ML20084D289

Preliminary AO 50-219/74/25:on 740409,loss of Primary Integrity W/Reactor Critical & Reactor Water Temp Greater than 212 F Occurred.Cause Unknown.Valves Properly Seated & Successfully Leak Tested & Power Increased to Initial Value

ML20084D289
Person / Time
Site:	Oyster Creek
Issue date:	04/10/1974
From:	Carroll J, Fickeiaem P JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-219-74-25, NUDOCS 8304110040
Download: ML20084D289 (4)

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King of Prussia, Pennsylvania 19406 Fron: Jersey Central Power 5 Light Company Oyster Creek . Nuclear Generating Station Docket #50-219 Forked River, I'cw Jersey 08731 Subj ect : Abnormal Occurrence Report No. 50-219/74/ 25 n.: felle.ing i: ; preliminar-/ report b:ing Ouhtitt;d in compliance with the Technical Specifications paragraph 6.6.2.

Preliminary Approval:

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Initial Telephone s Date of p Repore Date: )4/9/74 Occurrencei /g 4/9/74 Initial tiritten Time of Report Date: 4/10/74 Occurrence: 1040 l

OYSTER CREEK NUCLEAR GENI! RATING STisTION FORKED RIVER, NEW JhRSEY 08731 Abnermal Occurrence Report No. 50-219/74/25 IDENTIFICATION OF OCCURRENCE: Violation of the Technical Specifications, paragraph 3.S. A.1, loss of primary containment integrity with the reactor criti-cal and the reactor water temperature greater than 212 F.

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

CONDITIONS PRIOR TO OCCURRENCE: X Steady State Power Routine Shutdown Ilot Standby Operation Cold Shutdos;n Load Changes During Refueling Shutdown Routine Power Operation Routine btartup Other (Specify)

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

Power: Reactor,1849 5%t Electrical, 642 M,lc Flow: Recirc., 61 x 106 11]m/hr Feedwater, 6.9 x 106 lbm/hr Stack Gas: 34,895 pCi/.sec DESCRIPTION OF OCCURRENCE: At 1040 on April 9, 1974, a local Icak rate test on the reactor building to torus vacuum breakers was commenced ar,2 it was discovered that pressure could not be placed between V-26-15 and 16, the check and butterfly isolation valves. A check of Icakage of drywell atmosphere to the reactor building was made. No leakage was indicated when a plastic bag was taped over the vent pipe. When pressure was again applied,

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O O t.bnormal occurrence Report No. 50-219/74/25 Page 2 the bag filled with air indicating that the outside (check)

. valve was leaking. The check valve was cycled several times and then forced to seat. Air was again admitted between the valves and no leakage was detected through the check valve, but the pressure would not exceed 17.5 psig. This indicated that the butterfly valve, V-26-16, was leaking. Upon inspec-tion of V-?6-16, it was found that the valve had not been in the fully closed position. The valve wcs fully closed manually and a successful Icak test was performed.

The butterfly valve, V-26-16, was made inoperabic, as permitted by Technical Specification 3.5. A.5. .

APPAREST CAUSE OF OCCURRENCE: Design Procedure Manufacture Unusual Service Condition Installation / Inc. Environmental Construct ion 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 tine.

ANALYSIS OF OCCURRENCE: An initial analysis of the data indicates that under accident conditions in the drywell (35 psig) the Icakage rate through V-26-15 and V-26-16 would have been approximately 20% to 40%

of the allowable Icakage rate from the primary containment.

Additional investigation is continuing.

O G V b Abnormal Occurrence .

Report No. 50-219/74/25 Page 3 CORRECTIVE ACTION: At 1408, a reactor shutdown was commenced. Both valves werc

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subsequently properly seated, successfully leak tested, and made inoperabic. At 1443, the reactor shutdown was terminated and power was increased to the initial value.

7, 'AILURE DATA: llistory of torus, to reactor building vacuum breakers:

11/23/70 - V-26-18 failed to open during operability surveillance 12/18/70 - V-26-10 and V-26-18 failed to open during operability suiveillance 1/12/71 - V-26-18 failed Icakage rate test 1/13/71 - V-26-18 linkage tightened one turn, passed leakage test but valve would not open 1/1d/71 V 26-18 adjusted centr:11 r, pan d lenhage test and passed operability test 2/17/71 - V-26-16 and V-26-18 changed seats and both passed Icakage tests 5/3/73 - V-26-18 failed leakage test. Linkage ad-

, justed and valve passed Icakage and oper-ability tests.

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OYSTER CREEK NUCLEAR GENERATING S?ATION ,

FORKED RIVER, NEh' JERSEY 08731 .

2 Abnormal Occorrence - s Report No. 50-219/74/25 '

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Report Date ,

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' April 9, 1974 ,

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Identification of Occurrence .

