ML17264A108
| ML17264A108 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/11/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9507200239 | |
| Download: ML17264A108 (5) | |
Text
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PRXORXT'Z 1 (ACCELERATED RZDS PROCESSING)
R REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9507200239 DOC.DATE: 95/07/11 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 p AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-1 (PDl-1)
(Post 941001)
SUBJECT:
Offers listed info re SG tube rupture procedure,per telcon between AR Johnson
& G Wrobel.In EOP E-3,SG sampling allowed as means of identifying location of rupture.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution 0
R NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 I RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A INTERNA FIL CWER 01 NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1
~ 1 1
D 0
M N
NOTE,TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESKi ROOM OWFN 5DS (415-2083)
TO ELZMZNATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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LTTR 12 ENCL
AND ROCHESTER GASANDELECTRIC CORPORATION ~ 89 EASTAVfNUE,ROCHESTER, N. Y Id&f9-000I AREA CODE716 5'-27M ROBERT C. MECREDY Vice Pretirient Nvdear Operetions July, 11, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-1 Washington, D.C.
20555
Subject:
Reactor Coolant Activity Technical Specifications R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
Based on a telecon between
- you, Gorman
- West, and George Wrobel (RG&E's
- Manager, Nuclear Safety and Licensing),
the following information is offered relative to our Steam Generator Tube Rupture procedure:
In Emergency Operating Procedure E-3, steam generator sampling is allowed as a means of identifying the location of the rupture (Rev.
16 step 2, page 4 of 39).
- Note, however, that this sampling is a backup to:
1.
unexpected increase in either steam generator narrow range level, or 2.
high radiation indication of steam line radiation monitors R-31 or R-32, or 3.
local indication of high steamline radiation.
Since Ginna Station is a
2-loop plant, identification of the ruptured steam generator is less difficult than for plants with more reactor coolant loops.
The sampling of the steam generators to determine which steam generator has the ruptured tube is not credited in the UFSAR Chapter 15
- analysis, or in the Report "LOFTTR2 Analysis of Potential Radiological Consequences Following a
Steam Generator Tube Rupture at the R.E. Ginna Nuclear Power Plant", November 1987, attached to our May 23, 1994 submittal on this subject.
- Rather, the air ejector radiation monitors (R-15 or R-15A) and radiation monitors in the steam line (R-31 and R-32) or blowdown lines (R-19) 9507200239 950711 PDR ADOCK 05000244 P
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provide the first indication.
An estimate of the time to collect and analyze a local steam generator sample is about two hours.
Very truly yours, Robert C. Mecredy GJW5386 xc:
Mr. Allen R. Johnson (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector
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