ML17264A263
| ML17264A263 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/16/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A264 | List: |
| References | |
| NUDOCS 9512010128 | |
| Download: ML17264A263 (5) | |
Text
'RIDRITY ACCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9512010128 DOC.DATE: 95/11/16 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards addi info for application for amend to license re Reactor Coolant Activity TS.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR J ENCL L SIZE:
+ 7 TITLE: OR Submittal:
General Distribution P
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 R
RECIPIENT, ID CODE/NAME PD1-1 LA JOHNSON,A INTERNA~ILE,CENTERR~) 1 NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 D
U NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iUASTE! CONTACI THE DOCUMENTCONTROL DESK, ROOM PI-37 (EXT. 504-2083 ) TO ELlih!INATE YOUR NAME FROil DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON"I'L'ED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL ll
Arvn ROCHESTER GASANDEIECTR1C CORPORAVON ~ 89 EASTAVEhfUE, ROCHESTER, N. Y 1ddd9-0001 AREA CODE716 546-2700 ROBERT C. MECREDY Vice President Nvcteor operations November 16, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R.,Johnson Project Directorate I-1 Washington, D.C.
20555
Subject:
Additional Information for Application for Amendment to Operating License Reactor Coolant Activity Technical Specifications R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
RG&E Letter, R.
C.
Mecredy to A.
R.
Johnson (NRC),
"Application for Amendment to Operating License Reactor Coolant ActivityTechnical Specification,"
May 23, 1994.
Dear Mr. Johnson:
As a result of a November 9,
1995 telephone conversation between RG&E and members of the NRC staff the following additional information is supplied to supplement Ref. (a):
1.
A scrubbing efficiency of zero should be used for times greater 1260 sec.
in Case 1 and 1420 sec.
in Case 2 of Ref.
(a).
2 ~
3 ~
Attachment 1 supplements WCAP-11668 which was provided in Ref.
(a).
The attachment describes the Gamma Body Offsite Dose Calculation.
Results are provided for Case 1 and Case 2.
The results are well within the guidelines.
Attachment 2 provides a site plot and photos illustrating the distances from the release points to the control room intake.
They are:
control room vent intake elevation 315'elief valve discharge pipe elevation 351'op of containment facade elevation 387'orizontal distance from ARVs to control room intake 132'7<<
and 187'9>>
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If there are any questions you may reach George Wrobel at (716) 724-8070.'ery truly yours, Attachments RWEi402 Robert C. Mecredy 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 Ginna Senior Resident Inspector
Attachment 1
to RG&E to NRC Letter Dated 11/16/95 Supplement to WCAP-11668 Gamma-Body Offsite Dose Calculation