ML20056A169
| ML20056A169 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/31/1990 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-90278, NUDOCS 9008060002 | |
| Download: ML20056A169 (2) | |
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g Log # TXX-90278 l
File # 10013 F9 10125 9
5 Ref. # 10CFR50.72(a)(1)
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IllELECTRIC Jul 31, 1990 Wlmeen J. Caliitt, Jr.
L%erwon skt bes+no U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50 446 TRANSMITTAL OF REPORT FOLi.9 WING A NOTIFICATION OFUNUSUALEVENT(NUREG-OSSA)
Gentlemen:
As specified in the CPSES Emergency Plan, TV Electric hereby transmits the attached report which summarizes the incident which occurred on July 30, 1990.
As stated in the corrective action, an evaluation is in process and a Licensee Event Report (LER) will be submitted in accordance with 10CFR50.73 by August 29, 1990.
Sincerely, F
)
William J. Cahill, Jr.
FSP/daj c - Mr. R. D. Martin, Region IV l
Mr. J. H. Wilson, NRR ResidentInspectors,CPSES(3)
Mr. Robert Lansford, Division of Emergency Management 9008060002 900731 gDR. ADOCK0500g5
[
P. O. Box 1002 Glen Rose.Tetas 7600-1002
,,
- 6 Et closure TXX 90278 TU Electric Comanche Peak Steam Electric Station. Unit 1 Docket No. 50 445 Notification of an Unusual Event as a Result of Safety injection Actuation Renort Reentrement Evaluation of Radiological Emergency Response PlaThis ns and Preparedness in SuEG 0054, " Criteria f Power Plants" and in acco1 dance with Comanche P Emergency Plan Procedures. The CPSES Emergen eak Steam Electric Station (pport of Nuclear summar (NOUE). y be submitted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cf the closeout of the Notific CPSES)
Event Descrtntion an Unusual Event (RCS) temperature at 550 degrees P and preOn July 30,1990 ssure at 2245 psig, an Engineered Safety Fe Actuation Signal ESFAS) occurTed which result d followed by a Low (low Steam Generator Level React e in the initiation of a Safety Irgection the transient was in accordance with Emerge or Trip Signal. The the Emergency Plan with the Notification of an Uncy Operating Procedures (plant st of the Nuclear Regulatory Commission and the appropri tnusual Ev e to EOPs). Activation of in accordance with the applicable regulatory and procedural requirements,a e o!Tsite agencies was acco injection flow was terminated in accordance with th was terininnted at 2353. The initial review conduct dstable of the affected Steam Generator Atmospheric Relief V hcom n pressure at 2235 pelg. The NOUE e subsequent to the event indicates that all Generator Level Reactor Trip Signal, and a pot a c (SGARV), the Low Low Steamw ng the S SGARV3 rnom. At no time was there a threat t th ential problem with Emergency Lighting the event.
o Immedinte cauw Reactor Operator attempted to throttle SGARV 3 tat the time full open and subsequently returned to appnxtim t l ng maintained using the SGARVs. When the a e y 50 percent open. SGARV 3 hung The sudden opentng of SGARV 3 resulted in a ra id dpercent o
resukant rate compensated low main steamline press oom. SGARY 3 was manually isolated.
p immediately follow ecrease in main steamline pressure. The received, llowever,ing the SI signal, a Low Low Steam Generator level R ure initiated a Safety injection.
Steam Generator level at the time of this signal Corrective Actiong was 72 percent. rip signal was to prevent recuirence will be detennined basedimmediate corr on the results of the Evaluation Team fin associated with the P actions, will be included in the Licensee Event Report including root cause deterinination and recomm e event and the accordance with 10CFR50.73.
o be submitted to the Commission inenda g.--~'-
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