Event Notification Report for April 26, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/25/2006 - 04/26/2006
EVENT NUMBERS
4252842529425304253942546
Power Reactor
Event Number: 42528
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: JERRY RISTE
HQ OPS Officer: ARLON COSTA
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: JERRY RISTE
HQ OPS Officer: ARLON COSTA
Notification Date: 04/26/2006
Notification Time: 18:23 [ET]
Event Date: 04/26/2006
Event Time: 17:00 [CDT]
Last Update Date: 04/26/2006
Notification Time: 18:23 [ET]
Event Date: 04/26/2006
Event Time: 17:00 [CDT]
Last Update Date: 04/26/2006
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):
HIRONORI PETERSON (R3)
HIRONORI PETERSON (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 92 | Power Operation |
PLANT S/D REQUIRED BY TS DUE TO LEAK IN SERVICE WATER SUPPLY LINE TO "B" EDG
"At 1345 on April 26, 2006, a decision to shutdown the plant was made due to an Inoperable service water train. At 1700 on April 26, 2006, the plant shutdown was initiated.
"On April 25, 2006, a leak was found on the Service Water supply line to the 'B' emergency diesel generator. At 1725 on April 25, 2006, the 'B' train of service water was declared inoperable and the technical specification limiting condition for operation was entered for one train of service water being inoperable. The end state for exceeding the allowed outage time for the limiting condition for operation for service water is the reactor coolant system Tavg less than 350 degrees Fahrenheit.
"During investigation of the leak, an additional small leak was discovered approximately 180 degrees from the first leak on the same section of pipe. Based on this additional leak, a conservative decision was made to shutdown the unit.
"It is estimated that the repair to the service water piping would not be completed within the allowed outage time and therefore per 10CFR50.72(b)(2)(i) this event is reportable as the initiation of any nuclear plant shutdown required by plant's technical specifications."
All systems are currently functioning as required for the unit shutdown and the "B" EDG is operable and available.
The licensee notified the NRC Resident Inspector.
"At 1345 on April 26, 2006, a decision to shutdown the plant was made due to an Inoperable service water train. At 1700 on April 26, 2006, the plant shutdown was initiated.
"On April 25, 2006, a leak was found on the Service Water supply line to the 'B' emergency diesel generator. At 1725 on April 25, 2006, the 'B' train of service water was declared inoperable and the technical specification limiting condition for operation was entered for one train of service water being inoperable. The end state for exceeding the allowed outage time for the limiting condition for operation for service water is the reactor coolant system Tavg less than 350 degrees Fahrenheit.
"During investigation of the leak, an additional small leak was discovered approximately 180 degrees from the first leak on the same section of pipe. Based on this additional leak, a conservative decision was made to shutdown the unit.
"It is estimated that the repair to the service water piping would not be completed within the allowed outage time and therefore per 10CFR50.72(b)(2)(i) this event is reportable as the initiation of any nuclear plant shutdown required by plant's technical specifications."
All systems are currently functioning as required for the unit shutdown and the "B" EDG is operable and available.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 42529
Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: CHRIS POULOS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: CHRIS POULOS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/26/2006
Notification Time: 18:55 [ET]
Event Date: 04/26/2006
Event Time: 18:19 [EDT]
Last Update Date: 04/26/2006
Notification Time: 18:55 [ET]
Event Date: 04/26/2006
Event Time: 18:19 [EDT]
Last Update Date: 04/26/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
FIRE IN ADMINISTRATION BUILDING
At approximately 18:19, a fire occurred in the administration building lower level. The fire was in the southeast corner of the building in a communications room (PBX room). The fire department was called and extinguished the fire at 19:04. No injuries were reported. The fire did not affect the ISFSI and backup communications were available if required.
Notified the R1DO (Barkley).
At approximately 18:19, a fire occurred in the administration building lower level. The fire was in the southeast corner of the building in a communications room (PBX room). The fire department was called and extinguished the fire at 19:04. No injuries were reported. The fire did not affect the ISFSI and backup communications were available if required.
Notified the R1DO (Barkley).
