ML19282C155

Forwards LER 79-010/01T-0

ML19282C155
Person / Time
Site:	Peach Bottom
Issue date:	03/12/1979
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19282C157	List: ML19282C155 ML19282C159
References
NUDOCS 7903210110
Download: ML19282C155 (3)

Text

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET PHILADELPHI A. PA.19101 (21518414o00 March 12, 1979 Mr. Boyce H. Crier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Conaission 631 Park Avenue King of Prussia, Pennsylvania 19406 Dea r ?!r. Grier:

SUBJECT:

Licensee Event Re_p o r t Narr,ative Description The following occurrence was reported to Mr. Greenman, Region I, Office of Inspection and E n f o rc e.7e n t on February 26,

, 1979.

Reference:

Docket '!u n b e r s 50-277 & 50-278 Report No: LER 79-10/1T Report Date: March 12, 1979 Occurrence Date: February 26, 1979 Facility: Peach Botton Atomic Power Station R.D. 1, Delta, PA 17314 Technical Specificati_on

Reference:

Technical Specification 6.9.2a(9) requires reporting

" P e r f o rtaa n c e. o f structures, systens, or components that requires remedial action or corrective measures to prevent operation in a nanner less conservative than assumed in the accident analyses in the safety analysis report or technical s pecifica tions bases; or discovery during plant life of conditions not specifically considered in the safety analysis report of technical specifications that req u i re remedial action or corrective measures to prevent the existence or development of an unsafe condition."

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790321011o t \

Mr. Boyce 11 . Crier Page 2 March 12. 197') LER 79-10/IT D e s_c r i p t i,o n o f_ _t h e, Ev_e_n t :

Design errors in cable designations and routing were identified on February 26, 1979 during a design review of cable routing, initiated as a result of an investigation with respect to fire protection. In both units the power cable and control cable for Recirculation Pump Discharge Valves MO-53A and B are involved. Additionally, in Unit 3 the Recirculation discharge valve bypass Valves, MO-54 A and B, are involved. In the cable spreading room the control cable for both the __ and B valves are run in the same cable tray for a short distance. Outside the cable spread room the A and B valve cables are separated but are run in cable trays which have not been designated as safeguard.

C_onsey ences o_f_ Event:

The consequences of this event are considered minimal for the following reasons:

1. All the cables involved are Rockbesos Firewall 3 which have a flame retardant neoptera jacket.

2. All the cable trays involved are seismicly qualified.

3. Outside the cable spreading roon the A and B valve cables are run in separate caole trays.

4. The cables are routed t h ro u ;;h low fire probability areas. Fire detection devices are installed in the cable spreading area.

Cause of Event:

The cause of the occurrence was improper designation of the cables during the design and construction of the plant. This appears to have resulted f rom a lack of specific inf or:2a tion indicating the requirement for safeguard treatment in the design d o c utae n t a t i o n .

Corrective Action.

Upon notification of the occurrence, plant personnel identified the cable trays involved and marked them for easy recognition. A continuous fire watch was established in the cable spreading roon. A roving fire watch was established to cover the other eight rooms through which the cable trays pass.

A " clock" route was subsequently established to docunent the roving fire watch coverage and no welding or burning is being allowed in the area of the affected cable runs until the plant modification is completed.

r. Soyce 11 . Grier Page 3

.. arch 12, 1979 LER 79-lu/IT A plant aodification has been initiated to redesignate, reroute and roterniaate the ca bla s . The pre-outage construction work on Unit 2 is cocplete. Unit 3 is expected to be completed ay : larch 15, 1979. The detailed reternination drawings are in progress. Unit 2 drawings are expected to be couplete by March 16 and Unit 3 coupleted by March 23, 1979. The hardware necessary for the modification is being prepared and is expected to be available by ?! arch 15, 1979.

The modification will be completed during a plant outage following completions of the design drawings and p re pa ra t ion of the harduare. The outages will be scheduled no later than May 23, 1979.

Yours truly, P

/)-

M. J. Cooney S perintendent

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Generation Division-Nuclear Attachment ec: Director, ARC - Office of Inspection and Enforcement Mr. Nornan M. Haller, NRC - Office of Management &

Program Analysis

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