ML052310433
| ML052310433 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/24/2005 |
| From: | Holden C NRC/NRR/DLPM/LPD1 |
| To: | Korsnick M Ginna |
| Clarke D, NRR/DLPM/LPD3-1, 301-415-2854 | |
| References | |
| TAC MC7382 | |
| Download: ML052310433 (7) | |
Text
August 24, 2005 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
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - EXTENDED POWER UPRATE ACCEPTANCE REVIEW RESULTS (TAC NO. MC7382)
Dear Mrs. Korsnick:
By letter to the Nuclear Regulatory Commission (NRC) dated July 7, 2005, as supplemented on August 15, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted an application requesting authorization to increase the maximum steady-state thermal power level at the R.E.
Ginna Nuclear Power Plant (Ginna) from 1520 megawatts thermal (MWt) to 1775 MWt, which is a 16.8 percent increase. This requested change is commonly referred to as an extended power uprate (EPU).
The purpose of this letter is to provide the results of the NRC staffs acceptance review of the Ginna EPU application, which is based on the determination that sufficient information was provided to allow the NRC staff to proceed with its detailed technical review. The review also ensures that the application adequately characterizes the regulatory requirements and licensing basis of the plant. The NRC staff used the guidance contained in Review Standard (RS)-001, Revision 0, "Review Standard for Extended Power Uprates," December 2003, for the acceptance review. On the basis of its review of the information provided in the application, the NRC staff has determined that the licensee has provided the necessary and sufficient information for the staff to begin a detailed technical review.
However, during the acceptance review process, the NRC staff found that additional information was needed concerning certain aspects of the small-break loss-of-coolant accident and long-term cooling analyses. Enclosed are specific requests for additional information concerning these items. The need for this supporting information had been identified by the NRC staff during a pre-application meeting on February 3, 2005. Please provide the requested information to the NRC as soon as possible to prevent any delay in the completion of the detailed EPU review.
M. Korsnick In addition, the NRC staff expects to issue a letter requesting additional information in November 2005, and will request that you respond within 60 days of that letter in order to support your requested approval date.
Sincerely,
/RA/
Cornelius F. Holden, Director Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: See next page
M. Korsnick In addition, the NRC staff expects to issue a letter requesting additional information in November 2005, and will request that you respond within 60 days of the letter in order to support your requested approval date.
Sincerely,
/RA/
Cornelius F. Holden, Director Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-1 R/F C. Holden R. Laufer P. Milano J. Stang S. Little J. Trapp, R-I OGC ACRS ADAMS Accession Number: ML050310433 OFFICE PDIII-1\\PM PDI-1\\PM PDI-1\\LA SRXB\\SC PDI-1\\SC PDI-1\\PD NAME JStang PMilano SLittle JNakoski RLaufer CHolden DATE 08/19/05 08/19/05 08/19/05 08/22/05 08/22/05 08/24/05 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 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 Mr. Carey W. Fleming Sr. Counsel - Nuclear Generation Constellation Generation Group, LLC 750 E. 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
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE REVIEW R.E. GINNA NUCLEAR POWER PLANT The following information is required in order for the Nuclear Regulatory Commission staff to complete its review concerning loss-of-coolant accident (LOCA) and long-term cooling analyses.
1.
Regarding the small-break LOCA analysis, the licensee evaluated only the 1.5, 2, and 3-inch diameter line breaks, with only limited plots provided for the 2-inch break, in its application. In its August 15, 2005, supplemental letter, the licensee stated that no core uncovery occurred for 4-inch and 6-inch break sizes. However, the licensee did not provide documentation to support its statement. Further, the integer break spectrum approach is too coarse to identify the worse case peak clad temperature (PCT). Also, the analysis of a severed cold-leg injection line was not provided.
Provide: (1) an analysis of break sizes up to and including 1.0 ft2 in area, including break sizes other than integer break sizes to demonstrate that the worst break has been identified, (2) the major response parameters for the break spectrum, and (3) the NOTRUMP nodalization diagram.
2.
There were no quantitative analysis results supplied justifying the operator action time to reinitiate cold-side injection to control boric acid precipitation following a LOCA. No boron concentration vs. time curves were provided for the limiting breaks. No analyses of breaks where the reactor coolant system pressure remains above the residual heat removal pump shut off head were provided nor was the effect of the timing for reinitiating cold-side injection identified to show sufficient time exists to control boric acid concentration for small breaks. The margin in flushing flow was not identified nor was the time needed to turn around the boric acid concentration once flushing begins. The details of how the boron concentration was calculated was also not provided.
Provide the following information concerning the boron concentration calculation:
a.
Does the mixing volume vary with time?
b.
Was the loop resistance taken into account in calculating the mixing volume?
c.
What constitutes the mixing volume?
The minimum injection temperature and maximum boron concentration in the core was not identified to demonstrate that precipitation is precluded at the time to activate cold-side injection. The 1975 methods cited in the submittal for calculating boric acid concentration contain many unsubstantiated assumptions. See the Westinghouse-CE Topical Report CENPD-254 as an example of the analysis methods and results needed in order to complete the review of long-term cooling performance.
3.
Additional analysis results are also required for the best-estimate large-break LOCA analysis. Only the PCT plot for the hot rod and hot bundle were provided for the limiting break.
Provide the complete analysis results including all of the key major response parameters. Also, did the analysis include downcomer boiling effects and what was the worst single failure if downcomer boiling occurs? What containment pressure was assumed?