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Event Notification Report for March 24, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/23/2004 - 03/24/2004

** EVENT NUMBERS **


40472 40481 40557 40605 40606 40607 40608

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Power Reactor Event Number: 40472
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAVID FRYE
HQ OPS Officer: MIKE RIPLEY
Notification Date: 01/23/2004
Notification Time: 17:45 [ET]
Event Date: 01/23/2004
Event Time: 15:29 [EST]
Last Update Date: 03/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CLIFFORD ANDERSON (R1)
HERB BERKOW (NRR)
RICHARD WESSMAN (DIRO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP WITH SAFETY INJECTION ACTUATION SIGNALS

"At 1529 ET the reactor was manually tripped due to low steam generator level as a result of the loss of the 22 SGFP (Steam Generator Feed Pump). When the reactor was tripped, the turbine bypass and atmospheric dump valves went full open and did not shut. This lead to a SIAS (Safety Injection Actuation Signal) and SGIS (Steam Generator Isolation Signal). At 1718 ET, a second SIAS actuation occurred while reestablishing pressurizer level. The cause of the SGFP trip is unknown. The cause of the over steaming on turbine bypass valves and atmospheric dump valves is unknown."

All control rods fully inserted. Auxiliary Feedwater initiated normally. The licensee stated that there was no actual ECCS injection to the RCS. The plant electrical system responded normally and all emergency diesel generators remain operable. All ECCS systems remain operable. There are no primary to secondary leaks. Decay heat is currently being removed via the steam-driven auxiliary feedwater pump and the atmospheric steam dumps. As of 1830 ET, primary pressure is approximately 2103 psi and pressurizer level is at 242 inches. Plant conditions are being stabilized at normal hot standby values . The licensee notified the NRC Resident Inspector who responded to the Control Room.


* * * UPDATE FROM PACE TO GOTT ON 1/26/04 AT 1438 EST * * *

The licensee reported that their post trip review determined that the reactor received an automatic trip about 2 seconds before the manual trip. The automatic trip was due to low steam generator water level.

The licensee notified the NRC Resident Inspector.

Notified NRR (Reis) and R1DO (Meyer)

* * * UPDATE ON 03/23/04 @ 1604 BY DAVID FRYE TO C. GOULD * * *

During post event review of the 1/23/04 Rx Trip event (40472), it was discovered that Unit 2 met the entry criteria for EOP-4, Excess Steam Demand event. This condition required declaration of an Unusual Event. No declaration was made at the time because of the transitory nature of the condition. Transitory conditions such as this, however, still require reporting per NUREG-1022, Rev. 2. Immediate notification to the NRC via the Emergency Notification System is required per 10 CFR 50.72(a)(1)(i).

The NRC Resident Inspector will be notified.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40481
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: BILL GOTT
Notification Date: 01/26/2004
Notification Time: 20:20 [ET]
Event Date: 01/26/2004
Event Time: 14:30 [CST]
Last Update Date: 03/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BRUCE BURGESS (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

RECIRCULATION FAN ALTERATION AFFECTS ACCIDENT MITIGATION

"V-ERF-11 ('A' Emergency Filtration Train (EFT) recirculation fan) was found to have an improper alteration affecting the fan's shaft speed, and 'A' EFT was declared inoperable. Concurrently, the #12 Emergency Diesel Generator (EDG) was inoperable for planned maintenance, making 'B' EFT inoperable. This condition is a loss of safety function during a design basis accident, and impacts the ability of the plant to mitigate the consequences of an accident."

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 1/26/04 AT 2112 EST FROM RASK TO GOTT * * *

At 1958 CST the licensee declared the #12 EDG operable and thus the #12 ("B") EFT was also operable. Additionally, at 2010 the licensee declared the #11 ("A") EFT operable.

Notified R3DO (Burgess).

* * * RETRACTION AT 1043 ON 3/23/04 BLAKESLEY TO GOTT * * *

Based on further investigation V-ERF-11 ('A' Emergency Filtration Train (EFT) recirculation fan) would have been able to provide the required flow and would have fulfilled its required safety functions with the improper alterations. Therefore the event was not reportable.

Notified R3DO ( O'Brien).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40557
Facility: OCONEE
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/01/2004
Notification Time: 04:17 [ET]
Event Date: 02/29/2004
Event Time: 20:11 [EST]
Last Update Date: 03/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHARLES R. OGLE (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 96 Power Operation 96 Power Operation

Event Text

UNIT 2 AUTOMATIC FEEDWATER ISOLATION SYSTEM (AFIS) DECLARED INOPERABLE

The licensee reported that both digital trains of the automatic feedwater isolation system were declared inoperable when one channel's input failed to zero and about the same time the second channel showed a shift in readouts which was fairly significant that they also declared it inoperable. These two channels have a shared neutral bus and it is believed that there may be a loose connection somewhere in the circuit. They are currently troubleshooting the problem. Plant will initiate a unit shutdown if the problem cannot be corrected by 0600 on 03/01/04 (12-hour LCO A/S).

The NRC Resident Inspector will be notified.

