ML20043B390
| ML20043B390 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/09/1990 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9005290258 | |
| Download: ML20043B390 (4) | |
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GPU Nuclear Corporation.
Nuclear;
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Forked River, New Jersey 08731:0388-T 609 971-4000 9o Wnter's Direct Dial Numoer:
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Director Divigion'of Recctor Projects t
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~ U.S. Nuclear Regulatory' Commission
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Region I-475-Allendals Road
' King et Prussia, Pennsylvania 19406 Dear Sir Subjects Oyster. Creek' Nuclear Generating Station
. Docket No. 50-219 License No. DPR-16 y
p Reply to a Notice of Violation
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The enclosure to this letter contains GPU Nuclear Corporation's (GPUN) reply to the Notice cf. Violation forwarded by your letter dnted April 6, 1990.
The
' reply is in accordance with 10CFR2.201 and the Notice of Violation.
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- Your, April 8,(1990 lettor also contained requests for additional information in First,-.you requested'our evaluation of the ability.of the Oyster two. areas.
Creek plant to have met
- 10CFRSO.46 acceptance criteria for Emergency. Core.
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Cooling: Systema with a design deficiency'which could have -
.ided long term l
cooling of the water in'the_ suppression pool. Our +.espc-foe submitted wit'. tin WO, days of the date. of this letter.
In addition,-you requested'our plans and schedule to modify the automatic s
initiation logic of the Containment Heat Removal System to address single
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f ailure vulnerabi.1 Lies. Our current plans are to provide two narrow range Drywell pressure monitoring-instrument loops in accordance with Regulat'ery
. Guide 1.97,' Category 1 criteria during the Cycle 14R refueling outage'.
With
.this reliable:and' accurate monitoring instrumentation in place, manugl operator action will? replace automatic' initiation of the Containment Heat Removal
' System.. This modification will be incorporated in the next update of the
. Integrated Schedule.
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PDR A1>OCK 05000219 Fitzpatrick % r A,,
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V ce resident and Director yster Creek PC/cjg, C320657
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t GPU$udear Corporaron is a subsidia.y of General Public Utilities Cor,noration I l x
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,e Oct Regional Administrator
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Region I U.S. Nuclea.r Regulatory Comminelon 475 Allendale Road King of Prussia, PA 19406 Resident Inspector Oyster Creek Nuclear Generating Station E
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Mr. Alex Dromerick Y
U.S.
Nuclear Regulatory Commission
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Hail Station Pl-137 Washington, DC 20555 J
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ENCLOSURE P'.G8LY TO NOTICE OF VIOLATION
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.GPUiNUC1. EAR CORPORATION DOCKET NO. 50-219 OYSTER CEEEK NUCLEAR GENERATING STATION LICENSE NO. DPR-16 k
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Violation
" Oyster Creek Technical Specification Limiting condi. tion for Operation (LCO)
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,3.1.A specifies theioporating requirements for plant protective instrumentation W
in Table 3.1.1;- Table 3.1.1 requires two operable or tripped Trip Systems for Automatic Depressurization while in the Run mode.
Technical Specification 3.0.A requires that in the event a Technical Specification LCO and/or aspeciated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the y,
uni + shall be placed in COLD SHUTDOWN within the followirc 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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Contraryxto the above, for approximately 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> stnrting on July 2,
- 1985, D
while in the Run modo, one of the two Automatic Depressurization System ( ADS) trip systems was neither operable nor tripped when the core Spray System was
.recoved from service and the plant was not placed in COLD SHUTDOWN. The one ADS trip syntem was inoperable in that the proseure permissive inputs to the
' logic provioed by Core Spray System were not functional and thus the automatic s
initiation signal from that trip circuit uas not cperable."
Reply 3
-GPU Nuclear concurs in the above violation. Wo would like to clarify, however, thst only one of two Core Spray Systen loops was removed from service on July 2, 1985 during the 33 hour3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> period.
(1)? Corrective steos taken ud,,Jgggit,g,,w h tyjd Technical Specification 3.4.A.3 allows reactor operation to continue
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fcr 7 days wir.h one core Spray System locp out of service. The
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inconsistent requirements of Specification 3.4.A.3 and noto "h" of
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Table 3.1.1, have been reviewed with appropriate personnel. The requiremont te achieve cold shutdown within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> should a Core Spray System. loop be rendered inoperable has been revteved with licensed operators.. The LiNnsee Event Report (89-006) which reported-this condition was made required readingtfor licensed. operators, q
maintenanco supervisors and appropriate engineering personnel.
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addition, a placard was placed in the vicinity of the Core Spray
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Systera logic mimic panel in the control room to inform operators of the required Technical Specification action wt.an removing a core spray loop from t.,;xvice, g
(2) Ep.r,x,ective steps..to be taken to avoid further v(olatterp2 4
The correctivo actions already takea as discussed above are believed adequate to avoid further violations.
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' REPLY TO NOT2CE OF VIOLAT80N
'.' AGE 2 A modification is currently planned for the upcoming Cycle 13R refueling outage which will result in one inoperable instrument channel in each ADS trip system should a core spray loop become inoperable. Note "h" of Table 3.1.1 allows additional time (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) to effect repairs when in this condition.
The Core Spray / ADS logic "odification will be incorporated in the next Integrated Schedule L'
update.
(3) Date when full complianc e will be..:h i eved Full compliance was achieved in March 1989 with the diesemination and review of the applicable Technical Specification requirement.
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C320657
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