ML17265A552
| ML17265A552 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/25/1999 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17265A553 | List: |
| References | |
| TAC-MA0389, TAC-MA389, NUDOCS 9903020241 | |
| Download: ML17265A552 (6) | |
Text
~p,8 REMI
~ (4 VpO Cy I
fl C
O Cy
<r
~O
~>>*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 25, 1999 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 EastAvenue
'ochester, NY 14649
SUBJECT:
STAFF REVIEW OF THE SUBMITTALBY ROCHESTER GAS AND ELECTRIC COMPANYTO APPLY LEAK-BEFORE-BREAKSTATUS TO PORTIONS OF THE R.E. GINNA NUCLEAR POWER PLANT RESIDUALHEAT REMOVALSYSTEM PIPING (TAC NO. MA0389)
Dear Dr. Mecredy:
By letter dated November 11, 1997, you submitted a request for NRC review and approval of your leak-before-break (LBB) evaluation concerning portions of the R.E. Ginna Nuclear Power P ant residual heat removal (RHR) system piping. Your submittal was made in accordance with the provisions of Title 10 of the Code of Federal Re ulations Part 50, Appendix A, General Design Criteria 4, which permits licensees to exclude the dynamic effects associated
'ith postulated pipe ruptures from the facility's licensing basis if"analyses reviewed and approved by the Commission demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping." LBB evaluations utilizing the guidance of NUREG-1061, Volume 3 and/or Draft Standard Review Plan Section 3.6.3 have been previously approved by the staff as a method for making such a demonstration.
The NRC staff has completed its evaluation of your submittal. The information provided by you in your original submittal, your August 6, 1998 response to the staffs request for additional information, and further information on the Ginna leakage detection system was sufficient to permit the staff to independently evaluate your conclusions.
While the results of the staffs evaluation do differwith yours, the staff agrees with the your conclusion that LBB behavior has been demonstrated for the analyzed portions of the RHR system piping. It should be noted that the staff's conclusion was predicated on your demonstration that the R. E. Ginna leakage detection system inside containment was capable of reliably detecting 0.25 gallons per minute of leakage.
Therefore, the staff finds that you may remove consideration of the dynamic O~gOOG~ gg ~lR W'II 990302024%'990225 PDR ADQCK 05000244 P
R. C. Mecredy effects associated with the postulated rupture of the analyzed portions of the RHR system piping from the licensing basis of R. E. Ginna Nuclear Power Plant.
The Safety Evaluation which addresses the technical basis for the staffs finding is enclosed.
This completes our efforts forTAC No. MA0389.
Sincerely, Guy S. Vissing, Senior oject Manager Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc w/encl: See next page
R. C. Mecredy February 25, 1999 effects associated with the postulated rupture of the analyzed portions of the RHR system piping from the licensing basis of R. E. Ginna Nuclear Power Plant.
The Safety Evaluation which addresses the technical basis for the staff's finding is enclosed.
This completes our efforts for TAC No. MA0389.
Sincerely, ORIGINAL SIGNED BY'ocket No. 50-244
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
Guy S. Vissing, Senior Project Manager Project Directorate l-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket File PUBLIC PDI-1 R/F J. Zwolinski S. Bajwa S. Little G. Vissin'g R. Norsworthy (e-mail SE only)
J. Strosnider K. Wickman S. Barber, Region I
V. Ordaz G. Hubbard P. Drysdale M. Mitchell DOCUMENT NAME: G:FGINNA>LTRAO389.WPD To receive a copy ofthis document, indicate in the box C=copy w/o attachment/enclosure E=co with attachment/enclosure N = No co OFFICE PM:PDI-1 NAME G. Vissi c"
DATE
< /~'Y/99 LA:PDI-1 S. Littl W5't/99 D:PDI-1 S. Ba'wa A%
S 45/99 OFFICIAL',RECORD.COPY
FF I
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, 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. F. William Valentino, 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 Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 Ms. Thetma 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 111 West Falls Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223