Power Reactor
Event Number: 42530
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: JONATHAN ROBB
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: JONATHAN ROBB
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/26/2006
Notification Time: 22:39 [ET]
Event Date: 04/26/2006
Event Time: 20:49 [CDT]
Last Update Date: 04/27/2006
Notification Time: 22:39 [ET]
Event Date: 04/26/2006
Event Time: 20:49 [CDT]
Last Update Date: 04/27/2006
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
HIRONORI PETERSON (R3)
PETER WILSON (IRD)
MIKE WEBER (NRR)
MARY JANE ROSS-LEE (NRR)
JIM CALDWELL (RA)
HIRONORI PETERSON (R3)
PETER WILSON (IRD)
MIKE WEBER (NRR)
MARY JANE ROSS-LEE (NRR)
JIM CALDWELL (RA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A | Y | 35 | Power Operation | 0 | Hot Standby |
FAILURE OF RPS SIGNAL TO INITIATE REACTOR TRIP
"At 2043 [CDT] on 4-26-06, during a plant shutdown with the reactor at approximately 35% power, the operating crew manually initiated a reactor trip. The operating crew had just stopped one of the two condensate pumps and then the remaining feedwater pump tripped unexpectedly. The operating crew recognized the turbine did not trip, as it is expected to automatically trip when no feedwater pumps are running. The automatic turbine trip would have automatically tripped the reactor. Therefore, the operating crew manually initiated a reactor trip.
"Because the reactor did not automatically trip (i.e., failure of RPS to initiate and complete a reactor trip), the Shift Manager declared an Alert, at 2049, based on Chart F of Table 2-1 EPIP-AD-02. Therefore, this is a one-hour notification in accordance with 10CFR50.72(a)(1)(i) 'The declaration of any of the emergency classes specified in the licensee's approved Emergency Plan.'
"The manual reactor trip is reportable (4-hour) in accordance with 10CFR50.72(b)(2)(iv)(B) 'Any event or condition that results in an actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'
"All systems functioned as expected following the manual reactor trip. Service Water Train B is inoperable because of a one-gallon per minute leak."
All rods inserted fully. Decay heat is being removed with the steam dump and secondary PORVs. The condenser is losing vacuum due to the turbine trip. Auxiliary Feedwater Pumps started as required.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM JERRY RISTE TO JOHN KNOKE AT 01:45 EDT ON 04/27/06 * * *
"At 2049 on April 26, 2006, Kewaunee Power Station staff declared an Alert emergency classification (reference EN# 42530). The Kewaunee Power Station staff has assessed this event. There was no affect on the health and safety of the general public and no release of radiation. No plant personnel were injured and the only plant equipment problem was with the failure of a trip of both feedwater pumps to cause the main turbine to trip. The Kewaunee Power Plant staff has conducted a preliminary investigation of the control room indications and sequential events recorder, which indicates that before the manual reactor trip there was no automatic reactor trip signal present and a failure of the reactor trip breakers did not occur. The Alert was terminated at 0024 CDT [on 04/27/06]. The unit is currently in the Hot Shutdown Mode with plans to cool the plant to less than 350 degrees Fahrenheit."
The licensee notified the NRC Resident Inspector and will be notifying State and local government and issuing a press release. Notified NRR EO (MJ Ross-Lee), IRD Mgr (P. Wilson), R3DO (H. Peterson), DHS (Holz ), FEMA (Steindurf), NRC/EPA (Crews), DOE (Wyatt), USDA (Timmons), HHS (Peagler).
* * * UPDATE ON 04/27/06 AT 1718 EDT FROM JERRY RISTE TO ARLON COSTA * * *
"When performing a review of the event reported on April 26, 2006 (EN# 42530), the Kewaunee Power Station staff determined another reporting criterion was met. An eight-hour report is required to be made per 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of 10 CFR 50.72 except when the actuation results from and is apart of a pre-planned sequence during testing or reactor operation.' 10 CFR 50.72(b)(3)(iv)(B)(6) is PWR auxiliary or emergency feedwater system.
