ML20247M448
| ML20247M448 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/26/1989 |
| From: | Blosser J UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-06, 89-6, ULNRC-2045, NUDOCS 8908020103 | |
| Download: ML20247M448 (3) | |
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July 26, 1989 U. S. Nuclear Regulatory Commission Document Control Desk' Washington, DC 20555 ULNRC-2045 Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY. PLANT UNIT 1-FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 89-06 EMERGENCY CORE COOLING SYSTEM ACTUATION
,k This-Special Report is being submitted pursuant to Technical Specification 3.5.2 and 6,9.2 concerning an inadvertent Emergency Core
-Cooling System actuation and-subsequent Safety Injection signal during restoration.
.b W
. D. Blosser Manager, Callaway Plant
'TPS/MKD: jew cc: Distribution attached' 8908020103 890726 PDR. -' ADOCK 05000483 PDC 76N
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' I' Maing Address' PD Box 62Q Fulton, MO 65251 um___________________
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cc distribution for ULNRC-2045 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 l
American Nuclear Insurers Mr. 0. 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. 0. 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)
G. L. Randolph R. P. Wendling (470)
J. V. Laux 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. Wuertenbaecher, Jr. (100)
S. L. Auston (470)(NSRB)
S. J. Bellers/D. R. Oelrichs I
E210.01 Z40ULNRC A160.761 N. Date (Sandra Auston) (470) l l
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SPECIAL REPORT 89-06 EMERGENCY CORE COOLING SYSTZM ACTUATION l
On 5/18/89 at 0300 CDT, an Engineered Safety Feature (ESF) Safety Injection (SI) actuation on Train A was received due to's low steamline pressure signal during a reactor trip breaker Trip Actuating Device Opera-tional Test. During restoration, a second SI signal was received at 0305.
A Reactor Protection System (RPS) actuation, Containment Isolation, Control Room Ventilation Isolation, Main Steamline Isolation, and Motor Driven Auxiliary Feedwater Actuation followed the initial SI.
Identical ESF actua-tion signals were generated from'the second SI signal. The plant was in Mode 4, Hot Shutdown. This report is submitted pursuant to Technical Specifica-tions 3.5.2 and 6.9.2.
During performance of the surveillance test, a licensed operator turned a logic switch the wrong direction. This defertad the low steamline pressure SI block, causing the RPS actuation since steamline pressure is low in Mode 4.
When the mode switch was turned from TEST to OPERATE, the established SI signal caused the Train A SI plant equipment to actuate. During restoration, j
a licensed operator hit the Pressurizer Pressure SI RESET button, instead of the Manual SI RESET button, thus allowing a second SI signal to be processed at 0305. The SI was properly reset at 0313.
An Unusual Event was declared at 0320 as required by the emergency plan.
The plant was restored to a normal condition and the Unusual Event was terminated at 0335. This event was also reported in Licensee Event Report 89-005-00 transmitted via ULNRC-2021, dated 6/19/89.
The total accumulated actuation cycles at operating temperature for the Callaway Plant Emergency Core Cooling System is four. The previous actua-tions were reported by Special Report 84-03, via ULNRC-970, dated 11/8/84, Special Report 85-03, via ULNRC-1105, dated 5/31/85 and Special Report 88-01, via ULNRC-1770, dated 5/9/88.
In all'four 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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