ML19261F294

Abnormal Occurrence 74-1:on 740419,underwater Light Broken within Open Reactor Vessel.Caused by Administrative Controls Implementation Inadequacy.Fragments Recovered & Personnel Briefed on Cautions & Administrative Controls

ML19261F294
Person / Time
Site:	Three Mile Island
Issue date:	04/24/1974
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
NUDOCS 7910250748
Download: ML19261F294 (3)

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Directorate of Licensing i signed CLASS UNCLASS PROP II.'FO IITUT NO CYS RZC'D DOCK:T NO:

XXX 1 50-239 DE5CRIFTION: ENCLCSUZES:

Ltr furn info re abnormal occurrence #AO-74-1 of 4-19-74 in which an unprotected undcrwater DO NOT REMOVE light came into contact with the interf ace ag 1

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Operating License JFR-50 Decket No. 50-P89 Abnormal Cecurlence No. AC-7h-1 As defined by Technical Specifications for the Three Mile Island Nuclear Station Unit 1, Section 6.7.2. a, we are reporting the folleving abnormal occurrence as AC-Th-l.

At 1120 on April 19, 1974, during preparations for initial fuel loading, an unprotected underwater light came into contact with the interface flange (located between the core support shield and core barrel) and was broken within the open reactor vessel. It was assumed that these foreign materials , if allowed to remain in the reactor c olant during cperaticns, cculd impinge on fuel rods and degrade the fuel cladding, thereby causing ri unsafe condition in the operation of the plant. This threat to cause an unsafe conditicn resulted from an cbserved in-adequacy in the implementation of administrative controls , and constitutes an abnormal occurrence as defined by section 1.8.g of Technical Specifications.

After the light shield breakage, all fueling verk in the reactor vessel contrcl area was stopped. All fueling perscnnel working in the a ea were reinstructed on cautiens and administrative controls to be folicved while working in the area.

These cautions included a brief on the types of tcols and devices permitted in the vicinity of the open reactor vessel. In addition, Quality Centrol personnel were assigned on a full shift coverage basis fcr the remainder of initial fuel leading operations to inspect all tools for suitability and retrievability prior to permitting their passage beyond the Reactor Vessel Control Point. A precedure was written to recover the pieces of the light shield and the light shield pieces were recovered, assembled, and cated to the unbroken portien of the shield. Based en the reasse= bled light shield, it was cencl.'.ded that essentially all of the shield fragments had been recovered.

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DIRECTORATE CF LICENSING April 29, 197h The Plant Operations Review Cct=ittee (PCRC) met prcmptly after the incident to evaluate these events at which time PCRC reco:cended the corrective action outlined above to the Plant Superintendent. Upon completion of the subject corrective action FORC met and concluded that the corrective action taken was adequate tc prevett recurrence. The Plant Juperintendent has concurred in this finding.

Sincerely,

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d , ',, 3 -N i( f R. C. ARNOLD Vice President-Generation RCA:DNG:lv cc: Directorate of Regulatory Operations, Region 1 U. S. Atomic Energy Cc=nission 631 Park Avenue King of Prussia, Pennsylvania 19h06 File 20.1.1/7.7.3 5 1 b

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