ML031390404
| ML031390404 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/16/2003 |
| From: | Subbaratnam R NRC/NRR/DRIP/RLEP |
| To: | |
| Subbaratnam R NRR/DRIP/RLEP, 415-1478 | |
| References | |
| Download: ML031390404 (7) | |
Text
May 16, 2003 LICENSEE:
Rochester Gas & Electric (RG&E)
FACILITY:
R. E. Ginna Nuclear Power Plant (Ginna)
SUBJECT:
SUMMARY
OF TELECOMMUNICATION WITH ROCHESTER GAS &
ELECTRIC CORPORATION (RG&E) TO DISCUSS THE RESPONSE TO THE LICENSE RENEWAL APPLICATION (LRA) RAIs 4.2.1.-1 and 4.2.2. R. E. GINNA NUCLEAR POWER PLANT (Ginna)
On April 23, 2003, the NRC staff (the staff) and representatives from RG&E held a telecommunication (telecon) to discuss the draft response from RG&E dated April 11, 2003, to the NRC staff request for additional information (RAI). The telecon related to the use of Regulatory Guide 1.190 to perform the neutron fluence calculation in reply to the staff RAI 4.2.2-1. The staff requested clarification of the data contained in the vendor report WCAP-15885, Revision 0, "R. E. Ginna Heatup and Cooldown Limit Curves for Normal Operation," July 2002, describing the radiation analysis and neutron dosimetry used in Ginnas reactor vessel. A list of telephone participants is enclosed.
Staff Question:
The staff requested clarification for the calculated maximum pressure vessel exposures (fluence) shown in Tables 6 and 7 of WCAP-15885, as a function of cumulative operating time (Effective Full Power Years, (EFPY)). Specifically, the staff was concerned about the calculated maximum fluence of the intermediate to nozzle shell circumferential weld and the nozzle shell course clad/base metal interface values as shown in Table 7 at 54 EFPY. These were shown to be in the order of magnitude of E+18. This value seemed low when compared with corresponding values for clad/base metal interface fluence values shown in Table 6, which were approximately at E+19. The staff thought the value of the fluence calculated in Table 7 seemed rather low, as they could not readily corroborate a physical location in the shell courses that corresponded to this fluence. The staff felt the calculational location may not be lying in the vessel belt line.
Telecon Discussion:
The licensee informed the staff that the circumferential weld was located 10-inches above the upper active fuel region. The licensee proposed that they will resolve the issue either by performing additional three dimensional computations by including additional shell regions beyond the current extent, and verify the accuracy and the validity of reported fluence values in Table 7. This alternative will involve additional effort and cost. Alternatively, the licensee indicated they could perform a gross over estimation (by a factor of two) of the fluence at the weld and the results of such overestimate would help identify whether the assumptions are conservative (as indicated by a predicted low value for pressurized thermal shock (PTS)), or if there was indeed a need for a detailed evaluation. The staff agreed with the licensees later approach for resolving the issue. The staff indicated that when the applicant completes the PTS evaluation at 54 EFPY, it will resolve the staff concerns conclusively.
Staff Question:
The staff had a concern regarding Tables 10 thru 14 of WCAP-15885, on the measured sensor specific activities and reaction rate computations pertaining to reactor vessel Capsules V, R, T and S. The issue was the lack of details for the radial adjustments assumptions that the licensee made.
Telecon Discussions:
During the discussion, the licensee explained that the radial adjustment was necessary to account for the distance factor from the center of the capsule (axial level at 158.11 radius) relative to the dosimeter location. The staff was satisfied with the licensees explanations and there were no additional request on this issue.
RG&E has reviewed and did not have any comments on this telecon summary.
/RA Ram Subbaratnam, Project Manager License Renewal Section License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-244
Enclosure:
As stated cc w/encl: See next page Staff Question:
The staff had a concern regarding Tables 10 thru 14 of WCAP-15885, on the measured sensor specific activities and reaction rate computations pertaining to reactor vessel Capsules V, R, T and S. The issue was the lack of details for the radial adjustments assumptions that the licensee made.
Telecon Discussions:
During the discussion, the licensee explained that the radial adjustment was necessary to account for the distance factor from the center of the capsule (axial level at 158.11 radius) relative to the dosimeter location. The staff was satisfied with the licensees explanations and there were no additional request on this issue.
RG&E has reviewed and did not have any comments on this telecon summary.
/RA Ram Subbaratnam, Project Manager License Renewal Section License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-244
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
C:\\ORPCheckout\\FileNET\\ML031390404.wpd OFFICE PM:RLEP:DRIP PM:RLEP:DRIP LA:RLEP:DRIP SC:RLEP:DRIP NAME RSubbaratnam (RArrighi for)
RArrighi YEdmonds SLee DATE 05/14 /2003 05/14 /2003 05/14 /2003 05/16/2003 OFFICIAL RECORD COPY
DISTRIBUTION: Summary of Telecon with OPPD Re: Ginna RAIs, Dated: May 16, 2003 HARD COPY RLEP RF RArrighi RSubbaratnam E-MAIL:
PUBLIC W. Borchardt D. Matthews F. Gillespie C. Grimes RidsNrrDe E. Imbro G. Bagchi K. Manoly W. Bateman J. Calvo C. Holden P. Shemanski H. Nieh G. Holahan H. Walker S. Black B. Boger D. Thatcher G. Galletti C. Li J. Moore R. Weisman M. Mayfield A. Murphy W. McDowell S. Smith (srs3)
T. Kobetz R. Assa S. Duraiswamy C. Munson RLEP Staff L. Lois, DSSA, NRR B. Elliot, DE, NRR
Telecon Participants RG&E NRC George Wrobel, RG&E Ram Subbaratnam, RLEP, NRC Jerry Geiken, RG&E Barry Elliot, DE, NRR Lee Ochino, RG&E Lambros Lois, DSSA, NRR WESTINGHOUSE Stan Anderson
R.E. Ginna Nuclear Power Plant cc:
Kenneth Kolaczyk, Sr. Resident Inspector R.E. Ginna 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 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Daniel F. Stenger Ballard Spahr Andrews & Ingersoll, LLP 601 13th Street, N.W., Suite 1000 South Washington, DC 20005 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 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Alan P. Nelson Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, DC 20006-3708 APN@NEI.ORG George Wrobel Manager, License Renewal R.E.Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario, NY 14519 Mr. Denis Wickham Sr. Vice President Transmission & Supply Energy East Management Corporation P.O. Box 5224 Binghampton, NY 13902 Mr. David F. Wilson R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario, NY 14519