ML20086K218

Environ RO 74-C-1:on 741112,instrument Valves Associated w/PS-2-55C & PS-2-55D & Bypass Valves Associated W/Excess Flow Valves 3-2-3-11 & 3-2-33 Found in Improper Positions. Cause Unknown.Investigation in Progress

ML20086K218
Person / Time
Site:	Peach Bottom
Issue date:	11/21/1974
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
References
RO-74-C-1, NUDOCS 8401260355
Download: ML20086K218 (2)

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November 21, 1974 Mr. A. Giambusso h*'b Deputy Director of Reactor Projects -

United States Atomic Energy Commission ha==o.y.ddc Directorate of Licensing Washington, DC 20545 7

Subject:

A_bnormal Occurrence

! It is requested that this abnormal occurrence be teated as con-i fidential, and held from public disclosure.

i The following occurrence was repor ted to tir. W. Baunack, A.E.C.

Region 1 Regulatory Operations Office, and is submitted in accordance with Section 6 7.2.A of the Technical Specifications, Appendix A of DPR-44 and DPR-56 for Units 2 and 3 Peach Bottom Atomi<. Power Station.

Reference:

License N,.imber DPR 44 and DPR-56 Technical Specification Reference 3 1.1 Report No.: 50-277/278-74-c-i-Report Date: November 22, 1974 Occurrence Date: November 12, 1974 l Facility: Peach Bottom Atomic Pov>cr Station

, Unit 2 and Unit 3 R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:

i Instrument valves associated with PS-2-55C and PS-2-550 and, bypass valves associated with excess flow valves i/3-2-3-11 and #3-2-33 l were found in improper positions.

Conditions Prior to Occurrence:

Units 2 and 3 cach at approximately 70% power. .

l Description of Occurrence-Instrument tecnnician, in prepar ing to calibrate pressure switch, noted that its shutoff valve was in the closed position. tie also noted l

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PDR ADOCK 05000277 S PDR

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a similar situation existed on the neighboring pressure switch. The bypass valve on the excess flov check valves were noted open by an en-gineer during plant inspection.

Designation of Apparent Cause of Occurrence:

Investigation of the procedural safeguards designed to prevent such an occurrence has been conducted. No procedural deficiences were uncovered. Possibilitics exist that a person may be deliberately mis-valving in order to cause embarrassment.

Analysis of Occurrence:

The non-availability of the instruments (PS-2-55C and PS-2-550) would not have caused loss of function because of the redundant nature of the logic system. The open u'ypass valve on the excess flow checks would have effectively precluded automatic closure should a leak have

. occurred in the down stream piping. The consequences, however, of this occurrence are considered minimal because of the small size and number of lines involved.

Corrective Action:

Philadelphia Electric Company's Security Division has entered this investigation. The Security Director has met with A.E.C. Region 1 Security Personnel and developed a program which is designed to cc.nfirm if deliberate nis-valving is taking place. The investigation will con-tinue under the directicn of the Security Director, who has established liaison with the Director of Region I by way of the R0-1 Security Divi-sion.

Additionally, the Engineer (I & C) is verifying proper valve positions for instruments mounted on plant protective system instrument racks which were worked during the day.

Failure Data:

Two similar f ailures of this type have been repor ted as Abnormal Occurrence 50-277-74-36 and Abnormal Occurrence 50-273-74-10. ,

Very truly yours, M. J. Cooney Ass't General Superintendent

• Gene' ration Division cc: Mr. J. P. O'Rei lly Director, Region 1 United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 e