United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2003 > November 18

Event Notification Report for November 18, 2003

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/17/2003 - 11/18/2003

** EVENT NUMBERS **


40325 40326 40327

To top of page
Power Reactor Event Number: 40325
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JEFF SMITH
HQ OPS Officer: BILL GOTT
Notification Date: 11/17/2003
Notification Time: 09:35 [ET]
Event Date: 11/17/2003
Event Time: 01:10 [CST]
Last Update Date: 11/17/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANNE MARIE STONE (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

EVENT OR CONDITION THAT COULD HAVE PREVENTED FULFILLMENT OF A SAFETY FUNCTION

"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to mitigate the consequences of an Accident. During performance of scheduled surveillance test LIS-HP-310, Reactor Vessel High Water Level 8 [High Pressure Core Spray] HPCS Injection Valve Closure Instrument Channels A and B Functional Test, Instrument Maintenance personnel discovered one end of fuse 1B21A-F8 not fully seated. The other end of the fuse was fully seated, and was maintaining the un-clipped end in sufficient contact with the fuse holder to complete the circuit. Had the circuit been deenergized, a Control Room annunciator (1H13-P601 A404) would have alarmed, and High Pressure Core Spray (HPCS) automatic low level initiation circuits would have been disabled. The fuse was fully seated without incident.

"Upon discovery of the unseated fuse, the initial operability determination concluded that adequate contact was maintained to keep the circuit OPERABLE. After followup evaluation by Engineering, it was determined that continued OPERABILITY could not be assured during a seismic event. Failure of this fuse would prevent automatic actuation of HPCS on reactor vessel level low 2; and would prevent automatic closure of the HPCS discharge valve 1E22-F004 on reactor vessel level high 8. This would prevent the HPCS system, a single train safety system, from performing its design function during a Loss of Coolant Accident subsequent to a seismic event. This is reportable as an 8 hour ENS notification."

The licensee informed the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 40326
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/17/2003
Notification Time: 15:26 [ET]
Event Date: 11/17/2003
Event Time: 12:10 [EST]
Last Update Date: 11/17/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRISTINE LIPA (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

DIVISION 1 AND 2 DIESEL GENERATORS AND ALL ECCS SYSTEMS WERE DECLARED INOPERABLE

While aligning the Emergency Service Water (ESW) to the swale, the sluice gates were opened without the ESW being aligned to the swale. This condition made both Div 1&2 Diesel Generators and all ECCS systems inoperable. The probable cause of this event is that the wrong procedure was used in this evolution. Procedure SOI-P45/49 sec 7.3.1 "ESW Pumphouse Forebay Emergency Supply Initiation" was used instead of the correct procedure SOI-P45/49 section 7.3.3. "Alignment of ESW to Pumphouse Forebay Emergency Supply". The condition was discovered at 1215 and corrected at 1220 after section 7.3.1 was exited and section 7.3.3 was used to complete the lineup to the swale.

The Nrc Resident Inspector was notified.

To top of page
Power Reactor Event Number: 40327
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVID DEES
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/17/2003
Notification Time: 16:08 [ET]
Event Date: 11/17/2003
Event Time: 09:00 [CST]
Last Update Date: 11/17/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
KRISS KENNEDY (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

REACTOR COOLANT SYSTEM LEAKAGE DUE TO A CRACKED SOCKET WELD

During routine operations activities a leak was identified in the area of EPV0109 (combined SI/RHR to Accumulator "D" outlet line vent). At 0900 it was determined that the leak was due to a cracked weld on the socket up stream of EPV0109. The leak rate is 25-30 drops/per minute
.
This condition is being reported as a degraded condition in the primary coolant system under 10CFR50.72(b)(3)(ii)(A).
The plant is currently in Mode 5 with RCS pressure at approximately 345 psig and temperature at approximately 125F. Shutdown cooling is being supplied by the "A" train Residual Heat Removal System.

The Resident Inspector has been notified.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012