ML20084A467
| ML20084A467 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/23/1973 |
| From: | Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20084A447 | List: |
| References | |
| AO-3-2-11, NUDOCS 8304050196 | |
| Download: ML20084A467 (1) | |
Text
p O
O Consolidated Edison Company of New York, Inc.
4 Irving Place, New York, N Y 10003 August 23, 1973 Indian Point Station Re:
Facility Operating.
License DPR-26
.i Mr. James P. O'Reilly, Director i
Regulatory Operations, Region 1 U.S. Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
In accordance with the Technical Specifications of Facility Operating License No. DPR-26, we wish to inform you of an
(..O.
3-2-11) which was identified on Abnormal Occurrence A
August 22, 1973.
Periodic Surveillance Test PT-Mll, " Steam Line Pressure An-'
)
[
alog_ channel Functional Test" was performed during power op-eration at approximately 49% power.
The instrument setting l
for one channel-of the low steam line pressure controllers in the high steam flow safety circuit was found to be below j
that required by Table 3-1, No. 5 (577 versus 600 psig).
The remaining three channels were'found to be operating cor ~
i j
rectly. 'The channel was recalibratediand retested satisfac-
'i ', -
torily.
Safety implications of this occurrence are considered to be
. slight since the remaining three channels of the 2 out of 4 l-actuation logic were set correctly and would have' functioned j
iferequired.
Mr.-Fasano of your office.was notified of this occurrence by
/
telephone.on August 22,-1973.--
Very truly yours, n
8304050196 730906
,(,[
- r ' {DRADOCK 05000247 Warren R. Cobean, Jr.
\\
i PDR Manager, Nuclear Power Generation Department I -
'MFS:daf I
.Mr. John F.'O' Leary
' j0' pki e
Copy To:
0 Directorate of Licensing' 7
_ _