ML17251A789
| ML17251A789 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/16/1986 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Lear G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17251A790 | List: |
| References | |
| NUDOCS 8609220197 | |
| Download: ML17251A789 (4) | |
Text
REQULATOl INFORNATION DISTRIBUTION TEN (RI58)
If~
ACCESSION NBR:-8609220197 DOC. DATE: 86/09/16 NOTARIZED:
NO DOCKET 0 FACIL: 50-244 Robert Emmet ('irma Nuclear Planti Unit 1> Rochester 0
05000244 AUTH. MANE AUTHOR AFFILIATION KOBER> R. W.
Rochester ('s Sr Electric Corp.
RECl'P. NANE REC IPIENT AFFILIATION LEARN Q. E.
PWR Prospect Directorate 1
SUBJECT:
Forwards "Reactor Containment Bldg Integrated Leakage Rate Testi " per 10CFR50i App J. Leakage tuithin Tech Spec limits.
1(
/i DISTRIBUTI CODE A
D COPIES RECEIVED: LTR
~9i8 TITLE:
OR ubmittal:
Append J Containment Leak Rate Testing NOTES: License Exp date, in accordance with 10CFR2i 2. 109(9/19/72).
05000244 REC IP IENT ID CODE/NANE PWR-A ADTS PWR-A EICSB PWR-A PD1 LA FAIRTILEiN PWR-A RSB INTERNAL: ADN/LFNB NRR BWR ADTS NRR PWR-B ADTS NRR/DSRO/RSXB RCN1 COPIES LTTR ENCL 2
1 1
iy RECIPIENT ID CODE/NANE PWR-A EB PWR-A FOB PWR-A PD1 PD 01 PWR-A PSB ELD/HDS4 08 NRR PWR-A *DTS
/EIB REQ FILE 04 COPIES LTTR E CL 1
lo EXTERNAL: LPDR NSIC 0S 05 1
1%
1 ie NRC PDR 02 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 26 ENCL
,1 it a
h I"
I h
I'
I sent(z(sz(
rsuzirss
>~ IIII'I iZZZiZZ i IIIII ROCHESTER GAS AND ELECTRIC Ht<
II I OIII~
j
'g, TORK
$ 1ATK CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W. KOBER VKEPRES1DENT ELECTRIC 6I STEAM PRODUCTION TELEPHON E AREA CODE TI6 546-2700 September 16I 1986 Director of Nuclear Reactor Regulation Attention:
Mr. George E. Lear> Chief PWR Project Directorate No.
1 U.S. Nuclear Regulatory Commission WashingtonT D.C.
20555
Subject:
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Lear:
An integrated leak rate test was performed in March 1986 which demonstrated that leakage from the reactor containment building at the R.
E. Ginna Nuclear Power Plant was within the limit specified in our Technical Specifications.
Enclosed are five (5) copies of the report of that test titled> "Reactor Containment Building Integrated Leak Rate Test" dated March 1986.
This report is submitted in accordance with the requirements of Appendix J to 10 CFR Part 50 and contains an analysis and interpretation of the Type A test results and a summary analysis of Type B and Type C tests.
The last Type A test was performed in 1982.
V ry truly yoursT
~V,/
Roger W. Kober 8b09220197 Sb091b j
PDR ADQCK 05000244 P
0 J
?giJ4 %i'l.'+ -C A4