"As described in EN# 42530, a manual reactor trip of the Kewaunee Power Station was initiated at 2043 on April 26, 2006. The manual reactor trip was initiated when the plant experienced a loss of both feedwater pumps. With a loss of both feedwater pumps and a manual reactor trip, the narrow range water level in both steam generators decreased to the actuation setpoint value for starting the Auxiliary Feedwater Pumps, causing all three Auxiliary Feedwater Pumps to start as designed. Because the steam generator water level was below the actuation setpoint, this was a valid actuation of the auxiliary feedwater system. As a valid actuation of the auxiliary feedwater system, this condition is reportable under 10 CFR 50.72(b)(3)(iv).
"The untimeliness of the report has been entered into the Kewaunee Power Station's corrective action program."
The licensee notified the NRC Resident Inspector. Notified R3DO (H. Peterson).
"At 2043 [CDT] on 4-26-06, during a plant shutdown with the reactor at approximately 35% power, the operating crew manually initiated a reactor trip. The operating crew had just stopped one of the two condensate pumps and then the remaining feedwater pump tripped unexpectedly. The operating crew recognized the turbine did not trip, as it is expected to automatically trip when no feedwater pumps are running. The automatic turbine trip would have automatically tripped the reactor. Therefore, the operating crew manually initiated a reactor trip.
"Because the reactor did not automatically trip (i.e., failure of RPS to initiate and complete a reactor trip), the Shift Manager declared an Alert, at 2049, based on Chart F of Table 2-1 EPIP-AD-02. Therefore, this is a one-hour notification in accordance with 10CFR50.72(a)(1)(i) 'The declaration of any of the emergency classes specified in the licensee's approved Emergency Plan.'
"The manual reactor trip is reportable (4-hour) in accordance with 10CFR50.72(b)(2)(iv)(B) 'Any event or condition that results in an actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'
"All systems functioned as expected following the manual reactor trip. Service Water Train B is inoperable because of a one-gallon per minute leak."
All rods inserted fully. Decay heat is being removed with the steam dump and secondary PORVs. The condenser is losing vacuum due to the turbine trip. Auxiliary Feedwater Pumps started as required.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM JERRY RISTE TO JOHN KNOKE AT 01:45 EDT ON 04/27/06 * * *
"At 2049 on April 26, 2006, Kewaunee Power Station staff declared an Alert emergency classification (reference EN# 42530). The Kewaunee Power Station staff has assessed this event. There was no affect on the health and safety of the general public and no release of radiation. No plant personnel were injured and the only plant equipment problem was with the failure of a trip of both feedwater pumps to cause the main turbine to trip. The Kewaunee Power Plant staff has conducted a preliminary investigation of the control room indications and sequential events recorder, which indicates that before the manual reactor trip there was no automatic reactor trip signal present and a failure of the reactor trip breakers did not occur. The Alert was terminated at 0024 CDT [on 04/27/06]. The unit is currently in the Hot Shutdown Mode with plans to cool the plant to less than 350 degrees Fahrenheit."
The licensee notified the NRC Resident Inspector and will be notifying State and local government and issuing a press release. Notified NRR EO (MJ Ross-Lee), IRD Mgr (P. Wilson), R3DO (H. Peterson), DHS (Holz ), FEMA (Steindurf), NRC/EPA (Crews), DOE (Wyatt), USDA (Timmons), HHS (Peagler).
* * * UPDATE ON 04/27/06 AT 1718 EDT FROM JERRY RISTE TO ARLON COSTA * * *
"When performing a review of the event reported on April 26, 2006 (EN# 42530), the Kewaunee Power Station staff determined another reporting criterion was met. An eight-hour report is required to be made per 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of 10 CFR 50.72 except when the actuation results from and is apart of a pre-planned sequence during testing or reactor operation.' 10 CFR 50.72(b)(3)(iv)(B)(6) is PWR auxiliary or emergency feedwater system.
