Event Notification Report for November 05, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/04/2008 - 11/05/2008
Power Reactor
Event Number: 44629
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BYYKKONEN
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BYYKKONEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/05/2008
Notification Time: 05:44 [ET]
Event Date: 11/05/2008
Event Time: 00:57 [EST]
Last Update Date: 11/05/2008
Notification Time: 05:44 [ET]
Event Date: 11/05/2008
Event Time: 00:57 [EST]
Last Update Date: 11/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN CARUSO (R1)
JOHN CARUSO (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
EMERGENCY DIESEL GENERATOR START DUE TO UNEXPECTED ESF SIGNAL
"This is an 8-hour notification to report a valid ESF signal to start the 1A Emergency Diesel Generator that occurred on 11/5/08 at 0057. Salem Unit 1 is in Mode 5, with core cooling being provided by 12 RHR pump. The Reactor Coolant System is being maintained at 173 F and 315 PSIG with a pressurizer level of 35 percent. The operating crew was performing a load shed surveillance test for a single component IAW test plan. The test plan used the Safeguards Equipment Cabinet (SEC) test pushbuttons to verify the equipment's response to a load shed signal. When the 1A SEC test pushbutton was actuated in addition to testing the single component it opened the in-feed breaker to the 1A 4KV vital bus and the bus was de-energized and loaded in blackout conditions. All equipment functioned as designed and core cooling was unaffected and remained in-service from 12 RHR pump powered from 1B 4KV bus. Investigation revealed the test plan did not take into account all components operated by the test pushbutton and the test pushbutton operated as designed. The 1A 4KV vital bus was restored to off-site power and the 1A EDG was restored to a standby condition. There were no personnel injured during the event.
"The NRC Resident Inspector has been notified."
LAC Township was notified by the licensee.
Notified R1DO (Caruso).
"This is an 8-hour notification to report a valid ESF signal to start the 1A Emergency Diesel Generator that occurred on 11/5/08 at 0057. Salem Unit 1 is in Mode 5, with core cooling being provided by 12 RHR pump. The Reactor Coolant System is being maintained at 173 F and 315 PSIG with a pressurizer level of 35 percent. The operating crew was performing a load shed surveillance test for a single component IAW test plan. The test plan used the Safeguards Equipment Cabinet (SEC) test pushbuttons to verify the equipment's response to a load shed signal. When the 1A SEC test pushbutton was actuated in addition to testing the single component it opened the in-feed breaker to the 1A 4KV vital bus and the bus was de-energized and loaded in blackout conditions. All equipment functioned as designed and core cooling was unaffected and remained in-service from 12 RHR pump powered from 1B 4KV bus. Investigation revealed the test plan did not take into account all components operated by the test pushbutton and the test pushbutton operated as designed. The 1A 4KV vital bus was restored to off-site power and the 1A EDG was restored to a standby condition. There were no personnel injured during the event.
"The NRC Resident Inspector has been notified."
LAC Township was notified by the licensee.
Notified R1DO (Caruso).
Other Nuclear Material
Event Number: 44630
Rep Org: GEORGIA DEPARTMENT OF NATURAL RESOU
Licensee: CONTOUR ENGINEERING
Region: 1
City: DOUGLASVILLE State: GA
County:
License #: GA-2008-461
Agreement: Y
Docket:
NRC Notified By: ERIC JAMESON
HQ OPS Officer: VINCE KLCO
Licensee: CONTOUR ENGINEERING
Region: 1
City: DOUGLASVILLE State: GA
County:
License #: GA-2008-461
Agreement: Y
Docket:
NRC Notified By: ERIC JAMESON
HQ OPS Officer: VINCE KLCO
Notification Date: 11/05/2008
Notification Time: 15:20 [ET]
Event Date: 11/05/2008
Event Time: 10:45 [EST]
Last Update Date: 11/05/2008
Notification Time: 15:20 [ET]
Event Date: 11/05/2008
Event Time: 10:45 [EST]
Last Update Date: 11/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN CARUSO (R1)
GREG SUBER (FSME)
JOHN CARUSO (R1)
GREG SUBER (FSME)
AGREEMENT STATE REPORT - DAMAGED TROXLER MOISTURE DENSITY GAUGE
"On 11/5/2008 at approximately 10:45 am, the licensee had a Troxler moisture-density gauge (Model 3430, S/N 33839) on the ground in the "standardize" mode (sources shielded) when it was run over by heavy mechanical equipment. Licensee staff roped off the area around the gauge and maintained surveillance of the gauge until the RSO and consultant arrived. Based on a radiation survey, there was no apparent loss of shielding integrity. Results of leak tests on the sealed sources are pending. Gauge was transported back to the licensee's office for further evaluation and likely return to Troxler."
