ML17263A748
| ML17263A748 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/02/1994 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9408120109 | |
| Download: ML17263A748 (5) | |
Text
P R.I COB.IMY"'
~(ACCELERATED RIDS PROCESSING REGULAT INFORMATION DISTRIBUTIO ZSTEM (RIDS)
ACCESSiON NQP:9408120109 DOC.DATE: 94/08/02 NOTARIZED:
NO FACIL:5P-244 Robert Emmet,Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Documents conversation between J Tsao of NRC a
G Wrobel of RG&E re reduction in RCS TAVG.Requests NRC concurrence by 940901 w/info discussed in ltr.
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AND ROCHESTER GAS ANDELECTRIC CORPORATION
~ 89 EASTAVENUE, ROCHESTER, N.Y. 14649-0001 AREA CODE716 5'-2700 ROBERT C. MECREDY Vice Prerldeni Cinna Nuciear Producrion August 2, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Reduction in RCS T>>o R.E.
Ginna Nuclear Power Plant Docket No.
50-244 Ref. (a):
Letter from D.
Eisenhut (NRC) to All Operating PWR Licensees,
Subject:
Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04), dated Feb.
1, 1984.
(b):
Letter from D. DiIanni (NRC) to R. Kober (RGGE),
Subject:
Generic Letter 84-04, dated Sept.
9, 1986.
(c):
Letter from F. Miraglia (NRC) to All Operating Licensees,
Subject:
Relaxation in Arbitrary Intermediate Pipe Rupture Requirements (Generic Letter 87-11),
dated June 19, 1987.
(d):
Letter from Dennis M. Crutchfield (NRC) to John E. Maier (RGGE),
Subject:
IPSAR Section 4.13, Effects of Pipe Breaks on Structures,
- Systems, and Components Inside Containment for the R.
E.
Ginna Nuclear Power Plant, dated June 28, 1983.
Dear Mr. Johnson:
f This letter documents a conversation between John Tsao of the NRC and George Wrobel of RGGE.
Following RGL'E's steam generator replacement in 1996, we plan to reduce full load T<< from the present 573.5'F to as low as 559'F.
, This reduced coo'lant temperature results in a denser fluid and, for
~ purposes of,post-LOCA inertial force effects, is non-conservative.
We therefore plan to perform a re-evaluation of the effects of a postulated pipe rupture on the reactor vessel internals due to inertial'orces.
The pipe break selected for use in this evaluation will be the 10" RHR line, which is the largest line 9408120109 PDR ADOCK OS000aee PDR 00
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attached to the reactor coolant system which has not had an NRC-approved "leak-before-break" Safety Evaluation Report.
In accordance with GDC-4, against which Ginna Station was previously
- reviewed, the inertial effects of a double-ended RCS break is a
dynamic effect, and may be excluded from the Ginna Station design basis because the analyses submitted to the
- NRC, and subsequently
- approved, (References a,
b, c,
and d) demonstrated that the probability of a rupture in the RCS piping,'ressurizer surge line, and the accumulator lines is extremely low under conditions consistent with the design basis for the piping.
NRC concurrence by September 1,
1994 with the information discussed in this letter would be appreciated.
Very truly yours, Robert C.
Mec edy GJWi338 xc:
U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector U.S. Nuclear Regulatory Commission Allen R. Johnson (Mail Stop 14D1)
PWR Project DIrectorate I-3 Washington, D.C.
20555