ML20084D307

Preliminary AO 50-219/74/24:on 740409,stack Gas Particulate Filter in Svc from 740328-31 Not Analyzed for Gross Beta, Alpha & Lambda.Cause Under Investigation

ML20084D307
Person / Time
Site:	Oyster Creek
Issue date:	04/10/1974
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-219-74-24, NUDOCS 8304110050
Download: ML20084D307 (8)

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To: James P. O'Reilly Directorato of Regulatory Opentions Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 l _

prom: Jersey Central Power 4 Light Company .

Oyster -Creek Nuclear Generating Station Docket #50-219 Perked River, New Jarsey 08731 S4 ject: Abnormal Occurrence Report No. 50-219/74/ 24 1he following is a I tolininary report being submitted in compliance with the Technical Specifications paragraph 6.6.2. -

Prelimina'y 2 Approval:

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Report Date: 4/1A/74 Occurrence: . 1000 2 g ,

OYSTER CRFEK HUCLEAR GENERATING STATION PORKED RIVER, NEW JERSEY 08731 Abnomal Occurrence Report No. 50-219/74/24 ,

IDE}(TIFICATION ~

OF OCCURRENCE: Violation of the Technical Specifications, paragraph 4.6.B.1.g, .

in that the stack gas particulate filter in service from '

Marcfr 28, 1974 to Harch 31, 1974 was not analyzed for gross 8, gross a, and gross y.

This event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15Gi (X)NDITIONS PRIOR 10 OCCURRENCE: X Steady. State Power Routine Shutdown i~

e Hot Standby Operation '

Cold Shutdown Load Ganges During Refueling Shutdown Routine Power Operation Routine Startup Other (Specify) '

Operation __ __

1he major plant parmeters At the time of the event were as .

follows: l Power: Reactor,1806 IWt Blectrical, 632 IWe Plow:*

Recirc. , 57.2 x 106 lb/hr l ,

Peedwater, 6.735 x lo s Ib/hr Stack Gas: 35,000 pCi/sec j

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DESCRIPTION .- l 0F OCCURRENCE: A s' tack gas particulate filter, installed at 0847 on March 28, 1 1974 and removed at 0854 son March 31, 1974, was not counted I-

• E a for gross a, gross 8, and gross y within one week of removal.

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Report No. 50-219/F4/20

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1 APPARE T CAUSE "'

l OP OCCURRENCE: _ Design Procedure i

Hanufacture unusual Service Conditf on '

l Installation / Inc. Environmental Construction ,

Component Failure j Operator . Other (Specify)

I i Counting o'f the filter '48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />'s after removal was not perfonned by the technician as required. Investigation into the cause is continuing.

B ANALYSIS OF OCCURRENCE: no safety significance connected with this occurrence is that any unusually large release of particulate activity during this period might not have been recognized until the monthly compo-site analyses were complete. n is is not a likely possibility as a spectnnn analysis was performed to measura 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 per-formed and normal quantities of Iodine were found.

CORRECTIVE

[ ACTION: ne part'iculate filter was counted nine days after filter re-moval upon discovery of the abnormal occurrence. Se gross a, gross B, and gross y values were companble to samples removed before and after this filter. His would indicate that there was little or no change in plant gaseous effluents and that the plant was operating with releases less than 4% of the Technical 6"

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Sp.cification limit of 4 pC1/ soc of"ledine and particulates a

having half-lives >8 day's.

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l To: James P. O'Reilly *

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i Prom: Jersey Central Power 6 Light Company j! Oyster Creek Nuclear Generating Station Docket #50-219

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Abnormal Occurrence Report No. 5 0-219/74/ 25 y c .

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The following is a preliminary report being submit,ted a ~

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" Initial Written R: port Date:

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OccurrenceO, 1040 f .

1 OYSTER CREEK NUCLEAR CENERATING STATION FORKED RIVCR, NEW JERSEY 08731 Abnormal Occurrence

, Report No. 50-219/74/25 .

IDENTIFICATION OF OCCURRENCE: ViolatLon of the Technical Specifications, paragraph 3.5. A.1, Loss of primary containment integrity with the reactor criti-cal and the reactor water temperature greater than 2120F This eYent is considered to be an abnormal occurrence as de-o fined in the Technical Specifications, paragraph,1,158, '

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CONDITIONS PRIOR

i. 'IU OCCURRENCE: X Steady State Power Routine Shutdown Hot Standby Operation Cold Shutdown ~

Load Changes During Refuellng Shutdown Routine Powers 0peration Routine Startup Other (Specify)

Operation The major plant paramel:ers at the time of the event were as follows.

