ML17263A320
| ML17263A320 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/13/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17263A321 | List: |
| References | |
| NUDOCS 9307220221 | |
| Download: ML17263A320 (4) | |
Text
ACCEI ERAT D DOCUMENT DIST BUTION SYSTEM REGULA
.Y INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR:9307220221 DOC.DATE: 93/07/13 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1,'ochester AUTH;NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 8 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET G
05000244 05000244
SUBJECT:
Forwards "Reactor Containment Bldg Integrated Leakage
- Rate, Apr 1993 for Ginna Nuclear Station."
Rept documents~results of test conducted during 1993 refueling outage.
o'ISTRIBUTION CODE:
A017D COPIES RECEIVED:LTR ENCLi SIZE:
'k V TITLE: OR Submittal:
Append J Containment Leak ate Testing, NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: OC~DGB ZG~I 01 RES/DSIR/SAIS COPIES LTTR ENCL 1
1 1
0 1
1 1
1 RECIPIENT ID CODE/NAME JOHNSON,A OGC/HDS1 RES/DE/SEB COPIES LTTR ENCL 2
2.
1 1
1 1
EXTERNAL: NRC PDR 1
1
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NSIC 1
1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 10 ENCL 9
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fQADI/pg/fr 'rrrrr ROCHESTER GAS AND ELECTRIC CORPORATION 8F.:.
4 89 EAST AVENUE, ROCHESTER N. K 14649.0001 ROBERT G MECREDY Vlcc Prerldent Cinna Nuclear Production July 13, 1993 TELEPHOtrE AREACOOE7te 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Containment Building Integrated Leakage Rate Test Rochester Gas and Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
Enclosed is the final report documenting the results of the Ginna Containment Building Integrated Leakage Rate Test (ILRT) which was conducted during the 1993 Refueling Outage.
This report is being submitted in accordance with Section 4.4.1.6.a of the Ginna Station Technical Specifications and 10 CFR 50 Appendix J, Section V.B.
Based on the successful completion of this test, the next ILRT is anticipated for the 1996 Refueling Outage.
\\
Very truly yours, Robert C.
Mec edy MDFtt551 Enclosures xc:
Mr. Allen R. Johnson (Mail Stop 14Dl)
Project Directorate I-3 Washington, D.C.
20555 Ms. Donna Ross New York State Energy Office U.S. Nuclear Regulatory Commission Region 1
475 Allendale Road King of Prussia, PA 19406 200045 Ginna Senior Resident Inspector Pgj PQ
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