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f April 19, 1974 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing United States Atomic Energy Commission Washington, D. C.
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Dear Mr. Giambusso:
Subject:
Oyster Creek Station Docket No. 50-219 Abnormal Occurrenco Report No. 50-219/74/24 The purpose of this letter is to forward to you' an event which was reported as a Technical Specification violation on April 9,1974. Ilindsight leads me to believe this is not a reportable event.
Even though the sample was analyzed later than is our normal practice, there was no loss of continuity in the gross counting analysis.
i Enclosed are forty copies of this submittal.
Very truly yours, j
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i Donald A. Ross DAR/pd Manager, Nuclear Generating Stations Enclosures Mr. J. P. O'Reilly, Director /
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Directorate of Regulatory Operations, Region I
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OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/74/24
. Report Date April'19,' 1974
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Occurrence Date-April 9, 1974
-Identification of Occurrence Violation of 'the Technical Specifications, paragraph 4.6.B.1.g, in that the stack gas particulate filter in service from March 28, 1974 to March 31, 1974 was not analyzed for gross 8, gross a, and gross y, but was analyzed for Ba-140, La-140.and I-131 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15G.
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Conditions Prior to Occurrence The plant was operating at _ steady-state power.
The major plant parameters at the time of the event were as follows (during
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the period the filter was in service):
Power:
Reactor, 1806 MWt
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Electrical, 632 MWe Flow:
Recirculation, 57.2 x 106 lb/hr Feedwater, 6.735 x 106 lb/hr Stack Gas:
35,000 pC1/sec 3
Description of Occurrence A stack gas particulate filter, installed at 0847 on March 28, 1974 and re-moved at_0854 on March 31, 1974, was not counted for gross 6, gross a, and gross y,-.as per Technical Specification 4.6.B.1.9.
This was detected in a routine audit of the stack release records.
Apparent Cause of Occurrence Counting of the filter 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal was not performed by the technician as required by our normal practice.
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- Analysis of Occurrence
..The safety significance connected with. this occurrence is that ary unus ally large release of particulate activity during this period might rot have be
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0 Abnormal Occurrence No. 50-219/74/24
- Page 2 recognized until.the monthly composite analyses were complete.
This is not a likely possibility as a spectrum analysis was performed to measure releases of short-lived isotopes and if unusually large amounts of activity were present, it would have been readily apparent.
In addition, a spectrum analysis of the charcoal filter had also been performed and normal quantities of iodine were found.
Corrective Action' The particulate filter was counted nine days after filter removal upon discovery of the abnormal occurrence. The gross B, gross a, and gross y values were comparable to samples removed before and after this filter as is shown in the following tabic:
Samnie Gross a Gross S Gross y Per'iod pCi/CCx10~14 pCi/CCx10-10 CPM /CCx10-5 3/22 to 3/25
.487 1.36 2.09 3/25 to 3/28 1.14 1.92 2.84 2.11 3/28 to 3/31
.139 1,68 3/31 to 4/2 7.32 2.81 1.56 4/2 to 4/5
.677 2.13 3.16 This would indicate that there waz little or no change in plant stack effluents and that the plant was operating with releases less than 4% of the Technical Specification limit of 4 pCi/sce of iodine and particulates having half-lives
><S days.
The administrative control over stack gas filter cartridge analysis will be reviewed and tightened, if necessary, to assure that counting is performed on schedule.
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James P. O'Reilly Directorate of Regulatory Operations 4
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From:
Jersey Central Power fr Light-Company 1
Oyster Creek Nucienr Generating Station, Docket #50-219-Forked River, New' Jersey 08731 i
j Subjeht:
Abnormal: Occurrence Report"NoiP501219/74/28 1
'the following is a preliminary report being submitted in compliance with the Technical Specifications, paragraph 6.6.2.
Preliminary Approval:
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/TR/M 4/19/74
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[T. Carm11, Jr.
E Datio cc: Mr. A. Giambusso
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.. Report D!to:
4/19/74___
Occurnnee 0715
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I OYS111R CREliK NUCIRAR GENERATING STATION i
~ PORKED RIVER, NEW JERSHY 08731 Abnormal Occurrence Report No. 50-219/74/28 i
i IDENTIFICATION Violation of the Technical Specifications, paragraph 3.4.A.1, 0F OCCURRENQit j
which requires the core spray system to be operable at all i
I times with irradiated fuel in the reactor vessel, except as specified in Specification 3.4. A.3 and 3.4. A.4.
Suction valve j
(V-20-4) to the "s"' core spray pump was stuck in the closed j
position for a period of approximat' ly 15 minutes thereby e
causing a loss of core spray pump redundancy in.4ystem II.
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addition, core spray system I'was tagged out of service for i
maintenance at this time.
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'this event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15B and D.
CONDITIONS PRIOR Steady State Power Routino Shutdown TO OCCUIUENCE:
~ Hot Standby Operation j
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Cold Shutdown
_ ined Chimges During X ~ Refueling Shutdown koutine Power Operation
~ Routine Startup Other (Specify)
' Operation 1ho reactor mode switch was in the REFUEL position with reactor 1
i coolant touperature appmximately 104 F.
IESCRIMION At approximately 0735 on April 19, 1974, while performing sur-0F GCCURRENG:
4 veillance testing o,n cog sprety:systen.II,V.aotor-operated velve V-20-4 failed to open electrically after having closed electrically in a normal manner. 1hi's surveillance testing was being perfonned 4
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on core spray system II-after system I was tagged out of scr-
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vice for maintenance, (Hydraulic shock and sway arrestor units i^
were being replaced on cogonents of. system I.) V-20-4 was j
manually opened approximately 15 minutes after this valve prob-
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lem was identified.
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i APPARENT CAL 6E Design Procedure i.
OP OCCURRENCE:
Manufacture
.,,,_. Unusual Soryice Condition i
Installation /
Inc. havannmental Construction Component Failure
_ Operator
_ other (Specify)
The apparent cause of this. occurrence has not been identified at this time.
ANALYSIS OF Motor-operated valve V-20-d provides suction to the "B" coro DCCUkkBNCE:
spray pump in core spray system II. 'Ihis valvo is normally maintained in the open position but is closed whenever required for isolation purposes. Had core spray system operation been required, the "B" core spray pump would have functi~oned nor-msily both before performance of the surveillanco testing and after the valve was locked in the open position. Only the isolation function of the valvo was lost during these two time i
i periods. The safety' significance of this event is that for a period of approximately 15 minutes coro spray pump redundancy j
was lost in system II.. Since system I was tagged out of service j
during this time period, a further degradation in core spray
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system capability resulted, i
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00RRECT1VP.
Immediato correctiva cction involved manually opening.tha moter-hCTEUN:
operated valve (V-20-4) and tagging open the associated circuit brvAker to prevent subsequent.' closing. Additional ~ corrective!
actions will be detonnined following the completion of mainten-unce and reviev'of this incident by the Plant' operations Review Committoc.
1 FA11 AIRE DATA:
To be supplied at a later date.
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Prepared by:
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Date:
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