ML20155C880

Rev 1 to Special Rept 88-01:on 880213,ECCS Actuation Occurred.Caused by Open Main Steam Line Drain Valves & Malfunctioned Main Steam Seal Automatic Pressure Regulator Valve.Eccs Repaired & Plant Restored to Normal

ML20155C880
Person / Time
Site:	Callaway
Issue date:	05/31/1988
From:	Blosser J UNION ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-01, 88-1, ULNRC-1780, NUDOCS 8806140367
Download: ML20155C880 (3)

Text

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UNION Etscraic aCanaway Plat May 31, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ULNRC-1780 Gentlemen:

DOCKET NUFBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30

( SPECIAL REPORT 88-01 REV. 1 EMERGENCY CORE COOLING SYSTEM ACTUATION l The enclosed Special Report is submitted to revise information provided in Special Report 88-01 trancmitted via ULNRC-1770-dated S/9/88. Special Report 88-01 was submitted pursuant to Technical Specification 3.5.2 and 6.9.2 concerning an inadvertent Emergency Core Cooling System actuation. Special Report 88-01 stated that the main steam isolation valves shut in response to an SI. This report has since been revised to identify the valves shutting in response to a Main Steam Line Isolation Signal.

YedW ,

/ . D. Blosser Manager, Callaway Plant .

TPS/ PSP:jlh Enclosure cc: Distribution attached h

8806140367 880531 PDR ADOCK 05000483 S DCD  ;

Mahng Actkess' P.O Box 620 FJton, MO 652S1

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cc distribution for ULNRC-1780 Mr. A. Bert Davis Mr. Thomas Alexion (2 copies)

Regional Administrator Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory _ Commission Region III Mail Stop 13-E-21 799 Roosevelt Road Washington, D.C. 20555 Glen Ellyn, IL 60137 American Nuclear Insurers Mr. O. Maynard -

c/o Dottie Sherman, Library Wolf Creek Nuclear Operating Corp.

The Exchange Suite 245 P. O. Box 411 270 Farmington Avenue Burlington, KS 66839 Farmington, CT 06032 Mr. Merlin Williams Manager, Electric Department Supt of Regulatory Quality &

Missouri Public Service Commission Administrative Services P. O. Box 360 Wolf Creek Nuclear Operating Corp.

Jefferson City, M0 ~65102 P. O. Box 411 Burlington,-KS 66839 Records Center Institute of Nuclear Power Operations Mr. R. W. DeFayette Suite 1500 Chief, Project Section 3A 1100 Circle 75 Parkway U.S. Nuclear Regulatory Commission Atlanta, GA 30339 Region III 799 Roosevelt Road NRC Resident Inspector Glen Ellyn, IL 60137 D. F. Schnell (400)

R. J. Schukai (470)

G. L. Randolph J. F. McLaughlin W. R. Campbell R. P. Wendling (470)

F. D. Field (480)

A. P. Neuhalfen A. C. Passwater/D. E. Shafer/D. J. Walker (470)

G. A. Hughes Z170.05 (QA Record)

Z40SR (Z170.09 Commercial Record)

M. S. Evans M. E. Taylor H. Vuertenbaecher, Jr. (100)

S. L. Auston (470)(NSR3)

S. J. Bellers/J. D. Schnack JDB Chrono 3456-0021.6 3456-0260 Z40ULNRC A160.761 N. Date (Sandra Auston) (470)

SPECIAL REPORT 88-01 REV. 1 EMERGENCY CORE COOLING SYSTEM ACTUATION At 0522 CST on 2/13/88, a Low Steamline Pressure Signal (LSPS) was received resulting in a Safety Injection (SI). At the time of the event,-the plant was in Mode 3, Hot Standby, 0% reactor power. This report is submitted pursuant to Technical Specifications 3.5.2.and 6.9.2.

During restoration from a turbine / reactor trip, utility licensed operators were not continuously cognizant of PCS temperature and consequently did not take effective action to stop the decreasing RCS temperature caused by excessive steam loads. The excessive steam loads were the result of open main steam line drain valves and a malfunctioned main steam seal automatic pressure regulator valve. As part of the restoration, Emergency procedure ES-0.1, "Reactor Trip Response", was entered. The procedure required the temperature of the RCS to be verified at 557'F, but did not provide guidance if the temperature fell below this value. RCS temperature decreased to 495'F resulting in correspondingly lower S/G temperatures and lower steam line pressures. The steam line pressure reached its low setpoint-(615 psig) and an SI and Main Steam Line Isolation (MSLI) resulted._

l In response to the MSLI, the main steam isolation valves shut. The RCS temperature immediately bec,an to return to the normal average temperature of 557'F due to the isolation of the steam loads.

Licensed utility operators performed the appropriate emergency procedures and declared an Unusual Event at 0532 as required by the emergency plan. The plant was restored to a normal condition and the Unusual Event was terminated at 0645. This event was also reported in Licensee Event Report 88-004-00 transnitted via ULNRC-1742 dated 3/14/88.

The total accumulated actuation cycles at operating temperature for the Callaway Plant Emergency Core Cooling System is three. The previous actuations were reported by Special Report 84-03, via ULNRC-970, dated 11/8/84 and Special Report 85-03, via ULNRC-1105, dated 5/31/85. In all three cases, the usage factor for each Safety Injection nozzle was below the 0.70 limit specified in Technical Specification 3.5.2 action (b).

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