Event Notification Report for March 16, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/15/2002 - 03/16/2002
Power Reactor
Event Number: 38773
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ROBERT BOESCH
HQ OPS Officer: STEVE SANDIN
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ROBERT BOESCH
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/16/2002
Notification Time: 06:59 [ET]
Event Date: 03/16/2002
Event Time: 02:40 [EST]
Last Update Date: 03/16/2002
Notification Time: 06:59 [ET]
Event Date: 03/16/2002
Event Time: 02:40 [EST]
Last Update Date: 03/16/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID LEW (R1)
DAVID LEW (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNIT 2 ENTERED TS 3.0.3 AFTER DECLARING ESS BUSES INOPERABLE DUE TO ERROR IN CLEARANCE
"On 3/16/02 at 0240 hours, a field operator was directed to remove a clearance and rack in 4 Kv breakers for the Unit 1 A & B Control Rod Drive system. The system had been out of service for maintenance during the refuel outage. Upon arrival at the load center, the operator found both breakers racked out but not secured with the required seismic restraints. According to plant procedures, this renders the associated bus inoperable. Shift supervision was notified and the Unit 1 'A' and 'D' ESS Busses were declared inoperable. The immediate effects were for Unit 2 to enter TS 3.0.3 which was exited 30 minutes later, once the breakers were returned to their racked-in position. In review of the Loss of Safety Function, it was discovered that, with the 'A' and 'D' ESS Busses inoperable, the Control Structure chillers were inoperable resulting in an event or condition that could have prevented fulfillment of a Safety Function required to Mitigate the consequences of an accident. In accordance with 10CFR50.72(b)(3)(,v)(D) this loss of safety function requires an 8 hour ENS Notification."
The 4 Kv breakers were racked out 8 days ago. Due to an oversight in preparation of the clearance, the procedure requiring installation of the seismic restraints was not referenced. The licensee informed the NRC Resident Inspector.
"On 3/16/02 at 0240 hours, a field operator was directed to remove a clearance and rack in 4 Kv breakers for the Unit 1 A & B Control Rod Drive system. The system had been out of service for maintenance during the refuel outage. Upon arrival at the load center, the operator found both breakers racked out but not secured with the required seismic restraints. According to plant procedures, this renders the associated bus inoperable. Shift supervision was notified and the Unit 1 'A' and 'D' ESS Busses were declared inoperable. The immediate effects were for Unit 2 to enter TS 3.0.3 which was exited 30 minutes later, once the breakers were returned to their racked-in position. In review of the Loss of Safety Function, it was discovered that, with the 'A' and 'D' ESS Busses inoperable, the Control Structure chillers were inoperable resulting in an event or condition that could have prevented fulfillment of a Safety Function required to Mitigate the consequences of an accident. In accordance with 10CFR50.72(b)(3)(,v)(D) this loss of safety function requires an 8 hour ENS Notification."
The 4 Kv breakers were racked out 8 days ago. Due to an oversight in preparation of the clearance, the procedure requiring installation of the seismic restraints was not referenced. The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 38774
Facility: LASALLE
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: BOB STRANSKY
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: BOB STRANSKY
Notification Date: 03/16/2002
Notification Time: 13:55 [ET]
Event Date: 03/16/2002
Event Time: 12:15 [CST]
Last Update Date: 03/16/2002
Notification Time: 13:55 [ET]
Event Date: 03/16/2002
Event Time: 12:15 [CST]
Last Update Date: 03/16/2002
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):
MONTE PHILLIPS (R3)
MONTE PHILLIPS (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 |
PLANT SHUTDOWN IN ACCORDANCE WITH TECHNICAL SPECIFICATIONS
"This notification is being made pursuant to 10CFR50.72(b)(2)(i), and Exelon Reportability Manual section SAF 1.2. At 1215 CST on 03/16/02, during Unit 2 steady state operation at 100% power, a unit shutdown was initiated due to an increase in Reactor Coolant System Unidentified Leakage in excess of Technical Specification limits. RCS unidentified leakage has increased by 2.1 gallons per minute over a 24 hour period, from 0.9 gpm to 3.0 gpm, which is above the Tech Spec limit of less than or equal to 2 gpm. On 3/16/02 at 0555 CST, a 12 hour timeclock was entered to be in Hot Shutdown by 1755 CST, followed by Cold Shutdown on 3/17/02 at 1755 CST. Current plans are to enter Cold Shutdown in order to enter the Primary Containment, and determine and correct the cause of the unidentified leakage."
The NRC resident inspector has been informed of this event by the licensee.
* * * UPDATE 2214 EST 3/16/2002 FROM DANIEL COVEYOU TAKEN BY BOB STRANSKY * * *
"This notification provides an update of EN #38774 and is being made pursuant to 10CFR50.72(c)(2) and Exelon Reportability Manual section SAF 1.2.
