05000219/LER-1981-030, Forwards LER 81-030/01T-0.Detailed Event Analysis Encl

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Forwards LER 81-030/01T-0.Detailed Event Analysis Encl
ML20030B275
Person / Time
Site: Oyster Creek
Issue date: 07/27/1981
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20030B277 List:
References
NUDOCS 8108060278
Download: ML20030B275 (3)


LER-1981-030, Forwards LER 81-030/01T-0.Detailed Event Analysis Encl
Event date:
Report date:
2191981030R00 - NRC Website

text

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p OYSTER CREEK NUCLEAR Gi2NERATING STATION O j ETBI/3 tW7

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(609)693-6000 P.O. BOX 388

  • FORKED RIVER
  • 08731 i.

July 27, 1981 i

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n, Mr. Boyce H. Grier, Director

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.. OTi1983 Or Office of Inspection and Enforcenent p'

Region I United States Nuclear Regulatory Cm mission "J4 p.s. %

D 631 Park Avenue 2;

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King of Prussia, Pennsylvania 19406 Q

Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-30/01T-0 This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-30/0lT-0 in campliance with paragraph 6.9.2.a.2 and 6.9.2.b.2 e

  • the Technical Specifications.

Very truly yours, hA

. T. Carro Jr.

{

irector S

'on Operations JIC:dh l

Enclosures 1

cc: Director (40 copies)

Office of Inspection and Enforcamnt United States Nuclear Regulatory Comnission Washington, D.C.

20555 l

Director (3) l Office of Managemnt Information and Prog am Control United States Nuclear Regulatory Cm mission Washington, D. C. 20555 NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station l

Forked River, N. J.

((p 8108060278 810727

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PDR ADOCK 05000219 l

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OYSTER CREEK NUCLERR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-30/0lT-0 Report Date July 27, 1981 Occurrence Date July 14, 1981 Identification of Occurrence The failure of reactor building main exhaust valve V-28-22 to close resulted in a violation of Secondary Contamnent integrity as defined by the Technical Specifications, section 1.14C and a violation of Technical Specifications 3.5.B.l.

The plant was also operating in a degraded mode as permitted by a limiting condition of operation as given in Technical Specifications section 3.5.B.3 when Standby Gas Treatment Systen #I failed to start.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraphs 6.9.2.a.2 and 6.9.2.b.2.

Conditions Prior to Occurrence The planc was operating at steady state power.

Major Plant Parameters Power:

Reactor 1409 bMt Generatc,r 370 FMe Flow:

Recirculation 11.1 x 104 gp3 Feedwater 4.18 x 10 lb/hr Description of Occurrence On Tuesday, July 14, at 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br />, Standby Gas Treatment Systen #I failed to start during performance of required surveillance. At the same time reactor building main exhaust valve V-28-22 failed to close. However, valve V-28-21, the reactor building main exhaust valve in series with V-28-22, closed as it should have. At 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> the testing of SGIS II was cx:stpleted and SGTS II was dettonstrated operable. The flow sensor for SGIS I was worked on and at appraxi-mately 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> SGTS I was detonstrated operable, but V-28-22 still failed to close.

On Nednesday, July 15, at approx 2mately 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, the reactor building ventilation was secured and SGIS II was initiated. Again V-28-22 failed to close and upon recognition of a Technical Specification violation, an orderly plant shutdown was ccmnenced at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />. At 1018 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.87349e-4 months <br />, valve V-28-22 was manually closed and the shutdown was halted.

Reportable Occurrence Page 2 Peport No. 50-219/81-30/0lT-0 Apparent Cause of Occurrence he cause of SGTS I failure to start was due to a proble with the pitot tube flow sensor. 'Ihe cause of the failure of V-28-22 to close was due to a faulty solenoid. The inability of V-28-22 to isolate was not inmediately recognized as a Technical Specification violation.,

Analysis of Occurrt 3 The Standby Gas Treatment Systs is designed to filter and exhaust reactor building atmosphere to the stack during secondary containment isolation conditions.

Upon initiation of either SGTS, valves V-28-21 and V-28-22 will autmatically close to isolate the reactor building exhaust.

'Ihe safety significance of this occurrence is minimized by the fact that the redundant SGIS was operable. It is also minimized because valve V-28-21 performed its function of isolating the reactor building exhaust. Although section 1.14C of the Technical Specifications requires both V-28-21 and V-28-22.to be closed to satisfy secondary containment integrity requirments, the closure of one of the valves functionally meets the requir m ents of isolating the reactor building exhaust.

Corrective Action

In an attmpt to properly line up SGIS I, the belts on exhaust fan EF l-8 were checked and found in order (EF1-8 exhausts frm SGTS I to the stack). The flow sensor for SGIS I was adjusted to properly sense full flow. A reactor shutdown was initiated and subsequently valve V-28-22 was manually closed and secured.

The plunger and spring actuator assembly of the solenoid which controls the air operator of V-28-22 was replaced, which corrected the probl e with valve V 22. Valve V-28-22 was cycled and demonstrated to be operable at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on July 15, 1981.

Failure Data Solenoid Manufacturer: ASCO 1

Type: 3/4 inch, single actuator, 4-way valve