ML17263B077
| ML17263B077 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/15/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9506200364 | |
| Download: ML17263B077 (4) | |
Text
P RIGRITY I (ACCELERATED RIDS Pl<OCESSli REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9506200364 DOC.DATE: 95/06/15 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-1 (PD1-1)
(Post 941001)
SUBJECT:
Responds to listed issues discussed during 950517 telcon between NRC
& RG&E re reactor coolant activity TS amend submitted by RG&E 940523 ltr.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR g ENCL g SIZE:
TITLE: OR Submittal:
General Distribution DOCKET 05000244 P
0 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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NOTE TO ALL"RIDS" RECIPIENTS:
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>v AND ROCHESTER GASANDELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, MY ldbl9-0001 AREA CODE716 56-2700 ROBERT C. MECREDY Vice President Nucteor Operations June 15, 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 Specification Record of Telecon R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
On May 17, 1995 a telephone conversation was held between the NRC (Al Johnson, Gorman West) and RG&E (George Wrobel, Brian Flynn, Bob Eliasz) concerning the subject Technical Specification amendment submitted by RG&E in a letter dated May 23, 1994.
Two issues were discussed.
Issue 1:
The simulator demonstration runs used to show that the operator actions times assumed in the analysis are realistic should include at least 804 of licensed operators on shift.
The demonstration runs performed by RG&E included approximately 50% of the operating crews.
Response
RG&E agrees to voluntarily perform additional simulator demonstration runs to cover 80: of the licensed operators on shift for the proposed license amendment request.
This will be done during the normal training schedule.
RG&E willnotify the NRC when 804 has been achieved and the results of the demonstration runs.
Issue 2:
Does the replacement steam generator affect the operator response times assumed in the analysis?
Response
The replacement of the steam generator does not affect operator response times. It will only affect the plant response to operator actions.
New analysis using the replacement steam generator characteristics and the same operator response times results in a significant decrease in offsite doses, due primarily to the smaller diameter steam generator tubes in the replacement generator.
'st506200364 950615 PDR ADDCK 05000244 P
PDR C~W Z Ord~iD.u~
The operator response times used in the analysis are generic.
The basis for these response times is presented in WCAP-10698-P-A.
If there are any additional questions call George Wrobel at (716) 724-8070.
Very ruly yours, Robert C. Mecre RWEi381 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