ML20090D134

AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressures Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr

ML20090D134
Person / Time
Site:	Oyster Creek
Issue date:	10/08/1975
From:	Quintenz T JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML20090D121	List: ML20090D114 ML20090D134
References
12166, AO-75-27, NUDOCS 8302240076
Download: ML20090D134 (7)

Text

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k'eport D:te: Oct:htr 8, 1975 Occurr nces 10/8/7S w a -

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• Inifin1 Written October 8, 197S Tia cf

' Report Date: Occurrence: 1330 l

OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/75/ 27 IDENTIFICATION Violation of the Technical Specifications, paragraph 3.1.1.D.,3, OF OCCURRENCE: Low Reactor Pressure Core Spray Valve Permissive Pressure Switenes RE 17B and D were found to trip at pressures 1 css than the minimum required value of 285 psig. This event is considered to be an abnormil

- occurrence as defined in the Technical Specifications, paragraphs 1.15B and D.

CONDITIONS PRIOR TO OCCURRENCE: x Steady State Power Routine Shutdown

- flot Standby . Operation Cold Shutdown Load Changes During Refueling Shutdown Routine Power Operation Routine Startup Other (Specify)

Operation Plant Parameters:

Power (thermal) - 582.6 E't Power (cicctrical) - 155 Mwe Recire flow - 6.0 x 104 Q' Fced flow - 1.77 x 106 lb./hr.

Stack gas - 3090 nci/sec. 'y S

DESCRIPTION OF OCCURRENCE:

On Wednesday, October 8,1975 at approximately 1130 while performing quarterly surveillance testing on the four (4) Low Reactor Pressure Core Spray Valve Permissive Pressure Switches, it was discovered that RE 17B and D tripped at 275 psig and 277 psig, respective'ly.

These values are Icss than the Technical Specification limit of 285 psig. Pressure switches RE 17B and D were immediately recalibrated.

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bormal Occurrenc2 PCg; 2 eport N2. 50-219/75/27 _

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' he "as found" and "as Icft" switch settings were:

. "As Found" Settines "As Left" Settinns RE17A 285 psig 285 psig RE17B . 275 psig 287 psig RE17C 285 psig 285 psig RE17D 277 psig 289 psig PPARENT CAUSE IF OCCURRENCE: _ Design _ Procedure Manufacture ~

Unusual Service Condition

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Installation / Inc. Environmental Construction _ Component Failure

_ Operator X Other (Specify) ne cause of this occurrence is switch repeatability.

ALYSIS OF

{SCURRENCE: The Core Spray System Parallel Isolation Valves open when a low-low reactor water level and/or high drywell pressure condition exists in addition to a low reactor pressure condition (285 psig). The four (4) Low Reactor Pressure Core Spray Valve Permissive Pressure Switches sense the low reactor pressure condition and provide signals to the ' valve opening logic. Two (2) of these switches (RE 17A and B) are associated with Core Spray System 1 and the other two (2) switches (RE 17C and D) are associated with Core Spray System 2. A trip of one switch in each core spray system is required to effect paralici isolation valve opening in that system. A review of the "as found" switch settings indicates that parallel isolation valves in both core spray systems would have opened at reactor pressures 285 psig i

had a reactor low-low water level and/or high drywell pressure condition existed concurrently. The safety significanc of this event is considered to be the loss of switch redundancy.

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)RRECTIVE ACTION: Immediate corrective action involved the recalibration of pressure switches RE 17B and D.

AILURE DATA: - Manufacturer data pertinent to these switches are as follows: .

Manufacture: Barksdale Type: Pressure Actuated Switch Range: 50-1200 psig Switch No.: B2T-A12SS (RE '17B)

B2T-A12SS (RE 17D)

Previous Abnomal Occurrences involving these switches:

(1) A.O. Report No. 50-219/75/12 m.

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s w: Jees P. O'Reilly

, Lirectorate of Regulatory Oprations Eccion I 631 Park Aveavo

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King of Prussia, Pennsylvania 19405 i . .

FRar4: Jersey Cchtral Power C Light Compr.ny Op. tex Crcck f.'ucircr ihnexating Stttica Docket C50-215 Forked River, New Jersey OS731 l .

