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=Text=
=Text=
{{#Wiki_filter:' . ** .. Mr *.
{{#Wiki_filter:..
P. O'Reilly,  
                                                                              ">:*:9.!<::i.:*),:.':,1~\;*:*>i*;**.
*operations, Region I u. s. Atomic Energy.
                                            *\~.
631 Avenue . .. . . ; .. ... ' : . . . December lB, 1973 Re: .. Indian Point Unit No. 2 Facility License DPR-26 A.O. 3-2-17 king of Prussia, i9406  
                                                  . . ; .. ~ ... ' :.
                                                              . . December lB, 1973
            ' .
Re: .. Indian Point Unit No. 2 Facility Op~rating License DPR-26 A.O. 3-2-17
**.. Mr *. Jam~s P. O'Reilly,      Direct01.~
Reg~latory      *operations, Region I
: u. s.      Atomic Energy. Commissi~n 631 ~ark Avenue                    .
king of Prussia,       ~ennsylvania    i9406


==Dear Mr. O'Reilly,==
==Dear Mr. O'Reilly,==
The following report of Oocur1:ence No. 3-2-17 is 'Provided pursuant to the of Section G.12.2(a) of the Specifications to Facility Operating License No. PPR-.26. On 17 1 1973 an analysis of the results of periodic tests and calibration checks relating to pressurizer level that the setting for one of three biatables associated  
 
'''ith high pressux:-izer level reactor trip wa15 slightly above thr.tt *required by Teclinical Specificatjon 2.3.1.C(l).
The following report of Abnorm~l* Oocur1:ence No. 3-2-17 is
At the time of the1_3e periodic tests and calibration c.heoks, the reactor was in the cold shutdown condition for maintenance work associated with repairs to the feedwater piping for No. 22 steam generator*.
    'Provided pursuant to the requireme~te* of Section G.12.2(a) of the T~ohnioal Specifications to Facility Operating License No.
* particular bistable device is part of a tw6 out of ;three logic system which provides for *a reactor trif.' signal on high level. The setpoirit was found to be at 92.25% cif span in-. stead of the 'S. of span required by the Technical Specifications.
PPR-.26.
The other two bistables of the system were found to be operating correctly.
On Decemb.~r 17 1 1973 an analysis of the results of periodic tests and calibration checks relating to pressurizer level in-dica~ed that the setting for one of three biatables associated
The chahnel associated with this device was recalibrated and satisfactorily4 . . ., . . ,w, the observed discrepancy to be result of in* strument drift and have requested.
      '''ith high pressux:-izer level reactor trip wa15 slightly above thr.tt
our Engineering Department to provide a detailed analyses of the capability of the instrument buses .to sustain the applied loading and harmonic wave effect on power supplies, bistables, converters etc. As part of the . ses, the effect of voltage swings on the equipment listed above .-*.:
    *required by Teclinical Specificatjon 2.3.1.C(l). At the time of the1_3e periodic tests and calibration c.heoks, the reactor was in the cold shutdown condition for maintenance work associated with repairs to the feedwater piping for No. 22 steam generator*.
_: ... . . .. . -l* * .. ,.  
            * ~lis particular bistable device is part of a tw6 out of ;three logic system which provides for *a reactor trif.' signal on high pres-su~i~er level.       The setpoirit was found to be at 92.25% cif span in-.
... *; .. :!* *.,. **/_: .; James P. O'Reilly *,,:,;., .. .December 19,
stead of the 'S. 92~ of span required by the Technical Specifications.
* 1973 * *
The other two bistables of the system were found to be operating correctly. The chahnel associated with this device was recalibrated and ~etested satisfactorily4 .
                                      .                                 ., .                         .
              ,w, believ~ the observed discrepancy to be th~ result of in*
strument drift and have requested. our Engineering Department to provide a detailed analyses of the capability of the instrument buses .to sustain the applied loading and th~ harmonic wave effect on power supplies, bistables, converters etc. As part of the annly-
    . ses, the effect of voltage swings on the equipment listed above
                                                  .- *.:
 
