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mtw | |||
(? CU be U Consolidate:I Edison Company of Now York. Inc. | |||
4 i Ang P! ace, N York, N Y 10003 d | |||
December 18, 1973 Re: Indian Point Unit No. 2 Facility Operating License ; | |||
DPR-26 A.O. 3-2-17 . . | |||
Mr., James P. O'Reilly, Director .. | |||
Regulatory Operations, Region I U. S. Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 ' | |||
==Dear fir. O'Reilly,== | |||
The following report of Abnormsl-Occurrence No. 3-2-17 is provided purauant to the requirements of Section G.12. 2 (a ) of the Technical Specifications to Facility Operating License No. | |||
DP R- 2 6 . | |||
On December 17, 1973 an analysis of the results of periodic tests and calibration checks relating to pressuriser level in-dicated that the setting for one of three bistables associated with high pressurizer level reactor trip was slightly above that required by Technical Specificat ion 2. 3.1.C (l) . At the time of theoc periodi-c tests and calibration checks, the reactor was in . | |||
the coldto repairs shutdown the feedwaterconditionpiping for maintenance for No 22 steamwork associated with generator. | |||
This particular bistable device is part of a two out of three logic system which provides for a reactor trip signal on high pres-suriter level. | |||
The setpoint was found to be at 92.25% of span in-stead of the 192t of span required by the Technical Specifications. | |||
The other two bistables of the system were found to be operating correctly. | |||
and re'estedThe channel associated with this r*avice was recalibrated satisfactorily. | |||
s, ' | |||
. We Grift strument believe'the obcerved discrepancy to be the result of in- .- | |||
an! have reques*ed our Engineering Department to provide a detailed analyses of the capability of the instrument buses to sustain the applied loading and the harmonic wave effect on power syplies, b3ntables, converters etc. As part of the analy- | |||
= | |||
ses, the offect of voAtage swings on the equipment listed abovo l | |||
k 4 | |||
y , | |||
i L | |||
.? | |||
Mr. James P. O'Reilly O O December 18, 1973 Re Indian Point Unit No. 2 | |||
, Facility Operating License DPR-26 A.O. 3-2-17 will be evaluated. Based on these analy'ces, appropriate cor-rective action will be taken. Mr. Bert Davis of your office was notified of this occurrence by Mr. John Mahopeaco by tele-phone on December 17, 1973. | |||
Very truly yours, | |||
\ | |||
j y' O(L% % M o ~, ks GLW Warren R. Cobean, Jr., Manager Nuclear Power Generation cc: Mr. John F. O' Leary | |||
.= | |||
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5 m | |||
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h k' j j ; h h ' [ [ $ ) [ | |||
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Revision as of 20:03, 13 May 2020
| ML20084A252 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 12/18/1973 |
| From: | Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084A234 | List: |
| References | |
| AO-3-2-17, NUDOCS 8304050141 | |
| Download: ML20084A252 (2) | |
Text
Q l..
mtw
(? CU be U Consolidate:I Edison Company of Now York. Inc.
4 i Ang P! ace, N York, N Y 10003 d
December 18, 1973 Re: Indian Point Unit No. 2 Facility Operating License ;
DPR-26 A.O. 3-2-17 . .
Mr., James P. O'Reilly, Director ..
Regulatory Operations, Region I U. S. Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 '
Dear fir. O'Reilly,
The following report of Abnormsl-Occurrence No. 3-2-17 is provided purauant to the requirements of Section G.12. 2 (a ) of the Technical Specifications to Facility Operating License No.
DP R- 2 6 .
On December 17, 1973 an analysis of the results of periodic tests and calibration checks relating to pressuriser level in-dicated that the setting for one of three bistables associated with high pressurizer level reactor trip was slightly above that required by Technical Specificat ion 2. 3.1.C (l) . At the time of theoc periodi-c tests and calibration checks, the reactor was in .
the coldto repairs shutdown the feedwaterconditionpiping for maintenance for No 22 steamwork associated with generator.
This particular bistable device is part of a two out of three logic system which provides for a reactor trip signal on high pres-suriter level.
The setpoint was found to be at 92.25% of span in-stead of the 192t of span required by the Technical Specifications.
The other two bistables of the system were found to be operating correctly.
and re'estedThe channel associated with this r*avice was recalibrated satisfactorily.
s, '
. We Grift strument believe'the obcerved discrepancy to be the result of in- .-
an! have reques*ed our Engineering Department to provide a detailed analyses of the capability of the instrument buses to sustain the applied loading and the harmonic wave effect on power syplies, b3ntables, converters etc. As part of the analy-
=
ses, the offect of voAtage swings on the equipment listed abovo l
k 4
y ,
i L
.?
Mr. James P. O'Reilly O O December 18, 1973 Re Indian Point Unit No. 2
, Facility Operating License DPR-26 A.O. 3-2-17 will be evaluated. Based on these analy'ces, appropriate cor-rective action will be taken. Mr. Bert Davis of your office was notified of this occurrence by Mr. John Mahopeaco by tele-phone on December 17, 1973.
Very truly yours,
\
j y' O(L% % M o ~, ks GLW Warren R. Cobean, Jr., Manager Nuclear Power Generation cc: Mr. John F. O' Leary
.=
1 i
1
- l
. m
~
/
5 m
-um
. g m: ,
,.*'f
~. '
h k' j j ; h h ' [ [ $ ) [
- ; !