ML20085K272

Ro:On 731009,following Peformance of Isolation Condenser High Steam Flow & High Condensate Flow,Surveillance Valve MO3-1301-1 Failed to Open.Cause Not Found.Breaker Reset

ML20085K272
Person / Time
Site:	Dresden
Issue date:	10/18/1973
From:	Worden W COMMONWEALTH EDISON CO.
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20085K273	List: ML20085K272 ML20085K285
References
782-73, NUDOCS 8310200372
Download: ML20085K272 (2)

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' U '77, Addmss Feply to: Pcst Othce Box 767 50-249 r M/ CNcago Uhnois 60590

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, WPW Ltr.#782-73 Dresden Nuclear Power Station

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October 18, 1973

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Mr. A. Giambusso Deputy Director for Reactor Projects *[/ g Directorate of Licensing -' 9 U. S. Atomic Energy Co: mission [)4 ^ Q Washington, D. C. 20545' l .

SUBJCCT: _ LICENSE DPR-25, DRESDEN NUCLEAR POWER STATION, UNIT #3,

,SMCTION 6.6.B.2 0F TFF. TECINICAL SPECIFICATIONS ISOLATION COMP?hSCR VA*XE FAILURE

References:

1) 's6tification of Region II'I of AEC Regulatory Operations

. ' Telephone: F. Maura, 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on October 10, 1973 TOGgram: ifr. Keppler,1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on October 10, 1973

2) Drawings M-28 Dresden Station P & ID.

Dear Mr'. Giambusso:

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This letter is to, report a condition relating to the operation '

of the unit at 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> on October 9,1973. At this time MO-3-1301-1 valve in the isolation condensar system failed to operate correctly. This malfunction is contrary to section 3.5.E.1 of the Technical Specifications s

which requires that the isolation condenter be operable when reactor pressure is above 90 psig and irradiated fuel is in the vessel.

PROBLEM '

s Following performance of Isolation Condenser high steam flow, band high 'ec6densate flow surveillance, valve M03-1301-1 failed to open when the' isolation was reset. The supply breaker for the M03-1301-1 valve i

-was found tripped. It was reset and the valve then testeil satisfactorily. j r-

'At the' time of the failure, the reactor was in the "Run" mode.

and thermi power vam 2244 mecavatts. The unit was operating at a steady electrical load of 740 megawatts. Reactor pressure was 993 psig.

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"Mr. A. Giachusso October 18, 1973 INVESTICATIO'l An investigation into the problem failed to provide a cause for the breaker trip. As stated previously, the problem corrected itself once the breaker was reset. This problem has occurred on other valve breakers and is presently under investigation. For the present status of the breaker investigation, see Dresden Station's report of a malfunction of valve M03-1501-20B en Octcber 1, 1973.

CORRECTIVE ACTION The i==ediate corrective action taken was to reset the breaker trip and attcept a second valve operation. The second attempt to operate the valve proved to be successful with the valve operating as designed.

Also, this type of breaker failure has been under investigation and at this tine a cause for the brenker trips has not been found. The investigation of this type of failure will continue until the problem has  ;

been solved. Any further corrective actions will be based on the finds '

of the investigation.

EVALUATION During the failure of the M03-1301-1 valve, the safety of the I plant and public was not in jeopardy. With the valve failing closed, it I accurred pria ry ccatain.. nt integrity. Howavar, with the valve closed, the isolation condenser system would be inoperable. At the time of the failure, the high pressure core injection (HPCl) and Auto Blowdown systems were operational.

1 Continued operation of the plant was considered safe because of the short tire valve 3-1301-1 was not operational and the operational status of the high pressure core injection and auto blowdown systems.

Sincerely, 5: .YkM W. p. Worden -

Superintendent WFW:do em*en

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'i UNITED STATES

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ATOMIC ENERGY COMMISSION ,

, CIVISION OF COMPLIANCE l

,$ REGION lil trg g, 4 799 ROOSEVELT ROAD TELEPHONE GLEN ELLYN, ILLINOIS 60137 (312) ass-asso 1

i A. ~. RO Inspection Report No.

'j Transmittal Date  : k' a Distribution: Distribution.

RO Chief, FS&EB ,

R0 Chic f, FS&EB RO:HQ (5) RO:HQ (4)

DR Central Files L:D/D for Fuel & Materials Regulatory Standards (3) DR Central Files Licensing (13)

B. RO Inquiry Report No, i Transmittal Date  :

Distribution: Distribution:

RO Chie f, FS&EB RO Chief, FS&EB RO:HQ (5) . RO:HQ DR Cential Files DR Central Files Regulatory Standards (3)

Licensing (13) e C. Incident Notification From: Com.onwealth Edison Docket No. 50-249 i

(Licensee & Docket No. (or License No.) y Transmittal Date  : October 16. 1973 l

Distribution: Distribution:

RO Chief, FS&EB R0 Chief, FS&EB RO:HQ (4) RO:HQ (4)

Licensing (4) L:D/D for Fuel & Materials DR Central Files DR Central Files i

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