ML20084A444

AO 3-2-11:on 730822,discovered That Instrument Setting of One of Four Channels of Low Steam Line Pressure Controllers in High Steam Flow Safety Circuit Below Tech Spec Requirements.Caused by Instrument Drift.Channel Recalibr

ML20084A444
Person / Time
Site:	Indian Point
Issue date:	09/06/1973
From:	Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084A447	List: ML20084A444 ML20084A467
References
AO-3-2-11, NUDOCS 8304050190
Download: ML20084A444 (2)

Text

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c.c t.w .sJ d 4 frying Place New York, N Y 10003 September 6, 1973 Re: Indian Point Unit No. 2 Facility Operating License DPR-26

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Mr. John F. O' Leary, Director @ I Directorate of Licensing .' _7 I

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Dear Mr. O' Leary:

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The following report of Abnormal Occurrence No. 3-2-11 is pro-vided pursuant to the requirements of Section 6.12.2 (a) of the Technical Specifications to Facility Operating License No. DPR-26.

On August 22, 1973, it is discovered that the instrument set-ting of one of the four channels of the low steam line press-sure controllers in the high steam flow safety circuit was below that required by Table 3-1,, No. 5. The setting was found to be 577 psig rather than the required 600 psig or greater. The anomaly was identified during the performance of Periodic Sur-veillancq Test PT-Mll, " Steam Line Pressure Analog Channel Func-tional Test". Unit No. 2 was operating at approximately 49%

power at the time.

The discrepancy is believed to have resulted from instrument drift. To correct the situation,.te channel was recalicrated and retested satisfactorily. There are no safety implications associated with this occurrence since the three remaining channels in the low steam line pressure circuit would have produced the required protective action. The logic involved with this circuit requires actuation if two of four controllers sense low pressure. <! ti g'- -

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PDR ADOCK 05000247 , G881, S PDR

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h" p Mr. John F. O' scry n U S ptembsr 6, 1973 l

• The Station Nuclear Safety Committee and the Chairman of the il Company's Nuclear Facilities Safety Committee have reviewed the above described occurrence and have approved the correc-tive action taken.

MA 4 M i 1 Warren R. Cobean, Jr. Manager - Nuclear Power Generation Depa/i .ent TML/mo ~ cc/ Mr. James P. O'Rei11y Regulatory Operations, U.S.A.E.C. e 4

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            .      e-m Aic-93 in .. u.y 14.1941) AILM      )       Note end retven.                For signatue. y  For information.

TO tw,m..nd onn> innALs nauAnas ' CONSOLIDATED EDISON COMPANY j R0 Chief, Field _. Support & Enforyement j Branch, IQ i / , ABNORMAL OCCURRENCE

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TO (Name and balt) IfelflALS RE M ARKS , j Central Mail & Files The attached abnormal occurrence letter { Regulatory Standards (3) ' i Regional Directors, cart is forwarded for information. Distribution ' Ro (4)

Directorate of will be made by this office to the PDR, i TO (Name and unit) (MinALS REMARKS Licencing (13) Local PDR, NSIC, ITIIE, and State representativis  ;

cars after review by the licensee for proprietary information. FHOM LName and we.it) pguAnas i

      !   ,      E. J. Brunner                                                                                                                      ,

n Rcelon I i PHOftt IIth DATE i i X 264 8/28/73 i  ! USE OTH4A SIDE t'CT #T4flW8AL REMAAKS cro n 3,tt o - ses.ees . N r, ~

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