ML20090D134
| ML20090D134 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/08/1975 |
| From: | Quintenz T JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20090D121 | List: |
| References | |
| 12166, AO-75-27, NUDOCS 8302240076 | |
| Download: ML20090D134 (7) | |
Text
[ Initisi Telcphons Dato cf k'eport D:te:
Oct:htr 8, 1975 Occurr nces 10/8/7S
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- Inifin1 Written Tia cf October 8, 197S
' Report Date:
Occurrence:
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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.
'yS DESCRIPTION On Wednesday, October 8,1975 at approximately 1130 while performing OF OCCURRENCE:
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.
8302240076 751017 PDR ADOCK 05000219
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bormal Occurrenc2 PCg; 2 eport N2. 50-219/75/27 U
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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
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Construction
_ Component Failure
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_ Operator X Other (Specify) ne cause of this occurrence is switch repeatability.
{SCURRENCE:
The Core Spray System Parallel Isolation Valves open when ALYSIS OF 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.
Manufacturer data pertinent to these switches are as AILURE DATA:
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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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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Abnormal Occurrence Report No. 50-219/75/ 27 i
Yne following is a prelininary report being suimitted in co:pliance with the Technical-Specificatic,ns, paragrcph G.6.2.
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Preli::inary Approval:
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. T. Carroll. Jr Date i
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Date cf 3..p.:t 02:e:
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'Tiw cf October C, W Occurrence:
1330 Report Date:
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
- ESCE: Inv Keactor Pressure Core Spray Valve Pernissive Pressure bwltenes RE d
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
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liot Standby Operation Cold Shutdcren Load Changes During.
h.hetirc Shutdown Voutine Pcwer Operatias Routine Startup Other (Specify)
Operation Pirnt Par 2neters:
Power (thercal) - 592.6 int
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Power (clectrical) - ISS Mwe Recire flow - 6.0 x'104 Feed flow - 1.77 x 106 lb./hr.
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Stack gas - 3090 cci/sec.
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I 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!
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psig. Pressure switches P217B and D wero irr:cdiately recalibrate:
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i tuit Uccurret.te pn2C 2
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I 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
_Desitm
_ Procedure CUP 7._%CE.
-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.
4.5LS (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 t.'*.4.e teactor ptussure condition and pr.: vide signnis to the estse i
opening logic. Two (2) of tPese switches (RE 17A and 1:} are associetc<1 with Core Spray Syst.ect T. and. the other tsu (r1 e
switches (RE 17C and D) are assre:52,ted with Core Spray J
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Systen 2, A, trip of one suitc6 in each core r. pray sy? tem I'
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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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y Pay I x.21 0.:currence
- t Ax, 50-219/~5/27
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It::se2 bite corrective actien Isrw;4sd the recalibrstle::
ECUTE ACTION:
of pressure _ switches P2173 and D,
)*~~ Ec.c:xzer cata pertinent to :Cw e sEitches are as tu cATA:
a Odicas.:
l NeouFecture:
hh bevum:ne Actuated Switch Typr.
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S?--t302 ;?sig suit.:.% go :
E27-fJ.225 f.RE 178)
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DZI"-Adi2S5 (RE 17D)
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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
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