"As described in EN# 42530, a manual reactor trip of the Kewaunee Power Station was initiated at 2043 on April 26, 2006. The manual reactor trip was initiated when the plant experienced a loss of both feedwater pumps. With a loss of both feedwater pumps and a manual reactor trip, the narrow range water level in both steam generators decreased to the actuation setpoint value for starting the Auxiliary Feedwater Pumps, causing all three Auxiliary Feedwater Pumps to start as designed. Because the steam generator water level was below the actuation setpoint, this was a valid actuation of the auxiliary feedwater system. As a valid actuation of the auxiliary feedwater system, this condition is reportable under 10 CFR 50.72(b)(3)(iv).
"The untimeliness of the report has been entered into the Kewaunee Power Station's corrective action program."
The licensee notified the NRC Resident Inspector. Notified R3DO (H. Peterson).
General Information or Other
Event Number: 42539
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: CAROLINA ENVIRONMENTAL, INC.
Region: 1
City: Cary State: NC
County:
License #: NC-06-15
Agreement: Y
Docket:
NRC Notified By: GRANT MILLS
HQ OPS Officer: PETE SNYDER
Licensee: CAROLINA ENVIRONMENTAL, INC.
Region: 1
City: Cary State: NC
County:
License #: NC-06-15
Agreement: Y
Docket:
NRC Notified By: GRANT MILLS
HQ OPS Officer: PETE SNYDER
Notification Date: 05/01/2006
Notification Time: 13:27 [ET]
Event Date: 04/26/2006
Event Time: 00:00 [EDT]
Last Update Date: 05/02/2006
Notification Time: 13:27 [ET]
Event Date: 04/26/2006
Event Time: 00:00 [EDT]
Last Update Date: 05/02/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD BELLAMY (R1)
GREG MORELL (NMSS)
ILTAB (E-Mail)
RONALD BELLAMY (R1)
GREG MORELL (NMSS)
ILTAB (E-Mail)
AGREEMENT STATE REPORT - STOLEN SPECTRUM ANALYZER
"N.C. Radiation Protection Section was notified on 01 May 2006 by the RSO for Carolina Environmental, Inc. of the theft of a Niton Model XLP 303-A portable Spectrum Analyzer (Serial No. 7225). The gauge contained one sealed source: (1) Cd-109, 40 millicuries, source. The device was stolen from vehicle between 04-26-06 and 04-29-06 (exact date and time unknown). The device was stored in a grey plastic pelican style medium sized suitcase Exterior labeling and security on the case is unknown at this time. The vehicle had been in the Boston, [Massachusetts] area during this time frame.
"The NC Radiation Protection Section is investigating compliance issues related to the NC licensee.
"N.C. Radiation Protection Section is notifying the regional FBI, the N.C Highway Patrol, the State Bureau of Investigation, Nuclear Regulatory Operations Center, Massachusetts Radiation Control Program, local Massachusetts law enforcement are being informed by the victim of theft."
* * * UPDATE FROM L. COX TO P. SNYDER AT 1315 ON 5/2/06 * * *
The spectrum analyzer reported as stolen yesterday in Boston, Massachusetts as part of a reciprocity agreement was reported found today. The licensee said that the source was removed from the vehicle by a family member and stored without the custodian's knowledge. The licensee identified this on 5/2/06 and will contact local law enforcement and the state of Massachusetts about the recovery of the anayzer as well. The state of North Carolina will continue to follow this event and report additional information as it becomes available.
Notified R1DO (R. Bellamy) and NMSS (G. Morell).
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.
"N.C. Radiation Protection Section was notified on 01 May 2006 by the RSO for Carolina Environmental, Inc. of the theft of a Niton Model XLP 303-A portable Spectrum Analyzer (Serial No. 7225). The gauge contained one sealed source: (1) Cd-109, 40 millicuries, source. The device was stolen from vehicle between 04-26-06 and 04-29-06 (exact date and time unknown). The device was stored in a grey plastic pelican style medium sized suitcase Exterior labeling and security on the case is unknown at this time. The vehicle had been in the Boston, [Massachusetts] area during this time frame.
"The NC Radiation Protection Section is investigating compliance issues related to the NC licensee.