                                                                              *. .
_: ...                                     ,. ;:.*\~::.~;:~iii,~~~~i?:::~&sect;;::~,('~~/yi~l.;~\,i):*e:~;,~~;if'/:'.~'.*:5:;:~~~~:. i::-~ ... *;. :!* *.,. * /_: .;
Mr~      James P. O'Reilly                                             .December 19,
* 1973
                *,,:,;., ..                               * *
* Re:
* Re:
* Indian Point Unit No. 2 =. Facility Operating License I>PR--26 A.O. 3-2-17 *.will be evaluatad.
* Indian Point Unit No. 2
Based on these analy'ses, appropriate rective action will be taken. Mr. Dert Davis of your office was notified of this occurrence by Mr. Johri Makepeace by phone on December 17, 1973. cc: Mr. John F. O'Leary , J , ** ... / / **' " .... Very truly yours, . U!)uh,\J,11. . \ Warren *R. Cobean, Jr *. , J..!anager Nuclear Power Generation}}
                                                                            =. Facility Operating License I>PR--26 A.O. 3-2-17
              *.will be evaluatad.             Based on these analy'ses, appropriate cor-rective action will be taken. Mr. Dert Davis of your office was notified of this occurrence by Mr. Johri Makepeace by tele-phone on December 17, 1973.
Very truly yours,
                                                                                ..U!)uh,\J,11. 12{~,~~":                                                \
Warren *R. Cobean, Jr *. , J..!anager Nuclear Power Generation cc:        Mr. John F. O'Leary
  . ~.  .
                                                            ...
                                  ,
                                                                    ....
                                                          /
                                                            /
J ,* *
. . -
                                                        **'    "}}

Revision as of 19:18, 29 October 2019

Letter Regarding a 12/17/1973 Analysis of Results of Periodic Tests and Calibration Checks Relating to Pressurizer Level Indicated a Setting for One of the Bistables Was Above the Technical Spec. Limit - Indian Point Unit 2
ML17252A877
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 12/18/1973
From: Cobean W
Con Edison, Consolidated Edison Co of New York
To: O'Reilly J
US Atomic Energy Commission (AEC)
References
Download: ML17252A877 (2)
v • d • e


Text

..

">:*:9.!<::i.:*),:.':,1~\;*:*>i*;**.

  • \~.

. . ; .. ~ ... ' :.

. . December lB, 1973

' .

Re: .. Indian Point Unit No. 2 Facility Op~rating License DPR-26 A.O. 3-2-17

    • .. Mr *. Jam~s P. O'Reilly, Direct01.~

Reg~latory *operations, Region I

u. s. Atomic Energy. Commissi~n 631 ~ark Avenue .

king of Prussia, ~ennsylvania i9406

Dear Mr. O'Reilly,

The following report of Abnorm~l* Oocur1:ence No. 3-2-17 is

'Provided pursuant to the requireme~te* of Section G.12.2(a) of the T~ohnioal Specifications to Facility Operating License No.

PPR-.26.

On Decemb.~r 17 1 1973 an analysis of the results of periodic tests and calibration checks relating to pressurizer level in-dica~ed that the setting for one of three biatables associated

ith high pressux:-izer level reactor trip wa15 slightly above thr.tt

  • required by Teclinical Specificatjon 2.3.1.C(l). At the time of the1_3e periodic tests and calibration c.heoks, the reactor was in the cold shutdown condition for maintenance work associated with repairs to the feedwater piping for No. 22 steam generator*.
  • ~lis particular bistable device is part of a tw6 out of ;three logic system which provides for *a reactor trif.' signal on high pres-su~i~er level. The setpoirit was found to be at 92.25% cif span in-.

stead of the 'S. 92~ of span required by the Technical Specifications.

The other two bistables of the system were found to be operating correctly. The chahnel associated with this device was recalibrated and ~etested satisfactorily4 .

. ., . .

,w, believ~ the observed discrepancy to be th~ result of in*

strument drift and have requested. our Engineering Department to provide a detailed analyses of the capability of the instrument buses .to sustain the applied loading and th~ harmonic wave effect on power supplies, bistables, converters etc. As part of the annly-

. ses, the effect of voltage swings on the equipment listed above

.- *.:

  • . .

_: ... ,. ;:.*\~::.~;:~iii,~~~~i?:::~§;::~,('~~/yi~l.;~\,i):*e:~;,~~;if'/:'.~'.*:5:;:~~~~:. i::-~ ... *;. :!* *.,. * /_: .;

Mr~ James P. O'Reilly .December 19,

  • 1973
  • ,,:,;., .. * *
  • Re:
  • Indian Point Unit No. 2

=. Facility Operating License I>PR--26 A.O. 3-2-17

  • .will be evaluatad. Based on these analy'ses, appropriate cor-rective action will be taken. Mr. Dert Davis of your office was notified of this occurrence by Mr. Johri Makepeace by tele-phone on December 17, 1973.

Very truly yours,

..U!)uh,\J,11. 12{~,~~": \

Warren *R. Cobean, Jr *. , J..!anager Nuclear Power Generation cc: Mr. John F. O'Leary

. ~. .

...

,

....

/

/

J ,* *

. . -

    • ' "
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