of long-term cooling and boric acid participation, information was presented about the various break sizes and locations that were reviewed. For 2-loop pressurized-water reactors, analyses are performed include: (a) a subcriticality analysis using sump boron concentration, (b) a boric acid participation evaluation using the simplified method presented in a 1975 NRC letter, and (c) a decay heat removal analysis for required recirculation flows. Currently, Ginna has a 20-hour boric acid precipitation action time. For intermediate size breaks, the emergency operating procedure (EOP) require the plant to be depressurized to the upper plenum injection (UPI). Using the plant simulator, the licensee will run several events for various break sizes to validate the 6-hour UPI point and to assess the latest possible time to start a plant cooldown for depressuization and to determine if additional analyses will be needed to evaluate break sizes where pressure could hold above the UPI point. These assessments may help maximize the margins to increase flexibility in the EOPs. The NRC staff also requested that the mixing volume versus time be evaluated when justifying the precipitation limit, in particular when the volume level gets to the top of the core. Overall, the licensee stated that it was reviewing a proposed approach to resolve the issues in this area.
The approach would include: (a) an Appendix K decay heat analysis, (b) assessment of core voiding as a function of time, (c) computing boric acid concentration versus time and revising EOP actions, as necessary, and (d) addressing boric acid participation.
For non-LOCA transients and accidents, the NRC staff indicated that adequate information had not been included in the application to fully support whether, at EPU conditions, the existing design-basis calculations are bounding for each non-LOCA transient described in the licensees updated final safety analysis report (UFSAR). The licensee committed to submit the following information in a future supplement to address this issue:
1.
assumptions and other initial plant conditions used in each non-LOCA transient analysis; 2.
methodology and modeling used for each calculation; 3.
verification that the methodology been approved by the NRC for each application, and provide any differences from the code methodologies; and 4.
detailed results of the calculations to determine margins between current and EPU conditions and to show that the current design-basis calculations bound the plant at EPU conditions In particular, the NRC staff requested more details about (a) the steam generator modeling to determine levels during a feedwater line break, (b) verification of the P-7 and P-9 setpoints adjustment, (c) shutdown margins during steam line breaks in single and dual loop operation, and (d) the time to fill the pressurizer in the event of the inadvertent operation of the chemical and volume control system and operator actions to terminate the event.
During the meeting, the licensee also discussed the proposed power ascension and testing plans associated with the implementation of the EPU. The licensee presented information to the NRC staff that was later included in a supplement to the July 7, 2005, application dated September 30, 2005.
Lastly, the NRC staff raised concerns regarding the EPU effects on Ginnas compliance with 10 CFR 50.68, Criticality accident requirements. The licensee committed to address this issue in a future supplement.
Members of the public were not in attendance. Public meeting feedback forms were not received.
Please direct any inquiries to Patrick Milano at 301-415-1457 or pdm@nrc.gov.
/RA/
Patrick Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout cc w/encls: See next page Members of the public were not in attendance. Public meeting feedback forms were not received.
Please direct any inquiries to Patrick Milano at 301-415-1457 or pdm@nrc.gov.
/RA/
Patrick Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout cc w/encls: See next page DISTRIBUTION PUBLIC PDI-1 Reading File C. Holden R. Laufer J. Nakoski P. Milano J. Stang S. Miranda L. Ward K. Wood S. Little M. Barillas J. Burns P. Prescott, NRR R. Taylor J. Trapp, R-I OGC ACRS Accession No.: ML052920510 Package No.: ML052920515 OFFICE PDI-1/PM DLPM/LPM PDI-1/LA SRXB/SC PDI-1/SC NAME PMilano JStang SLittle JNakoski RLaufer DATE 10/19/05 10/19/05 10/20/05 10/20/05 10/20/05 OFFICIAL RECORD COPY
R.E. Ginna Nuclear Power Plant cc:
Mr. Michael J. Wallace President R.E. Ginna Nuclear Power Plant, LLC c/o Constellation Energy 750 East Pratt Street Baltimore, MD 21202 Mr. John M. Heffley Senior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519 Kenneth Kolaczyk, Sr. Resident Inspector R.E. Ginna Nuclear Power Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Carey W. Fleming, Esquire Senior Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200 Rochester, NY 14624 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 MEETING ATTENDEES R.E. GINNA NUCLEAR POWER PLANT, LLC R.E. GINNA NUCLEAR POWER PLANT SEPTEMBER 15, 2005 NRC Staff:
Name Chu-Yu Liang Samuel Miranda Robert Taylor Leonard Ward Kent Wood Joseph Burns Martha Barillas Patrick Milano John Stang Title Acting Section Chief Reactor Engineer Reactor Engineer Sr. Reactor Engineer Reactor Engineer Reactor Engineer Reactor Engineer Sr. Project Manager Sr. Project Manager Organization NRR/Division of Systems Safety and Analysis (DSSA)/Reactor Systems Branch (SRXB)
NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/Division of Licensing Project Management/Project Directorate I NRR/DLPM/Power Uprate Lead Project Manager Constellation Energy/R.E. Ginna Nuclear Power Plant, LLC:
Name Mark Finley George Wrobel Title Manager, Power Uprates Manager, Licensing Westinghouse Electric Company:
Name David Sklarsky Dave Dominicis Dave Fink Pat Vaughn Andy Gagnon Brett Kellerman Jeff Kobelak Josh Hartz Chris McHugh Steve Love Ed Monahan Other
Participants:
None