ML20085K134

Telecopy Ro:On 731127,valve MO-3-1201-2 Failed to Isolate on Low Reactor Level.Caused by Problem W/Auxiliary Contact on Breaker Coil.Problem Corrected

ML20085K134
Person / Time
Site:	Dresden
Issue date:	11/28/1973
From:	Worden W COMMONWEALTH EDISON CO.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20085K131	List: ML20085K129 ML20085K132 ML20085K134
References
NUDOCS 8310200138
Download: ML20085K134 (1)

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U.S. ATOMIC ENERGY COMM.

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PMS MR J y aRv DMECTOR DIRECTORI ATE OF LICENSING US ATOMIC ENERGY COMMISSION WUX WASHDC 20545 SUBJECT DPR-25 DRESDEN NUCLEAR POWER STATION UNIT 3 THIS WILL CONFIRM A CONVERSATION WITH MR MAURA OF YOUR OFFICE AT 1500 HOURS THIS DATE CONCERNING FAILURE OF MO-3-1201-2 TO ISOLATE ON LOW REACTOR LEVEL A80VE Wil NOVEMBER 27, 197:a OTHER VALVES IN THE SYTEM CLOSED PROPERLY.

INITI ATING SIGNAL WAS RESULT OF FEED WATER CONTROL SYSTEM PROBLEM AND NOT ASSOCI ATED WITH CLEAN UP PIPING LEAKS ELECTRICI AN FOUND PRO 8LEM WITH AUXILI ARY CONTACT ON BREAKER COIL AND C,0RRECTED SAM E.

VALVE WAS SATISFACTORILY CYCLED PRIOR TO REACTOR START UP W P WORDEN, SUPERINTENDANT DRESDEN NUCLEAR POWER STATION f,,

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o DIRECTORATE OF REGULATORY OPER ATIONS jg REGION lli

%rts o' "p 799 ROOSEVELT ROAD mag GLEN ELLYN. ILLINOIS 60137 (312) 858-2660 November 27, 1973 Comonwealth Edison Co:npany Dockets No. 50-10 ATTN Mr. Byron Lee, Jr.

.30-23Z 50-2497 (50-254 Vice President P. O. Box 767 Chica'go, Illincis 60690 50-265 Centiment The enclosed Directorato of Regulatory Operations Bulletin No. 73-6,

" Inadvertent Criticality in a Loiling Water Reactor," io sent to you to provide you with infor: nation that was reported

• to the AEC by the Vermont

' Yankee Nucicar Power Corporation concerning an inadvertent criticality incident that was experienced in the Vermont Yankee facility. This information my have direct applicability to your facilitics. Action requested on your part is identified in Sc'ction A of the enclosed bulletin.

Very truly yours, James G. Koppler Regional Director

• a Enclosures RD Bulletin No. 73-6 bec: RO Files DR Central Files PDR Local PDR l

• Ltr dtd 11-8-73 to' Directorate of Regulatory Operations, Region I, I

King of Prucaia, Pa.

• Ltr dtd 11-14-73 to Directorate of Licensing, USAEC, Washington, D.C.

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~J November 27, 1973 Directorate of Regulatory Operations Bulletin No. 73-6 INADVERTENT CRITICALITY IN A BOILING WATER REACTOR We recently received an abnormal occurrence report from the Vermont Yankee Nuclear Power Corporation relating to an inadvertent criticality incident that was experienced at their Vermont Yankee facility. A copy of this report is being sent to you under separate cover to provide you with pertinent details of this event.

At the time of the inadvertent criticality incident, the reactor vessel and primary containment heads were removed, the refueling cavity above the reactor vessel was flooded, control rod friction tests were in progress, the rod worth minimizer was bypassed, and core verification had been in progress. As a result of the incident, no measurable radioactivity was released, no fuel damage resulted and no personnel exposures were experienced. The incident is currently under review l

and evaluation by the Regulutory Staff.

i Action requested by this bulletin is contained in Section A.

A.

Action Requested by Licensees

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In light of this occurrence you are requested to take the following actions. Upon completion of these actions you are requested to i

inform this office in writing, within 45 days of the date of this letter, of the status of each item identified in each paragraph and subparagraph listed below:

1 1.

Procedural Review a.

Control Rod Drive Operating and Testing Procedures (1) Conduct a review of your control rod drive operating and testing procedures to determine that approved l

procedures exist for all operations and tests.

l (2) Verify that appropriate prerequisites are included in the procedures to require testing of associated inter-i locking and protection features before control rod testing is permitted.

l (3) Assure that prerequisites and detailed instructions are provided that dedonstrate compliance with technical specification requirements and design bases.

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Bypass Installation Procedures (Jumpers or Lifting of Leads) i Assure that existing bypass installation procedures have been conservatively reviewed for technical adequacy and for adminis-j strative controls.

c.

Radiation Protection Procedures Assure that procedures for access control and personnel f

accountability in areas subject to accidents are current.

d.

Shift Transition Procedure (Turnover)

Assure that complete and detailed procedures are in effect that provide instructions for a proper and conservative turnover of shift responsibilities. Such procedures must include requirements for communicating the status of all safety related equipment and conditions.

2.

Management controls l

Assure that your management controls that are in effect provide for qualified technical and administrative reviews and approvals of i

temporary circuitry changes and temporary off-normal plant conditions.

This review should assure that the responsibilities and requirements associated with the review and approval, installation, verification, j

removal, and subsequent testing of temporary circuitry changes and temporary off-normal plant conditions are clearly delineated in station procedures, are understood by the station staff, and arc being properly implemented.

3.

Licensed Operator Performance Assure that management provides the necessary opportunities and time so that operators are adequately trained to carry out their

'i assigned responsibilities.

In particular, confirm that shift crew members are provided special training for safety related activities that are infrequent, complex, or have unusual safety significance.

If you have any questions concerning this request, please contact this office.

Enclosure:

AO No. 7331 - Ltr dtd 11/14/73 (separate cover) b s

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UNITED STATES ATOMIC ENERGY COMMISSION j ]

I DIVISION OF COMPLIANCc REGION lli f,

si,,,, p 799 ROOSEVELT ROAD TELEPHONC GLEN ELLYN, ILLINOIS 60137 (sta) ess.2eso NOV 2 7 1973

' LOCAL PUBLIC DOCUMENT ROOMS

• Enclosed are copies of documents listed below relating to Commonwealth Edison Company '

, Docket No(s).

50-10, 50-237, t 50-249 :

Letter to Commonwealth Edison Compary from James G. Keppler dated November 27, 1973.

3 This correspondence is submitted pursuant to arrangements made by the Public Proceedings Branch, Office of the Secretary, for use by 3

the public.

1 Where possible, these materials should be punched and filed in a folder labeled as follows:

a CORRESPONDENCE TO AND FROM APPLICANT OR' LICENSEE q

(Excluding Envirdnmental and Antitrust) 5 :*. ' ja f t i c j c...u e

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' James G. Keppler Regional Director

Enclosures:

As noted above t

ec: Washington " Ulic Document Room, w/enci Central Mali & Files Unit, Document Room Clerk, w/o enc 1 I\\

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