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4 g s'aJ::CT: Abnormal Occurrence Report No. 50-219/75/ 27 i

• Yne following is a prelininary report being suimitted in co:pliance with the Technical-

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Cate.ial tiritten October C, W 'Tiw cf

. Report Date: Occurrence: 1330 4 OYSTER CPIEK NUCtEAR CENEPATING STATION FOnXED hlYER, NEW .!E7,SEY CS .*'.? 2 (knoraal Occurrence Cr:gOcc Na. S0-2%/75( tr .

IDESTIFICATION Violation of the Technical Specifications, paragraph 3.1.1.D.,3, OF OCCUR d

• ESCE: Inv Keactor Pressure Core Spray Valve Pernissive Pressure bwltenes RE 17B er.d D were found to trip at pressures less. than the ninic.m requir valus of 265 psig. This event is considered to be en abnor:41 occurrence as defined in the Technical Specifications, paragraphs

, 1.15B zad O.

CX)NDITIONS PRIOR ,

~ TO OCCUA:sCE: v Steady State Power Routine Shutdown liot Standby . Operation Cold Shutdcren Load Changes During .

h.hetirc Shutdown Voutine Pcwer Operatias Routine Startup Other (Specify)

Operation .

Pirnt Par 2neters:

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Power (thercal) - 592.6 int Power (clectrical) - ISS Mwe

, Recire flow - 6.0 x'104 .

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Feed flow - 1.77 x 106 lb./hr.

. Stack gas - 3090 cci/sec.

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DESCRWTICN OF OCCUPJ.ESCE: On tfednesday, October 8,197S at appmxtr'ately 1130 while perfornl j quarterly surveillence testing on the four (4) 14w Reactor Pressurs

! Core Spray Vr.!ve Perr.issive Pressure Switches, it was discovered i that PZ ITS and D tripped at 27S psig and 277 psig, respectively.

1 These values are Icss than the Technical Specification 11 nit of 28!

l l psig. Pressure switches P217B and D wero irr:cdiately recalibrate:

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• The % found" and "as left" w2ech settings were:

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"As Fu=>U* Sctticy **As Left" Settings RE17A 235 pi2 285 Psig RE1?B - 275 psig -

287 psig

• FEL7C 2h~> psig 265 psig .

RE23 ~13's psig - 2s9 psig

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• ES.T C.vsE ,,

CUP 7._%CE. _Desitm _ Procedure

-Mar.u n, xra mm.us3 Service Conditire, Int. tan tion / 7 rt.. Environ = ental

-Construction _Cocponent Failure

_Opmma- E,_?tibw (Specify)

', The cause of this occurnnee is cadtti repeatchility.

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.5LS (YG t^r F C ir. h Ctest Spray Systen Pars 11e1 hi.rtion Yalves open sets a low-low reactor vetor level and/or high dbvell presa.ure conditJon exists in addit 5on tr, .* Jew reactor pressure ccaditica (285 psic). The frcrr 5.Q low Reactor Pressure Core Spra.y Valve Perlisstre Prescure Switches sense

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, teactor ptussure condition and pr.: vide signnis to the estse i opening logic. Two (2) of tPese switches (RE 17A and 1:} are e

associetc<1 with Core Spray Syst.ect T. and. the other tsu (r1 J . switches (RE 17C and D) are assre:52,ted with Core Spray l

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, Systen 2, A , trip of one suitc6 in each core r. pray sy? tem l,

l is nquired to effect parc22e2 IsoJrqion velve opening in-i- that systen. A review of the "r.s kre.r.d" switch settings 9

indirstzo that parallel isol:4tice valves in b:sth core 5;say i

systens "would have opened at swetor pressures 2S5 psia l

I had v. teactor low-3ow ws.ter twel, cr4/or high drywell prwsi:n.

, condition existed concurrer.tly. N safety sicnifico. ce of f this event is considered to be the loss of switch redumhccy.

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ECUTE ACTION:

It::se2 bite corrective actien Isrw;4sd the recalibrstle::

of pressure _ switches P2173 and D,

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)*~~ a Ec.c:xzer cata pertinent to :Cw e sEitches are as

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NeouFecture: hh Typr. bevum:ne Actuated Switch h p t. S?--t302 ;?sig .

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E27-fJ.225 f.RE 178)

DZI"-Adi2S5 (RE 17D)

Pem:Loes 35: torc.a1 Occurrencer Enmtf.tscc'es these switclm r (t} A.o. T.eport No. 50-2L9/76/iL2 f

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• Date: 0:txter 8,1975 gg 37

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