* * * * UPDATE ON 03/23/04 @ 1348 BY RANDY TODD TO C. GOULD * * * * RETRACTION

Update- FNS 40557, dated 3-1-04, addressed an apparent loss of safety function on Oconee Unit 2. Specifically, the Automatic Feedwater Initiation System (AFIS) was considered inoperable, and therefore unable to perform its required safety functions. During that event, Operations shift personnel conservatively declared AFIS Channel 2 inoperable because it demonstrated an unexpected shift in readout concurrent with the failure of Channel 1. Subsequently Duke power concluded that Channel 2 remained capable of performing its safety function despite the shift in readout, which was in the conservative direction. Therefore, Duke Power has concluded that there was no reportable loss of safety function associated with this event and hereby retracts ENS notification 40557. Duke Power notes that, during the event, both channels were intentionally disabled for a brief period as a planned part of the repair activity. This was done to prevent the possibility of a spurious actuation during the repair. However, per guidance in NUREG 1022, removal of both trains of a safety function as part of a planned activity which results in entry into a Tech Spec action statement is not reportable. Initial Safety Significance: Operations declared TS 3.3.13 Condition B, which allowed 12 hours to come to Mode 3. Repairs were completed prior to initiation of shutdown. Corrective Action(s): A loose wiring connection was repaired.

The NRC Resident Inspector was informed.

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Power Reactor Event Number: 40605
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/23/2004
Notification Time: 11:00 [ET]
Event Date: 03/23/2004
Event Time: 07:46 [EST]
Last Update Date: 03/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
FRANK COSTELLO (R1)

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

Event Text

INDICATION OF CRACK FAILURE ON RCS PRESSURE BOUNDARY PENETRATION

"Unit 1 is currently in a refueling outage in Mode 5. During a routine inservice inspection of the reactor vessel, an indication was discovered on the N1B penetration. This is associated with the suction for B Loop of Reactor Recirculation. At 0746 on 3/23/2004, the Control Room was notified that the evaluation was completed and the indication was determined to be unacceptable under the ASME Section XI Code. Based on guidance provided in NUREG-1022, Rev. 2, this material defect in the primary coolant boundary constitutes a seriously degraded condition and is reportable under 10CFR50.72(b)(3)(ii)(A). A final evaluation of the flaw and a repair plan is being developed."

The licensee informed the NRC Resident Inspector.

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Other Nuclear Material Event Number: 40606
Rep Org: US ARMY
Licensee: US ARMY
Region: 3
City: ROCK ISLAND State: IL
County:
License #: 12-00722-06
Agreement: Y
Docket:
NRC Notified By: THOMAS GIZICKI
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/23/2004
Notification Time: 15:15 [ET]
Event Date: 03/23/2004
Event Time: 12:15 [CST]
Last Update Date: 03/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
KENNETH O'BRIEN (R3)
DAVID GRAVES (R4)
JOHN HICKEY (NMSS)

Event Text

THE US ARMY REPORTED A MISSING BEAM SPLITTER FOR A M1A1 TANK.

On 03/03/04 the Texas National Guard discovered that one of their M1A1 tanks which was stored in a outside fenced area at their Army training facility in Wylie, Texas was missing a tritium beam splitter from its muzzle reference sensor. A thorough search was made of the entire area with negative results and a wipe of the tank also tested negative. The beam splitter contained a sealed 10 curie tritium source. All of the other tanks stored in the same fenced area with the one having the missing source were inspected and found to be intact.

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Power Reactor Event Number: 40607
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD WHITE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/23/2004
Notification Time: 16:49 [ET]
Event Date: 03/23/2004
Event Time: 14:32 [EST]
Last Update Date: 03/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
FRANK COSTELLO (R1)

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

Event Text

OFFSITE NOTIFICATIONS MADE DUE TO AN ETHYLENE GLYCOL SPILL FROM UNDERGROUND PIPING

Environmental state notification was made on 3/23/04 due to an ethylene glycol spill from the underground circulating water (CW) boiler piping. The spill is isolated and contained on site. Clean-up is in progress, and no discharge to the river occurred. Approximately 100 gallons of ethylene glycol has been cleaned up. The CW system is not effected by this spill. There were no injuries as a result of the spill.

The NRC Resident Inspector will be notified.

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Power Reactor Event Number: 40608
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: RICHARD SWEENEY
HQ OPS Officer: BILL GOTT
Notification Date: 03/24/2004
Notification Time: 04:39 [ET]
Event Date: 03/24/2004
Event Time: 03:31 [EST]
Last Update Date: 03/24/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RUDOLPH BERNHARD (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP

"At approximately 0331 EST the reactor tripped due to reactor protection system actuation. The Emergency Feedwater System actuated.

"It appears that a main feedwater perturbation [sensed low feedwater flow] occurred which actuated a main turbine trip. The main turbine trip actuated the reactor protection system which tripped the reactor."

The reactor shutdown and all control rods fully inserted. Decay heat is being removed using the turbine bypass valves and emergency feedwater.

The Licensee notified the NRC Resident Inspector.

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