Event Notification Report for November 16, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/15/2001 - 11/16/2001
Power Reactor
Event Number: 38506
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BOB SCARBOROUGH
HQ OPS Officer: LEIGH TROCINE
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BOB SCARBOROUGH
HQ OPS Officer: LEIGH TROCINE
Notification Date: 11/16/2001
Notification Time: 12:09 [ET]
Event Date: 11/16/2001
Event Time: 10:15 [CST]
Last Update Date: 11/16/2001
Notification Time: 12:09 [ET]
Event Date: 11/16/2001
Event Time: 10:15 [CST]
Last Update Date: 11/16/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
CHARLES MARSCHALL (R4)
CHARLES MARSCHALL (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
DISCOVERY OF A COMPROMISE OF SAFEGUARDS INFORMATION
The licensee reported the discovery of a compromise of safeguards information in accordance with 10CFR73.71(b)(1). Immediate compensatory measures were taken upon discovery. (Contact the NRC operations officer for additional details).
The licensee plans to notify the NRC resident inspector.
The licensee reported the discovery of a compromise of safeguards information in accordance with 10CFR73.71(b)(1). Immediate compensatory measures were taken upon discovery. (Contact the NRC operations officer for additional details).
The licensee plans to notify the NRC resident inspector.
General Information or Other
Event Number: 38507
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: NORTH CAROLINA STATE UNIVERSITY
Region: 2
City: RALEIGH State: NC
County:
License #: 092-0090-3
Agreement: Y
Docket:
NRC Notified By: GERALD SPEIGHT
HQ OPS Officer: BOB STRANSKY
Licensee: NORTH CAROLINA STATE UNIVERSITY
Region: 2
City: RALEIGH State: NC
County:
License #: 092-0090-3
Agreement: Y
Docket:
NRC Notified By: GERALD SPEIGHT
HQ OPS Officer: BOB STRANSKY
Notification Date: 11/16/2001
Notification Time: 12:31 [ET]
Event Date: 11/16/2001
Event Time: 11:30 [EST]
Last Update Date: 11/16/2001
Notification Time: 12:31 [ET]
Event Date: 11/16/2001
Event Time: 11:30 [EST]
Last Update Date: 11/16/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
R2 IRC TEAM MANAGER (R2)
DOUG BROADDUS (NMSS)
R2 IRC TEAM MANAGER (R2)
DOUG BROADDUS (NMSS)
AGREEMENT STATE REPORT
A vial containing approximately 6.64 mCi of S-35 was discovered to be missing from a laboratory refrigerator. The material had last been handled on 10/31/01 when a researcher removed 0.36 mCi of the material for an experiment. The university is currently investigating this issue.
A vial containing approximately 6.64 mCi of S-35 was discovered to be missing from a laboratory refrigerator. The material had last been handled on 10/31/01 when a researcher removed 0.36 mCi of the material for an experiment. The university is currently investigating this issue.
Power Reactor
Event Number: 38509
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: FERGUSON
HQ OPS Officer: LEIGH TROCINE
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: FERGUSON
HQ OPS Officer: LEIGH TROCINE
Notification Date: 11/16/2001
Notification Time: 17:53 [ET]
Event Date: 11/16/2001
Event Time: 12:30 [CST]
Last Update Date: 11/16/2001
Notification Time: 17:53 [ET]
Event Date: 11/16/2001
Event Time: 12:30 [CST]
Last Update Date: 11/16/2001
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):
CHARLES MARSCHALL (R4)
CHARLES MARSCHALL (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
DISCOVERY THAT CERTAIN SAFETY-RELATED COMPONENTS COULD BECOME SUBMERGED DURING A POTENTIAL FLOODING SCENARIO
The following text is a portion of a facsimile received from the licensee:
"The Wolf Creek Nuclear Operating Corporation (WCNOC) is reviewing calculations and assumptions regarding its flooding analysis. Internal room flooding calculation FL-04 for Auxiliary Building Rooms 1206 and 1207 is based on a maximum flood rate of 3500 gpm. Research into this maximum flood rate indicates the value was based upon the required flow rate to the Condensate Hotwell from the Condensate Storage Tank (CST). The non-safety related 10" pipe which is routed through rooms 1206 [and] 1207 provides water at a flow rate greater than 3500 gpm from the CST to the Condensate Hotwell. Engineering review found that the subject rooms (1206 [and] 1207 are connected) could flood given a Safe Shutdown Earthquake and a subsequent double guillotine break of the non-safety related 10" line within the room. Multiple trains of safety related equipment exist in this room, and are at an elevation such that these components could become submerged during the flooding. Subsequently, WCNOC is reporting this issue as an event or condition that could have prevented the fulfillment of the safety function of systems needed to mitigate the consequences of an accident."
"Upon discovery, WCNOC has throttled valve AP-V012 Condensate Storage Tank Outlet Isolation to one-third open, thereby eliminating the potential of flooding in excess of the capability of the floor drain system in the subject rooms given a Safe Shutdown Earthquake."
The licensee notified the NRC resident inspector.
The following text is a portion of a facsimile received from the licensee:
"The Wolf Creek Nuclear Operating Corporation (WCNOC) is reviewing calculations and assumptions regarding its flooding analysis. Internal room flooding calculation FL-04 for Auxiliary Building Rooms 1206 and 1207 is based on a maximum flood rate of 3500 gpm. Research into this maximum flood rate indicates the value was based upon the required flow rate to the Condensate Hotwell from the Condensate Storage Tank (CST). The non-safety related 10" pipe which is routed through rooms 1206 [and] 1207 provides water at a flow rate greater than 3500 gpm from the CST to the Condensate Hotwell. Engineering review found that the subject rooms (1206 [and] 1207 are connected) could flood given a Safe Shutdown Earthquake and a subsequent double guillotine break of the non-safety related 10" line within the room. Multiple trains of safety related equipment exist in this room, and are at an elevation such that these components could become submerged during the flooding. Subsequently, WCNOC is reporting this issue as an event or condition that could have prevented the fulfillment of the safety function of systems needed to mitigate the consequences of an accident."
"Upon discovery, WCNOC has throttled valve AP-V012 Condensate Storage Tank Outlet Isolation to one-third open, thereby eliminating the potential of flooding in excess of the capability of the floor drain system in the subject rooms given a Safe Shutdown Earthquake."
The licensee notified the NRC resident inspector.