ML17252A873

From kanterella
Jump to navigation Jump to search
Letter Regarding Periodic Surveillance Test PT-M2, Reactor Coolant Temperature Analog Channel Functional Test - Delta T Overtemperature and Delta T Overpower in Cold Shutdown Condition -Indian Point Unit 2
ML17252A873
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 01/15/1974
From: Cobean W
Con Edison, Consolidated Edison Co of New York
To: O'Reilly J
US Atomic Energy Commission (AEC)
References
Download: ML17252A873 (2)


Text

..-:::. - ,

~~~-n

~~Yi ti

~A

,.,R~

H ~

~

Consolidated Edison Company of New York, Inc.

4 Irving Place, Nr,w York., NY 10003 January 15, 1974 Rei Indian Point. Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.0.-4-2-2 Mr. James P. O'Reilly, Director

  • Regulatory Operations, Region 1 U. S.,Atomic Energy Commission 631 Park Avenue
~ing of Prussia, Pa. ~9406

Dear Mr. otReilly:

ln accordance with the requirements of Section 6.12.2.a of the Technical Specifications of Facility Operating License No. OPR-26, the following report is submitted.

Periodic surveillance test PT-Mi, "Reactor Coolant Temperature Analog Channel Functional Test -/j T OVertem.perature and AT Overpower",~was performed with Unit No. 2 in the cold shutdown cond.i tion. 'l'he lirni ting safety system settings of Channels I and III of the overpower AT Reactor Trip circuitry were found to be below that required by Technical Specification 2.3.1.B (S). Channels II and IV were found to be operating correctly.

Channel III was recalibrated and tested satisfactorily. Re-pair of Channel No. I will be completed prior to reactor start-up.

Safety implications of.this discrepancy are considered slight since the reactor was in a cold shutdown condition and the re-

_maining trip Qircuits would have provided complete reactor pro-tection again$t an excessive flux tilt even if this had not been the case. The maximum error found would have resulted in the actual reactor C> T exceeding the limit by O.15 OF in achieving an overpower AT trip.

In an effort to determine the cause of these deviations and pre-viously reported ones of a similar nature, our Engineering De~

partrnent is continuing the investigation mentioned in our letter

\to you dated December 18, 197 3.

  • --1 . '****: .*'-*'*
  • ~* ~.*,.~**-

,.:..: . *' ............~..:. ~- ',:: ..',*1' *'.:;*_*~--~-*.:

...:.*'*. - .' ... . .: . .: . ~'.. *. . . -~ .

Mr. ~ames P* *eilly 2 -

Re:

India:a:1:: ~::ti:~~ 2 *. ,*,~,~~

    • ' AEC DOcket No. 50-247 Operating License OPR-26 A.0.-4-2-2 Mr. Bert Davis of your office was notified of this occurrency by Mr. John Makepeace bi' telephone on January 11, 1974 ..

Very truly yours, LQlvJu ~ (1 k~ *1\

1 Warren R. Cobean, Jr. \(

Manager - Nuclear Pow.er Generation ec/ John F. O'Leary


*-*-.. -- - -* .. - . .. .