ML20154B390

Special Rept 88-01:on 880213,low Steam Line Pressure Signal Received Resulting in Safety Injection.Caused by Personnel Oversight.Msiv Shut

ML20154B390
Person / Time
Site:	Callaway
Issue date:	05/09/1988
From:	Blosser J UNION ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-01, 88-1, ULNRC-1770, NUDOCS 8805170177
Download: ML20154B390 (3)

Text

~

Union Etscriac n

Cabay PLW May 9 , 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ULNRC- 1770 Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 88-01 EMERGENCY CORE COOLING SYSTEM ACTUATION The enclosed Special Report is subaitted pursuant to Technical Specification 3.5.2 and 6.9.2 cc- aing an inadvertent Energency Core Cooling System actuation.

l (ktuuw

~

,_ J. D. Blosser Manager, Callaway Plant PSF:jlh Enclosure cc: Distribution attached 8805170177 880509 PDR ADOCK 05000483 \ )

S DCD A4atng Actress PO. Box 631 fum A40 65:st

, . ~

. cc distribution for ULNRC- 1770 i

Mr. A. Bert Davis Mr. Thomas Alexion (2 copies)

Regic ial Administrator Office of Nuclear Reactor Regulation U.S. Nuclear Rer,ulatory 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, MO 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. E. Evans M. E. Taylor H. Vuertenbaecher, Jr. (100)

S. L. Auston (4~ 0)(NSRB)

S. J. Bellers/J. D. Schnack JDB Chrono

• 3456-0021.6 3456-0260 Z40ULNRC A160.761 N. Date (Sandra Auston) (470)

r e,

< - o SPECIAL REPORT 88-01 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 RCS temperature and consequently did not take effective action to stop the decreasing RCS temperature caused by excessive steam loads. T.e excessive steam loads were the result of open main steam line drain valves and a malfunctioned main steam seal automatic pressure regulator valve. As par'. of the restoration, Energency 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 reach

• its low setpoint (615 psig) and an SI resulted.

In response to the SI, the main steam isolatfor. valves shut. The RCS temperature immediately began to return to the normal average temperature of

$57'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 vae also reported i. Licensee Event Report 88-004-00 transmitted via ULNRC-1742 dated 3/14/88.

The total accumulated actuation cycles at operating temperature for the Callaway Plant Zmergency Core "soling System is three. The previous actuattor.s 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).

,