Power: Reactor, ?,849 Wt P Electrical, 642 We

,,, Flow: h Recirc., 61 x 10 6 lbm/hr

' ' FeedWater 6.9 x 10 6 lbm/hr Stack Gas: 34,895 9C1/sec DESCRIPTION , . . , , . , .m j

l OF OCCURRENCE:

At 1040 on' Apri1'9.19' 7 4) a local leak rate test on the reactor building to torus vacuum breakers was commenced and it was discovered that pressure could not be placed between V-26-15 and 16, the check and butterfly isolation valves. A check of leakage of drywell atmosphere to the reactor building

[ us made. No leakage was indicsted whco a plastic bag was

,' taped over the vent pipe. When persun was again appde6 1 _

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O f,I O the bag filled with air indicating that the outside (check) t

( valve was leaking. De check valve was cycled several times 1

and then forced to seat. Air was again idaltted between the

! vs',ves and no leakage was detected through the check valve, but the pressure vould not exceed 17.$ psig. 1his indicated that the butterfly valve, V-26-16, was leaking. Upon inspec-

• tion of V-26-16, it was found that the valve had not been in

,. the fully ' closed position. 'Iho valve was fully closed manually l and a successful }eak test was performed.

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,I W The butterfly valve, V-26-16, has' made. inoperable, as permitted _

by Technical Specification 3.S. A.S.

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b APPARENT CAUSE

OP OCCURRENCE: Design Procedure i, 14anufacture Unusual Service Condition' Installation / Ice. Environmental

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Construction X_ _ Component Failure

.. Operator Other (Specify)

, The cause for valves V-26-15 and V-26-16 not to seal properly

[ . .is not known at this time.

.. ANALYSIS OF OCCURRENCE: An initial analysis of the data indicates that under accident

{ conditions in the drywell (35 psig) the. leakage rate through V-26-15 and V-26-16 would have been approximately 20% to 40% .

of the allowable leakage rate from the primary containment.

, Additional investigation is continuing. .

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l CORRECT,IVE Q ~ -s I

ft ACTIDN: At 1408, a reactor shutdown was commenced. Both valves were

', subsequently properly seated, successfully leak tested, and f made inoperable. At 1443, the reactor shutdown was terminated

) and power was increased to the initial value, t

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FAILURE DATA: History of torus to reactor building vacuum breakers:

11/23/70 - V-26-18 failed to open during operability suryeillancc

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12/18/70 - V-26-16 and V-26-18 failed to open during j operability surveillance 1/12/71. - V-26-18 failed leakage rate test

. . 1/13/71 - V-26-18 linkage tightened one turn, passed Isakage. test but valve would not open

{ 1/14/71 - V-26-18 adjusted controller, pused leakage test and passed operability test 2/17/71 - V-26-16 and V-26-18 changed seats and both passed leakage tests S/3/73 - V-26-18 failed lenkage test. Linkage ad- -

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. justed afi(: valve passed leakage'.and oper-ability tests.

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.lersey Centra l Power & Lig h t Company []k/((J g

MADIGON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J.07960

• 201-539-S111 m . , r-

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Mr. A. Gianbusso /I%  ? ),'

Deputy Director for Reactor Projects Directorate of Licensing

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United States Atomic Energy Commission h'ashington, D. C. 20545

Subject:

Oyster Creek Station Docket No. 50-219 stock cns r:ilter cyrr.:..y Analycir In ny report of Abnormal Occurrence No. 50-210/74/24, dated April 19, 1974, I indicated that a review of the administrative control over the stach gas filter cartridge analysis would be undertaken to assure that counting is performed on schedule. This review has been completed, and a change in the check-off procedures has been incorporated to insure that the counting schedule is met.

Very truly yours, f e )

[hDGib ( (. f n Donald A. Ross \-

Manager, Nucicar Generating Stations Cs  ;

cc: Mr. J. P. O'Reilly, Director I Directorato of Regulatory Operations, Region I ]

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O OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence

. Report No. 50-219/74/24 Report Date April 19,1974 Occurrence Date April 9, 1974 Identification of Occurrence Violatior 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 analy:cd 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.

Conditions Prior to Occurrence

'lhe plant was operating at steady-state power.

The major plant parameters at the time of the event were as follows (during the period the filter was in service):

Power: Reactor, 1806 MWt Electrical, 632 MWe Flow: Rocirculation, 57.2 x 106 lb/hr Feedwater, 6.735 x 106 lb/hr Stack Gas: 35,000 pCi/sec 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 detceted 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.

Analysis of Occurrence The safety . significance connected with this occurrence is that any unusually large release of partkulate activity during this period might not.have been e

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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 i charcoal filter had also been performed and normal quantitics of iodine were found. ,

Corrective Action f i

The particulate filter was counted nine days after filter removal upon discovery j of the abnormal occurrence. The gross 6, gross a, and gross y values were .

comparabic to samples removed before and after this filter as is shown in the following tabic:

- Sampic Gross a Gross 8 Gross y .

pCi/CCx10-10 -5 Period pCi/CCx10-14 CPM /CCx10 l 1

.487 1.36 2,09 i 3/22 to 3/25 3/25 to 3/28 1.14 1.92 2.84 l 3/28 to 3/31 .139 1.68 . 2.11 3/31 to 4/2 2.32 2.81 1.56 '

4/2 to 4/5 .677 2.13 3.16  !

