ML17264A286
| ML17264A286 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/07/1995 |
| From: | Zimmerman R NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M89516, NUDOCS 9512130099 | |
| Download: ML17264A286 (6) | |
Text
~ll 4Egy 0
Op AnO I
0 gO
++*++
UNITED STATES NUCLEAR REGULATORY COMMISStON WASHINQTONOC2055&0001 December 7,
1995 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
R.
E.
GINNA NUCLEAR POWER PLANT CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS RESOLUTION OF THE GINNA DESIGN BASIS FOR REFUELING ACCIDENTS (TAC NO. M89516)
Dear Dr. Mecredy:
As part of your application for a license amendment to convert the R.
E. Ginna Nuclear Power Plant Technical Specifications to the improved Standard Technical Specification (STS) for Westinghouse
- plants, Rochester Gas and Electric (RG8E) proposed to relocate the provisions for containment integrity during refueling conditions, on the basis that these requirements do not satisfy the criteria for Technical Specification (TS) content as specified in 10 CFR 50.36.
RG&E concluded that the containment integrity provision does not satisfy the TS criteria because the Ginna design basis fuel handling accident assumes that there is no containment capability.
The NRC staff concluded that the containment capability should be retained in the TS.
This issue was discussed during an appeal meeting on November 16, 1995.
The Ginna license has included requirements for containment integrity during refueling conditions since the license was originally issued in 1969, but the basis for that requirement was not clearly stated.
The improved STS for Westinghouse
- plants, NUREG-1431, include provisions for containment integrity for refueling conditions, on the basis that this function satisfies "Criterion 3" in 10 CFR 50.36.
Briefly stated, Criterion 3 includes those structures, systems or components that constitute the "primary success path" to mitigate design basis accidents and transients.
During the development of the improved STS, Criterion 3 was typically applied to those safety functions which are relied upon in design basis accidents and transients.
In this circumstance,
- however, the design basis for fuel handling accidents has historically separated the radiological consequences from the containment capability.
Accordingly, the staff has treated the containment capability for fuel handling conditions as a logical part of the "primary success path" to mitigate fuel handling accidents, irrespective of the assumptions used to calculate the radiological consequences of such accidents.
On this basis, the staff has concluded that the Ginna conversion to the improved STSs must retain the containment integrity provisions for fuel handling conditions.
The NRC staff intends to modify the STS Bases to 95i2i300'P'P 95i207 PDR ADOCK 05000244, P
ln
R. Hecredy )
g,~
p 1
a a+ V t
A handfing 'condifions. 'h5'NRC staff intends to modify the STS Bases to genericaTly clarify"the applicability of the TS criteria to fuel handling accidents for all plants.
Your conversion application should be modified accordingly.
In the event that RG&E wishes to appeal this position, you should make arrangements for an appeal meeting formally and promptly, in order to avoid any delay in the completion of the staff's review of the conversion amendment.'incerely, Docket No. 50-244 cc:
See next page y P.
i erman socia Director for Projects ffice of Nuclear Reactor Regulation
Dr. Robert C. Mecredy R.E.
Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior 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. Williams Valentino, President New York State
- Energy, Research, and Development Authority 2 Rockefeller Plaza
- Albany, NY 12223-1253 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston
& Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 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 ill West Fall Road, Room ll Rochester, NY 14620
R. Hecredy handling conditions.
The NRC staff intends to modify the STS Bases to generically clarify the applicability of the TS criteria to fuel handling accidents for all plants.
Your conversion application should be modified accordingly.
In the event that RGKE wishes to appeal this position, you should make arrangements for an appeal meeting formally and promptly, in order to avoid any delay in the completion of the staff's review of the conversion amendment.
Sincerely, Original signed by:
Docket No. 50-244 cc:
Se'e next page Distribution:...
Docket'File,-
PUBLIC PDI-1 Reading RZimmerman
- SVarga,
'Zwolinski LHarsh
- SLittle, AJohnson GHolahan CHiller"
'Grimes CSchulten OGC i'CRS LDoerflein, RGN-I Roy P.
Zimmerman Associate Director for Projects
, Office of Nuclear Reactor Regulation
- see previous concurrence DOCUMENT NAME:
G: iG INNA~I,G189516. STS To receive a copy of this document. indicate in the box: "C" I Copy without enclosures "E" ~ Copy with enclosures "N" ~ No copy OFFICE LA:PDI PH: PD I-1 +
- OTSB D:PDI-1 H
- DD:DRPE
- DRPH NAME SLit AJohnson:s CGrimes LHarsh JZwolinski DCrutchfield DATE OFFICE NAME DATE 12/
/95 D:DR 1 /
/95 12/
/95 11/21/95 DRP:NRR RZimmerman 1
12/
/95 12/ 0 i /95 11/29/95 12/01/95
V H
J II
)
"n
,I
'f(
IJ
'I' I
1[