"N.C. Radiation Protection Section is notifying the regional FBI, the N.C Highway Patrol, the State Bureau of Investigation, Nuclear Regulatory Operations Center, Massachusetts Radiation Control Program, local Massachusetts law enforcement are being informed by the victim of theft."
* * * UPDATE FROM L. COX TO P. SNYDER AT 1315 ON 5/2/06 * * *
The spectrum analyzer reported as stolen yesterday in Boston, Massachusetts as part of a reciprocity agreement was reported found today. The licensee said that the source was removed from the vehicle by a family member and stored without the custodian's knowledge. The licensee identified this on 5/2/06 and will contact local law enforcement and the state of Massachusetts about the recovery of the anayzer as well. The state of North Carolina will continue to follow this event and report additional information as it becomes available.
Notified R1DO (R. Bellamy) and NMSS (G. Morell).
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.
General Information or Other
Event Number: 42546
Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: CONTOUR ENGINEERING
Region: 1
City: PLANT BOWEN State: GA
County: BARTOW
License #: GA 1398-1
Agreement: Y
Docket:
NRC Notified By: LIZ SEALE
HQ OPS Officer: PETE SNYDER
Licensee: CONTOUR ENGINEERING
Region: 1
City: PLANT BOWEN State: GA
County: BARTOW
License #: GA 1398-1
Agreement: Y
Docket:
NRC Notified By: LIZ SEALE
HQ OPS Officer: PETE SNYDER
Notification Date: 05/02/2006
Notification Time: 16:22 [ET]
Event Date: 04/26/2006
Event Time: 16:00 [EDT]
Last Update Date: 05/02/2006
Notification Time: 16:22 [ET]
Event Date: 04/26/2006
Event Time: 16:00 [EDT]
Last Update Date: 05/02/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD BELLAMY (R1)
C.W. (BILL) REAMER (NMSS)
RONALD BELLAMY (R1)
C.W. (BILL) REAMER (NMSS)
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following information was provided by the state via facsimile:
"Description of event: At [approximately] 1600 hours, a portable moisture density gauge and its user were hit by heavy equipment. The gauge was run over, flattening the gauge. The user was injured and was taken for medical treatment. At the time of the notification, the RSO was enroute to evaluate the condition of the gauge. RCP advised the caller to contact [phone number deleted] if the RSO determines the source to be leaking, or if a response team is needed. Additionally, RCP advised the licensee to provide an update upon determination of gauge condition, as well as specific [information]. [The] gauge was a Troxler moisture density gauge Model 3430, Serial #32478.
"Isotope: Am-241 (44 millicuries) and Cs-137 (9 millicuries).
"[On] May 1, 2006 [RCP was] notified by [the] RSO that the source was stuck in the out position and it is being stored at their facility shielded by concrete test cylinders. Troxler has been notified and is sending a container to ship the gauge back in. A leak test has been performed. [The licensee] will send [the state] a summary of the event and information on the gauge."
Georgia Department of Natural Resources Report ID No. GA-2006-10.
The following information was provided by the state via facsimile:
"Description of event: At [approximately] 1600 hours, a portable moisture density gauge and its user were hit by heavy equipment. The gauge was run over, flattening the gauge. The user was injured and was taken for medical treatment. At the time of the notification, the RSO was enroute to evaluate the condition of the gauge. RCP advised the caller to contact [phone number deleted] if the RSO determines the source to be leaking, or if a response team is needed. Additionally, RCP advised the licensee to provide an update upon determination of gauge condition, as well as specific [information]. [The] gauge was a Troxler moisture density gauge Model 3430, Serial #32478.
"Isotope: Am-241 (44 millicuries) and Cs-137 (9 millicuries).
"[On] May 1, 2006 [RCP was] notified by [the] RSO that the source was stuck in the out position and it is being stored at their facility shielded by concrete test cylinders. Troxler has been notified and is sending a container to ship the gauge back in. A leak test has been performed. [The licensee] will send [the state] a summary of the event and information on the gauge."
Georgia Department of Natural Resources Report ID No. GA-2006-10.