Amount of activity: 8 mCi (Cs-137) and 40 mCi (Am-241)
Georgia Report Number: GA-2008-461
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.
"On 11/5/2008 at approximately 10:45 am, the licensee had a Troxler moisture-density gauge (Model 3430, S/N 33839) on the ground in the "standardize" mode (sources shielded) when it was run over by heavy mechanical equipment. Licensee staff roped off the area around the gauge and maintained surveillance of the gauge until the RSO and consultant arrived. Based on a radiation survey, there was no apparent loss of shielding integrity. Results of leak tests on the sealed sources are pending. Gauge was transported back to the licensee's office for further evaluation and likely return to Troxler."
Amount of activity: 8 mCi (Cs-137) and 40 mCi (Am-241)
Georgia Report Number: GA-2008-461
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.
Power Reactor
Event Number: 44632
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILLY JOHNSON
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILLY JOHNSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/06/2008
Notification Time: 00:59 [ET]
Event Date: 11/05/2008
Event Time: 22:54 [EST]
Last Update Date: 11/06/2008
Notification Time: 00:59 [ET]
Event Date: 11/05/2008
Event Time: 22:54 [EST]
Last Update Date: 11/06/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BINOY DESAI (R2)
BINOY DESAI (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
BOTH TRAINS OF CONTROL ROOM EMERGENCY AIR TEMPERATURE CONTROL DECLARED INOP
"WBN Unit 1 initiated a Tech Spec required shutdown at 2254 on 11/05/08. The plant entered TS 3.0.3 at 2135 on 11/05/08 due to both trains of Control Room Emergency Air Temperature Control (CREATCS) being declared inoperable. Initially Train 'B' CREATCS was inoperable due to the scheduled maintenance of Train 'B' auxiliary air system. With one train of Aux Air inoperable this renders that respective train of CREATCS inoperable. During this planned maintenance the 'A' train CREATCS chiller lost ability to cool the Main Control Room due to a failure in the control circuitry. This rendered 'A' train inoperable which led to entry into TS 3.0.3 for both trains CREATCS being inoperable. The plant exited TS 3.0.3 at 2345 on 11/05/08 upon completion of Post Maintenance Testing on the train 'B' Aux Air system and return to operability of the 'B' train Aux Air and therefore the 'B' train of CREATCS. The planned plant shutdown was stopped upon exit of TS 3.0.3 at 2345 11/05/08 and Rx power restored to 100%."
The licensee notified the NRC Resident Inspector
"WBN Unit 1 initiated a Tech Spec required shutdown at 2254 on 11/05/08. The plant entered TS 3.0.3 at 2135 on 11/05/08 due to both trains of Control Room Emergency Air Temperature Control (CREATCS) being declared inoperable. Initially Train 'B' CREATCS was inoperable due to the scheduled maintenance of Train 'B' auxiliary air system. With one train of Aux Air inoperable this renders that respective train of CREATCS inoperable. During this planned maintenance the 'A' train CREATCS chiller lost ability to cool the Main Control Room due to a failure in the control circuitry. This rendered 'A' train inoperable which led to entry into TS 3.0.3 for both trains CREATCS being inoperable. The plant exited TS 3.0.3 at 2345 on 11/05/08 upon completion of Post Maintenance Testing on the train 'B' Aux Air system and return to operability of the 'B' train Aux Air and therefore the 'B' train of CREATCS. The planned plant shutdown was stopped upon exit of TS 3.0.3 at 2345 11/05/08 and Rx power restored to 100%."
The licensee notified the NRC Resident Inspector