ML20084A026

AO 4-2-2:limiting Safety Sys Settings of Channels I & III Found Below Tech Spec Requirement.Cause of Setpoint Drift Under Investigation

ML20084A026
Person / Time
Site:	Indian Point
Issue date:	01/15/1974
From:	Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	James O'Reilly US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084A017	List: ML20084A014 ML20084A026
References
AO-4-2-2, NUDOCS 8304050072
Download: ML20084A026 (2)

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Q,p Cont.otidated Edison Company of New York, Inc.

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f January 15, 1974 E

F Ret Indian Point. Unit No. 2 l

AEC Docket No. 50-247 Operating License DPR-26 A.O.-4-2-2 B

Mr. James P. O'Reilly, Director E

Regulatory Operations, Region 1 U.

S. Atomic Energy Commission

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631 Park Avenue g

King of Prussia, Pa.

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Dear Mr. O'Reillyt f

I In accordance with the requirements of Section 6.12.2.a of F

the Technical Specifications of Facility Op3 rating License No. DPR-26, the following report is submitted.

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Periodic surveillance test PT-M2, " Reactor Coolant Temperature Analog Channel Furictional Test -d T Overtemperature anddT V

Overpower,'was performed with Unit No. 2 in the cold shutdown cozidit4.on.

The limiting safety system settings of Channels I i

and III of the Overp3wer6T Reactor 'lrip circuitry were found

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to be below that required by Technical Specification 2.3.1.B i

(5),

channels II and IV were found to be operating correctly.

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Channel III was recalibrated and tested satisfactorily.

Re-E pair of Channel No. I will be completed prior to reactor start-1 up.

E Safety implications of this discrepancy are considered slight since the reactor was in a cold shutdcwn condition and the re-au E

maining trip circuits would have provided complete reactor pro-tection again6t an excessive flux tilt even if this had not been g

the case.

The maximum error found would have resulted in the 0

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actual reactor 6T exceeding the limit by 0.15 F in achieving an overpowera T trip.

In an effort to determine the cause of these deviations and pre-E viously reported ones of a similar nature, our Engineering De-E partment is continuing the investigatlon mentioned in our letter to you dated December 18, 1973.

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8304050072 740125 PDR ADOCK 05000247

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Mr.JamenP.O'ReiO-Re:

Indian Point it No. 2 1

AEC Docket No. 50-247 Operating Licence DPR-26

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A.O.-4-2-2 i

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=I Mr. Bert Davis of your office was notified of this occurrency g

11, 1974.

4 by Mr. John Makepeace by telephone on January Very truly yours,

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C Warren R. Cobean, Jr.

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. l Manager - Nuclear Power 6

Generation

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John F. O' Leary j

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