This would indicate that there was little or no change in plant stack effluents j and that the plant was operating with releases less than 4% of the Technical Specification limit of 4 pCi/sec of iodine and particulates having half-lives i

>/8 days. i The administrative control over stack gas filter cartridge analysis will be reviewed and tightened, if necessary, to assure that counting is performed on .

I schedule. ,

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MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J.07960

• 201-539-6111 nanase a ras Genera! g, ~ Public Utstaties Corporation srsne e-  %

April 19,1974 e g 1 -

g R.>. 0 9 Mr. A. Giambusso 2 APR241974 >  :-

Deputy Director for Reactor Projects b. u. [g,gm 1 Directorate of Licensing  :::a.;rr United States Atomic Energy Commission q, " " * 'e Washington, D. C. 20545 y -

Subject:

Oyster Creek Station Docket No. 50-219 Ahnnrmal Occiivmee P.eport Mc. 50.210/74/24 The purpcse of this letter is to forward to you an event which was reported as a Techni:a1 Specification violation on April 9,1974. liindsight lead.1 me to believe this is not a reportabic event. Even though the sample was analyzed later than is our normal practice, there was no loss of continuity in the gross counting analysis.

Enclosed are forty copies of this submittal.

Very truly yours, I f Donald A. Ross DAR/pd Manager, Nuclear Generating Stations Enclosures cc: Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region I s.

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From: Jersey Central Power 6 Light Company Oyster CIcek .Nucicar Generating Station Docket #50-219 Forked River, New Jersey 08731

Subject:

Abnormal Occurrence Report No. 50-219/74/ 2a The following is a prelit::inary report being submitted in compliance with the Technical Specifications paragraph 6.6.2.

Prelimina'ry Approval:

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Initial Tel,cphene Date of Report D.fte: *

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% Occurrence: 4/9/74

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Report Date: 4/10/74 Occurrence: 1000 OYSTER CPIEl' NUCLEAR GENtiRATING STATION FORKED RIVER, NEli JERSEY 08731

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Abnomal Occurrence Report No. 50-219/74/24 IDENTIFICATION OF OCCURRENCE: Violation of the Technical Specifications, paragraph 4.6.B.1.g, in that the stack gas particulate filter in service from

!! arch 28,1974 to !! arch 31, 1974 was not analy::cd for gross 8, 2

gross a, and gross y.

This event is considered to be an abnomal occurrence as de-fined in the Technical Specifications, paragraph 1.15G.

, CONDITIONS PRIOR TO OCCURRENCE: X Steady State Power Routine Bhutdown llot Standby Operation Cold Shutdo'.in Load Changes During Refueling Shutdown Routine Power Operation Routine Startup Other (Specify)

Operation The major plant parameters at the time of the event were as follows:

Power: Reactor,1806 !Et Electrical, 632 frie i

Flow: Reci rc. , 57.2 x 106 lb/hr Feedwater, 6.733 x 106 lb/hr Stack Gas: 35,000 pCi/sec

, DESCRIPTION OF OCCURRENCE: A stack gas particulate filter, installed at 0847 on March 28, 1974 and removed at OS54 on !! arch 31, 1974, was not counted i

for gross a, gross 8, and gross y within one week of removal.

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Abnornal Occurrence Report No. 50-219/74/24 Page 2 APPARENT CAUSE OF OCCURRENCE: Design Procedure

!bnufacture Unusual Service Condition Installation / Inc. Environmental Construction Component Failure Operator Other (Specify)

Counting of the filter 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> after removal was not performed by the technician as required. Investigation into the cause is continuing.

ANALYSIS OF

. OCCURRENCE: The safety significance connected with this occurrence is that any unusually large release of particulate activity during this period might not have been recognized until the monthly compo-site analyses were complete. This is not a likely possibility

, as a spectrun analysis was perrormea to measure reicases ot 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 per-formed and normal quantities of Iodine were found.

CORRECTIVE ACTION: The particulate filter was counted nine days after filter re-moval upon discovery of the abnormal occurrence. The gross a, gross 8, and gross y values were comparabic to sampics removed before and af ter this filter. This would indicate that there was little or no change in plant gaseous effluents and that the plant was operating with releases less than 4*6 of the Technical

1

Abnormal Occurrence j j Report No. 50-219/74/24 Page 3 1

Specification limit of 4 pCi/sec of Iodine and particukates having half-lives >8 days, i

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Prepared by: , hd A -

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