ML17251A988
| ML17251A988 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/21/1988 |
| From: | Snow B ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC |
| References | |
| NUDOCS 8803250288 | |
| Download: ML17251A988 (2) | |
Text
gCCKLKRATED DI lBUTION DEMONSTRA, EON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8803250288 DOC.DATE: 88/03/21 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION SNOW,B.A.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION STAHLE,C.
NRC No Detailed AffiliationGiven
SUBJECT:
Provides minor clarification to safety evaluation accompanying 880223 Amend 25 to License DPR-18.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET g 05000244 05000244~
RECIPIENT ID CODE/NAME PD1-3 LA STAHLE,C INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB8H7 NRR/DEST/MTB 9H NRR/DOEA/TSB11F OGC 15-B-18 RES/DE/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
1 1
1 1
1 0
1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS7E4 NRR/DEST/ESB 8D NRR/DEST/RSB 8E N'og)/~ling/ILRB12 ggEG FIL~
Ol NRC PDR COPIES LTTR ENCL j
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D TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 1
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 STATE March 21, 1988 TEE.EPNONE AREA COOE TIE 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Clarification to Safety Evaluation Accompanying Amendment No.
25 to the Facility Operating License R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
On February 23, 1988 the NRC issued Amendment No.
25 to Facility Operating License No.
DPR-18 for the R.E.
Ginna Nuclear Power Plant.
The purpose of this letter is to provide a minor clarification to the Safety Evaluation accompanying the Amendment.
The Safety Evaluation on Page 3
states
"...the licensee assumed a factor of.
3 for the accident initiated iodine spike and a
factor of 6
for the pre-accident iodine spike for the radiological release analysis."
The factors of 3
and 6 are not just assumptions, but conservative bounding values by which the calculated doses might increase due to SG tube uncovery.
The modified methodology when developed is expected.
to result in smaller factors.
The bounding nature of the estimated increase factors (factors of 3
and 6) was discussed in the cover letter which transmitted the subject analysis (RG&E to NRC letter dated, December 24, 1987 from R.W. Kober to C. Stahle).
Sincerely, Bruce A. Snow Superintendent Nuclear Production 8803250288 880321 PDR ADOCK 05000244 P
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