"As of 1540 CST, the indicated increase in the Unit 2 unidentified leakage rate over the previous 24 hr period has decreased to 1.7 gpm. As this value meets the LCO requirements of LaSalle Technical Specification 3.4.5 (<2 gpm increase within previous 24 hours), the plant shutdown initiated at 1215 CST is no longer required.
"The increase (and subsequent decrease) in the indicated unidentified leakage rate is consistent with previously observed behaviors following primary containment cooling equipment lineup changes that induce containment air temperature changes. Initial chemistry analyses of the primary containment environment (air and sump samples) indicate that there has been no increase in reactor coolant system leakage.
"The shutdown was terminated with the reactor operating at 69% power. Current plans are to return the unit to full power operation."
The NRC resident inspector has been informed of this update by the licensee. Notified R3DO (Phillips).
"This notification is being made pursuant to 10CFR50.72(b)(2)(i), and Exelon Reportability Manual section SAF 1.2. At 1215 CST on 03/16/02, during Unit 2 steady state operation at 100% power, a unit shutdown was initiated due to an increase in Reactor Coolant System Unidentified Leakage in excess of Technical Specification limits. RCS unidentified leakage has increased by 2.1 gallons per minute over a 24 hour period, from 0.9 gpm to 3.0 gpm, which is above the Tech Spec limit of less than or equal to 2 gpm. On 3/16/02 at 0555 CST, a 12 hour timeclock was entered to be in Hot Shutdown by 1755 CST, followed by Cold Shutdown on 3/17/02 at 1755 CST. Current plans are to enter Cold Shutdown in order to enter the Primary Containment, and determine and correct the cause of the unidentified leakage."
The NRC resident inspector has been informed of this event by the licensee.
* * * UPDATE 2214 EST 3/16/2002 FROM DANIEL COVEYOU TAKEN BY BOB STRANSKY * * *
"This notification provides an update of EN #38774 and is being made pursuant to 10CFR50.72(c)(2) and Exelon Reportability Manual section SAF 1.2.
"As of 1540 CST, the indicated increase in the Unit 2 unidentified leakage rate over the previous 24 hr period has decreased to 1.7 gpm. As this value meets the LCO requirements of LaSalle Technical Specification 3.4.5 (<2 gpm increase within previous 24 hours), the plant shutdown initiated at 1215 CST is no longer required.
"The increase (and subsequent decrease) in the indicated unidentified leakage rate is consistent with previously observed behaviors following primary containment cooling equipment lineup changes that induce containment air temperature changes. Initial chemistry analyses of the primary containment environment (air and sump samples) indicate that there has been no increase in reactor coolant system leakage.
"The shutdown was terminated with the reactor operating at 69% power. Current plans are to return the unit to full power operation."
The NRC resident inspector has been informed of this update by the licensee. Notified R3DO (Phillips).
General Information or Other
Event Number: 38778
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: PROFESSIONAL SERVICES INDUSTRIES
Region: 1
City: COLUMBIA State: MD
County: HOWARD
License #: 12-16941-01
Agreement: Y
Docket:
NRC Notified By: RAY MANLEY
HQ OPS Officer: RICH LAURA
Licensee: PROFESSIONAL SERVICES INDUSTRIES
Region: 1
City: COLUMBIA State: MD
County: HOWARD
License #: 12-16941-01
Agreement: Y
Docket:
NRC Notified By: RAY MANLEY
HQ OPS Officer: RICH LAURA
Notification Date: 03/18/2002
Notification Time: 14:48 [ET]
Event Date: 03/16/2002
Event Time: 09:00 [EST]
Last Update Date: 03/18/2002
Notification Time: 14:48 [ET]
Event Date: 03/16/2002
Event Time: 09:00 [EST]
Last Update Date: 03/18/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICHARD CONTE (R1)
DOUG BROADDUS (NMSS)
RICHARD CONTE (R1)
DOUG BROADDUS (NMSS)
AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER MOISTURE DENSITY GAUGE
The Maryland Department of the Environment reported that over the weekend a moisture density gauge was stolen from a construction trailer in Howard County, Maryland. The model number of the gauge is 3430 with a serial number of 22798. The gauge uses 8 millicuries of Cs-137 and 40 millicuries of Am- 241. The theft was reported to the Howard County Police Department. The device is not a radiological hazard provided the source remains locked in its device. The gauge is owned and licensed to Professional Services Industries who is an NRC licensee doing work in Maryland under reciprocity. The state issued a press release.
The Maryland Department of the Environment reported that over the weekend a moisture density gauge was stolen from a construction trailer in Howard County, Maryland. The model number of the gauge is 3430 with a serial number of 22798. The gauge uses 8 millicuries of Cs-137 and 40 millicuries of Am- 241. The theft was reported to the Howard County Police Department. The device is not a radiological hazard provided the source remains locked in its device. The gauge is owned and licensed to Professional Services Industries who is an NRC licensee doing work in Maryland under reciprocity. The state issued a press release.