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Event Notification Report for February 6, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/05/2007 - 02/06/2007

** EVENT NUMBERS **


43038 43141 43142 43143 43144

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 43038
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KENNETH FABER
HQ OPS Officer: JASON KOZAL
Notification Date: 12/07/2006
Notification Time: 21:51 [ET]
Event Date: 12/07/2006
Event Time: 17:28 [EST]
Last Update Date: 02/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARVIN SYKES (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

LOSS OF SAFE SHUTDOWN CAPABILITY

"The Unit 2 Spray Additive System was isolated due to an identified crack on a weld at a 'tee' section of pipe upstream of a sample point. The crack was identified during a system release for an unrelated maintenance activity. Isolation of the crack for repairs requires isolation of the Containment Spray Additive system from both Containment Spray headers. This isolation was also completed to comply with ASME (Technical Specification Action Statement) 3.4.11.1. Therefore the Containment Spray Additive system is unable to perform its safety function. Salem Unit 2 remains in TS A/S 3.6.2.2 until repairs are complete."

TS A/S 3.6.2.2 is a 72 hour LCO (entered at 0503 on 12/07/06) and requires the plant to be in hot standby within 6 hours of the expiration of the LCO.

The licensee will inform the Lower Alloways Creek Township and has informed the NRC Resident Inspector.

* * * RETRACTION FROM ABBOTT TO HUFFMAN AT 2146 EST ON 2/05/07 * * *

"On December 7, 2006, PSEG made a non-emergency report in accordance with the 10 CFR 50.72(b)(3)(v)(A) and 10 CFR 50.72(b)(3)(v)(D) (event report 43038) regarding the Salem Unit 2 Spray Additive System.

"Upon further investigation, PSEG determined that the identified crack on a weld which resulted in a one drop per minute leak would not have caused a loss of system function. Therefore, based upon the guidance provided in NUREG 1022 that there is reasonable assurance that the weld would have remained intact and would have satisfactorily performed its intended function in the event of a CS system actuation (i.e., there was no loss of system safety function) this event report is being retracted.

"The NRC Resident Inspector was notified of this retraction."

R1DO (Cook) notified.

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Power Reactor Event Number: 43141
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JERRY SHEPP
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/05/2007
Notification Time: 06:38 [ET]
Event Date: 02/05/2007
Event Time: 03:07 [EST]
Last Update Date: 02/05/2007
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):
MIKE ERNSTES (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 95 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO STEAM LEAK DURING MAIN FEED BOOSTER PUMP STARTUP

"While starting D Feedwater Booster pump, a steam leak developed in the Turbine building. The Reactor was manually tripped at 0307 on 02/05/07. Investigation revealed that an orifice (XPS0006D) in the D Feedwater Booster pump recirculation header was the source of the leak. The steam/water leak was isolated at 0500 on 02/05/07. All systems responded normally on the Reactor trip. Emergency Feedwater (AFW) system started on LoLo Steam Generator level. Steam Generator level recovered quickly."

All control rods fully inserted on the manual Reactor trip signal. No relief valves or PORVs lifted as a result of the transient. Decay heat is being removed by the main condenser via the steam dump valves.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43142
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN GRAHAM
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/05/2007
Notification Time: 07:24 [ET]
Event Date: 02/05/2007
Event Time: 07:07 [EST]
Last Update Date: 02/05/2007
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
CHRISTOPHER CAHILL (R1)
MARY JANE ROSS-LEE (NRR)
MELVYN LEACH (IRD)
BARNES (DHS)
LIGGETT (FEMA)

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

Event Text

UNUSUAL EVENT DECLARED DUE TO LOW SERVICE WATER INTAKE LEVEL

Licensee provided the following details via facsimile on 02/05/05 at 1305 EST:

"On February 5, 2007, at approximately 05:30 hours, the control room received an alarm for 'intake structure or traveling screen trouble alarm,' and a nuclear plant operator was dispatched to investigate the condition. At approximately 05:57 hours, the control room was notified that the alarm was due to low screen wash pressure on all traveling water screens as a result of the all screen wash pumps found tripped. Review of the Emergency Plan (EP) determined that Emergency Action Level (EAL) 8.4.3, 'Service Water Level 4 Feet, 5 Inches Below Mean Sea Level, 'was met and entry into an Notification of Unusual Event (NUE) was required. At approximately 07:07 hours, operations entered an NUE for EP EAL 8.4.3. Further investigation and corrective action are in progress. At approximately 07:24 hours, the NRC Emergency Operations Center was notified of the NUE (Jeff Rotton)."

Licensee reported entering EAL 8.4.3 - Service Water Bay Level < 4 feet 5 inches below mean sea level. There are presently no other open LCOs that impact Service Water operability.

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1058 EST ON 2/5/07 FROM J. HARVEY TO P. SNYDER * * *

The licensee terminated the Unusual Event at 1014 based on the fact that:
(a) Service Water Bay Levels had increased to 1 ft below mean sea level and were rising,
(b) The licensee initiated cleaning of the trash rack for the intake structure, and
(c) the time for an unusually low tide was now passed.

The licensee notified the NRC Resident Inspector. Notified R1DO (Cahill), IRD Mgr (Leach), NRR EO (Ross-Lee), DHS (T. Barnes), FEMA (C. Liggett), and R4 (L. Howell).

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Power Reactor Event Number: 43143
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DONALD DETTMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 02/05/2007
Notification Time: 08:28 [ET]
Event Date: 02/05/2007
Event Time: 05:25 [EST]
Last Update Date: 02/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTOPHER CAHILL (R1)
NADER MAMISH (DDEP)

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

BLOCKED EMERGENCY VEHICLE ACCESS

"Ginna Station Site access for emergency vehicles has been unavailable since 0525 this morning due to the inability to lower both the North and South Active Vehicle Barriers."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43144
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN FINCH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/05/2007
Notification Time: 12:25 [ET]
Event Date: 02/05/2007
Event Time: 04:30 [EST]
Last Update Date: 02/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WILLIAM COOK (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation

Event Text

LOSS OF STACK EFFLUENT MONITORING CAPABILITY


"At 0430 on 2/5/07, Nine Mile Point Unit 1 determined that the capability to determine effluent radioactivity going out the stack has been lost. It is postulated that this is likely due to moisture in the primary and auxiliary sampling line which has frozen and blocking the flow of effluent to the sample analysis equipment.

"Compensatory actions include monitoring alternate indications of increased radioactivity in the plant effluent steams. A method has been proceduralized to sum systems that input to the stack. Portions of the systems required for monitoring plant effluents are currently out of service for preventive maintenance. It is expected that they will be returned to service by 1700 hours today." The State of New York will be notified of this event.

The NRC Resident Inspector was notified of this event by the licensee.


See similar event # 43125 reported by Nine Mile Point Unit 1 on 01/26/07

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Thursday, March 29, 2012