ML20066A581

RO 2-82-36/1P:on 821024,71J Safety Relief Valve Opened When Pressure Reached 832 Psig.Cause Unknown.Valve to Be Sent to Vendor.Two Vacuum Breakers Replaced.Fatigue Analysis Determined Downstream Piping Not Overstressed

ML20066A581
Person / Time
Site:	Peach Bottom
Issue date:	10/28/1982
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-2-82-36-1P, NUDOCS 8211060130
Download: ML20066A581 (2)

Text

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,, Peach Bottosh Atomaic Power Station 1, Delta, Pennsylvania R.D.

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Mr. R.:C.'IIaynes ,

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• s converention w i tta a.-51ough, Rangiosa I, i',r ;. Ussited states Muclear Regulatory c-immiosa on'10/24/82.

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of.. anni t 2, ,the YkJ' safety /a'relief paaring startup valve opened wesena

• ~ reactor' presseure reactaed,832 peig'daaring reactor 'startup p sog rams.

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conditiorum , Prior to' occurrences' .

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' Unit 2 had'beena sthutdown om Coe- h r-23, 1982, to add oil to the

- lower reseryoir'of the 2A reciro pump anotor. Unit 2 was being

~ React.or power

" resturraad to'pcaser operation'following this osatage.

at the tisme of occurremace was appa oasianately- 14.

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• '?" Un3cnowra a t "tRai m tiano . ~ The relief valve will ' he seat'to a' vendor to de termisme t2ae caume-ofr this opurious opassing .

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Po11 outing q' maintenance shutdowra e ra Oc*nh=r 23, 1 9 8 2 ,. Unmit 2 wem

1 " being started up. Primmary cooleavat pressure was bei ngr increased in l - - **accordance with normal At approas i - te ly 3:07 PM orn October 24, when time startup primmy Reactor procedures.

coolant premeure reackaed 832 peig, power et the tiame was a p p r oas aas.

• S tate 71J relief walve: opened. - ' ' '

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' Opening of . the ? relief "valvan -diately ieduced 'preemmui'am r e sau 1 1c i n g :

' swell of reactor water level which tripp4ed t.has o p e ras t i.n g r oesc t o r '

feed p u.s.ap . Before the reactor feed pumip could*be recovered, reacto

~3evel reduced to approastmately zero incnes and the re. actor scr.=med.

The NPC2 asy stmuss wem ==nually started to recover reactor level to n o;.;

sainismum level reached during this treamient was approasimeteely aminu -

13 inchess . .i .

. . e Cince ' there was minimal. . decay heat in the reactor at this time, pres and temperature reductiost were rapid. The normal cooldowsa race og

'100*F was excw -d during this blowdown event.

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=rhe relief' valve remained open until pri=mry-coolant' pressure reduce

'"to 40 poig'at 3:58 PM on 10/24/82. During thias transient; , the torue

' level increamed slightly above the -alanum TechnAcal Specification

'11amit . of 14.90 feet. sa mas h m indicated torum level wem 14.96 feet.

• yo11owing closure of'the relief valve, steps were taken to pumsp dowr '

The tearum ' to normal ' level., , y .' . *

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'Za"accordmance with the mite emergency-plan,:mma 'unusualievent'was 4

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declared and propertnotifications were made. The unumue.1 event

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terminated when the relief valve ressatada- '

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• puring'the'above transient,-all 3CCS systeams operated properly and

' ' all par ===ters responded an' expected. No releases ' of acti$/ity occurr

'during1this evema t. safety significasace is therefores mainiamm1.

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., . corrective Actiosaa , .

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=rta'e 71J re11ef valve wa ss replaced. Asa ' Assapeatiosa og'the dowanstrearm

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' piping waa m <= = d a n c ted a nd sao discrepancies identified. Proliansissary danta- indicated that the 71J valve had operated numerous e-4==m.

"" Fatigue asamlysia was perforsned by Bechtel and a determaisaation smado

. that'the downstreams piping was stot overstrammed. T2se vacuum breakur oss the dowatcosmer -froam stain valve med a secossd valve whicks taad benen operated manuaIZy daaring the tran asiosat were inspected. Both valves u I

! ~ aceae bisading osa +% 2ainge pisa much that snormal sprimag preneure wem

' ** ' insuf ficienst to close the valve.^ 29te two vacuum azreakera were r es p a.,

M Corrective actions have thereforet beest completed with the exception

. " ou r. continu.ed isavestigation 12 20'the origisaal -cause of the valve ope

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