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Event Notification Report for April 13, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/12/2004 - 04/13/2004

** EVENT NUMBERS **


40654 40667 40670 40671

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General Information or Other Event Number: 40654
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: OWENSBY AND KRITIKOS INC
Region: 4
City: GRETNA State: LA
County:
License #: LA-2234-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: BILL GOTT
Notification Date: 04/07/2004
Notification Time: 21:45 [ET]
Event Date: 04/07/2004
Event Time: 20:00 [CDT]
Last Update Date: 04/12/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4)
C.W. (BILL) REAMER (NMSS)
DONNA-MARIE PEREZ (TAS)

Event Text

LOUISIANA AGREEMENT STATE REPORT - LOST RADIOGRAPHY CAMERA IN THE GULF OF MEXICO

While passing a SPEC 150 Industrial Radiography Camera from a boat to an Apache Corporation Petroleum platform in the Gulf of Mexico, the radiography camera fell into the water. The water depth is 60 to 70 feet and is located approximately 50 to 70 miles from the coast of LA. The lost camera was a SPEC 150 S/N 223 with a 24 Curie Ir-192 source S/N 12433B. The radiography camera was in a Type B shipping container. The licensee plans on using divers to retrieve the radiography camera.

* * * UPDATE 0940 EDT ON 4/12/04 FROM MIKE CIULLA TO S. SANDIN * * *

The LA licensee notified the State of Louisiana (Joe Noble) that the camera was recovered on 4/10/04 at approximately 0930 CDT and has been returned to the manufacturer for evaluation.

Notified R4DO (Powers), NMSS (Essig) and TAS (Hahn).

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Power Reactor Event Number: 40667
Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SCOTT SMITH
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/12/2004
Notification Time: 05:25 [ET]
Event Date: 04/12/2004
Event Time: 03:47 [CDT]
Last Update Date: 04/12/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
THOMAS DECKER (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 0 Startup 0 Hot Standby

Event Text

UNIT 2 EXPERIENCED A REACTOR TRIP DURING STARTUP DUE TO AN INVALID SR TRIP SIGNAL

"Unit 2 reactor tripped during low power physics testing. Trip appeared to be from an invalid source range [SR] trip signal in one train of solid state protection system. All systems responded properly. The Unit is currently stable in mode 3."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 40670
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: VAN FORD
HQ OPS Officer: ARLON COSTA
Notification Date: 04/12/2004
Notification Time: 15:43 [ET]
Event Date: 04/12/2004
Event Time: 10:33 [EDT]
Last Update Date: 04/12/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BRIAN MCDERMOTT (R1)

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

Event Text

ACCIDENT MITIGATION - COMMON CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM

"Salem Unit 2 was placed in a configuration that affected the ability to mitigate the consequences of an accident due to an inadvertent actuation of the common control room emergency air conditioning system (CREACS). CREACS was actuated as a result of an invalid safety injection signal initiated on April 12, 2004 at 1033 hours, during solid state protection system testing on Salem Unit-1. Salem Unit-1 is currently defueled. Salem Unit 2 is in Mode 1 at 100% power. Unit 2 has two shutdown LCOs in effect. The first is for the CREACS system, which is shared between Unit 1 & 2, being aligned for single train operation with the Unit 1 CREACS train out of service per LCO 3.7.6a. The second shutdown LCO is for two outside air intake dampers being inoperable for scheduled maintenance.

"With Unit 1 having an invalid Safety Injection signal, the CREACS system actuates in accident pressurized mode. This mode of actuation starts the CREACS fans, isolates the Control Room Envelope from the normal control room ventilation system and aligns the two sets of CREACS outside air intake dampers. With a Unit 1 Sl signal, the Unit 1 CREACS intake dampers close and the Unit 2 CREACS intake dampers open. These damper positions are locked in until manually reset. With only one train of CREACS operable, the dose analysis indicates that the requirements of General Design Criterion (GDC) 19 can only be met during a the worst case design basis accident if the Unit 2 CREACS intake dampers are closed and the Unit 1 CREACS intake dampers open. Therefore, until the CREACS intake dampers were reset and realigned, Salem Unit 2 would not have been able to mitigate the consequences of an accident and is reportable in accordance with 10CFR50.72(b)(3)(v)(D). The CREACS system actuation was reset and the dampers were re-aligned to their pre-actuation alignment at 1232 hours, restoring Salem Unit 2 to within the assumptions of the dose analysis.

"As a result of the Unit 1 Safety Injection signal, all available equipment started as designed. Since the SI signal has been determined to be invalid the start of this equipment is not reportable per 10CFR50.72(b)(3)(iv)(B). The Unit-1 Safety Injection signal has been cleared and an investigation of the cause is in progress.

"The only piece of major equipment out of service on Salem Unit 2 is the 25 Service water pump which is out of service for scheduled maintenance."

The Licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40671
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: EDWARD BURNS
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/13/2004
Notification Time: 00:46 [ET]
Event Date: 04/12/2004
Event Time: 18:10 [CDT]
Last Update Date: 04/13/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRIS MILLER (R3)

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

Event Text

HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) DECLARED INOPERABLE

"High Pressure Coolant Injection System Incapable of Performing its intended Safety Function.

This report is being made in accordance with 10 CFR 50.72(b)(3)(v) due the High Pressure Coolant Injection System being incapable of performing its intended safety function.

At 1810 hours (CDT) during performance of the functional test of the level instrumentation for the automatic realignment of the High Pressure Coolant Injection system (HPCI) suction sources, plant maintenance person identified that logic circuitry leads had been lift. The leads not being connected would prevent the automatic realignment of the HPCI suction from its non-safety related source, the Condensate Storage Tank (CST), to its safety related source, the Suppression Pool.

Based on preliminary information, the leads were lifted during scheduled maintenance activities on the HPCI system in March.

The applicable Technical Specification specified that HPCI be declared inoperable within an hour. Actions were immediately taken to restore the automatic function. The leads were re-landed and the TS condition exited at 1853 hours.
The inability of the system to automatically realign due to a CST low level or a Suppression Pool high level is considered to be a condition that would prevent the fulfillment of the safety function of the HPCI system."

The licensee is still investigating the cause.

The NRC Resident Inspector was notified.

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Friday, March 30, 2012