', , N sy Violation of the Technical Specifications, paragraph 3.5. A.1, loss of,primar~j t containment integrity with the reactor critical and the reactor water temperatue . -

greater than 212 F. Based on the criteria ~of Technical Specification 4.5.F.cf the torus vacuum breaker valves, V-26-15 and 16, could be considered;ho

}' s This event is considered to be an abnormal occurrence as defined in the'brably Technicc1 , -

Specifications, paragraph 1.15B. ,

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Conditions Prior to Occurrence

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The plant was operating at steady-state power. '

The major plant parameters at the time of the occurrence were as follows: ,

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Power: Reactor, 1649 MNt ~

Electric, 642 MWe Recirculation, 61 x 10 6 lb/hr

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Flow:

Feedwater, 6.9 x 10 6 lb/hr Stack Gas: 34,895 pCi/sec ,,

Description of Occurrence <

At 1040 on April 9, 1974, a local leak rate test on the rolctor tuilding to torus vacuum breakers was couenced and it was discoveredithat prpure could not be placed between V-26-15 and 16, the check anc butterfly isordjion valves. 's A check of leakage of drywell atmosphere to the reactor buil 5ini: was,made. No leakage was indicated when a plastic bag was taped over the' vent pipe. When '

pressure was again applied, the bag filled with air indicating -that the outside (check) valve was leaking. The check valve was cycled neveral times and then forced to seat. Air was again adnitted between the valves an'd no Icakage was ,

detected through the check valve, but the pressure would noticxceed 17.5 pM g.

This indicated that the butterfly valve, V-26-16, was leeaking. Upon inspection of V-26-16, it was found that the valve had not been it the fully closdd poM. tion.

The valve was fully closed manually and a successful'icak test was performed, i

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Abnormal Occurrence No. '50-219/74/25 Page 2 The butterfly valve, V-26-16, was made inoperable, as pemitted by Technical s Specification 3.5.A.S.

Apparent Cause of Occurrence The cause of this occurrence is attributed to component failure. The reason for valycs V-26-15 and V-26-16 not to seal properly is not known at this time.

Analysis of Occurrence l>rior to the forced seating of check valve V-26-15, pressure could not be placed between the two valves, V-26-15 and 16, making a detemination of Icakage rate

{' impossibic. It was determined, however, that at normal drywell and torus pressure, no leakage from the torus to the reactor building was present.

s After the forced seating of V-26-15, a valid leakage rate test at 35 psig could

- not be performed since the maxinum attainabic pressure between the valves was only approximately 17.5 psig. The inability to reach 35 psig was due to the small size of the test penetration on valve V-26-15 and also leakage through V-26-16.

The leakage rate at 17.5 psig was estimated from availabic data and extrapolated tr> 20 psig (l't). This estimation showed tnat tne leakage rate was less tnan 40% of the all'owable drywell leakage rate.

Coy ctive Action c Check valve V-26-15 was manually forced to seat properly. At 1408, after it was s

~ ' detemined that V-26-16 was also Icaking, a reactor shutdown was commenced.

s V-26-16, the air-operated butterfly valve, which was found not to be fully in x the c1csed position, was properly seated and a leak rate test was begun.

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At approximately 1440, results of the test were obtained indicating a satisfactory leak rate and proper primary containment integrity.

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Since-both V-26-15 and V-26-16 had to be closed using manual assistance and it was' felt that V- -16 might not open without manual assistance if required, this vacuua. breaker valve set was considered inoperabic as allowed by Technical Specificatien 3.5.A.5. V-26-16 was, therefore, disabled to ensure that it

' wsuld remain in the closed position.

A't 1443, the shutdown was teminated and a return to the initial power level wag commenced.

Th . following PORC recommendations made upon review of the occurrence will be s implemented:

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1 Abnornal Occurrence No. 50-219/74/25 Page 3

1. A Study of the suitability of butterfly valves for this application be conducted by Cencration Engineering.

2. V-26-15 (check valve) be disassembled, inspected, and cicaned during the 1974 refueling outage. While disassembled, V-26-16 be internally inspected.

3. Revise the surveillance test procedure to reficct use of the shaft position indicator in determining that the butterfly

, valves are fully closed after operability testing.

Failure Data Ilistory of torus to reactor building vacuum breakers:

11/23/70 - V-26 18 failed to open during operability surveillance 12/18/70 - V-26-16 and V-26-18 failed to open during operability surveillance 1/12/71 - V-26-18 failed Icakage rate test 1/13/71 - V-26-18 linkage tightened one turn, passed Icakage test but valve would not open 1/14/71 - V-26-18 adjusted controller, passed Icakage test and passed operability test i 2/17/71 - V-26-16 and V-26-18 changed seats and both passed Icakage tests 5/3/73 -

V-26-18 failed Icakage test. Linkage adjusted and valve passed Icakage and operability tests.

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.ersey Centra  ;

Power & Lig7t Company .% '/[. /$

MADISON AVEtJUE AT PUNCH BOWL ROAD + MORRISTOWN, N.J. 07900

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General c .== i J,' ;.;. ,,, Pub!ic Utihties Corporation l sys ri w April 19, 1974 p ,ny j[,

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Mr. A. Giambusso U $jj!fW ,/

Deputy Director for Reactor Projects Directorate of Licensing g ryen

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h'ashington, D. C. 20545

Subject:

Oyster Creek Station Docket No. 50-219 Abnorral Occurrence Report No. 50-219/74/25 The purpose of this letter is to forward to you the attached Abnormal Occurrence Report in compliance with paragraph 6.6.2.a of the Technical Specifications.

Enclosed are forty copies of this submittal.

Very truly yours,

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h'727.<A..-f;!g L- --

I Donald A. Ross '

Manager, Nuclear Generating Stations Cs Enclosures cc: Mr. J. P. O'Reilly, Director j j Directorate of Regulatorv Operations, Region I , .j {

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