Event Notification Report for January 07, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/06/2001 - 01/07/2001
Power Reactor
Event Number: 37654
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREGORY CIRAULA
HQ OPS Officer: BOB STRANSKY
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREGORY CIRAULA
HQ OPS Officer: BOB STRANSKY
Notification Date: 01/08/2001
Notification Time: 13:54 [ET]
Event Date: 01/07/2001
Event Time: 09:30 [EST]
Last Update Date: 01/08/2001
Notification Time: 13:54 [ET]
Event Date: 01/07/2001
Event Time: 09:30 [EST]
Last Update Date: 01/08/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
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 | Y | 100 | Power Operation | 100 | Power Operation |
CLOSED FIRE DAMPERS WOULD RESULT IN BYPASS OF HEPA FILTERS
"On January 6, 2001, during testing of the auxiliary building ventilation system, it was noted that the flow through the HEPA-charcoal train did not meet the Technical Specification acceptance criterion. Upon further investigation by plant personnel on January 7, 2001 at 0930 it was discovered that fire damper ABF13 had closed. Closure of this damper resulted in the closure of damper ABS8 (an excess flow damper). On January 8, 2001, at 1030 following further engineering evaluation, it was determined that with these dampers closed, filtration of the effluents from the pipe chase and RHR areas would not have been processed through the HEPA-charcoal absorber. This condition does not meet the assumptions of the Salem offsite dose analysis, and therefore the condition meets the reporting requirements of 10 CFR 50.72(b)(2)(iii). As of January 7, 2001 at 1605 dampers ABF13 and ABS8 were open and flow through the HEPA-charcoal train was verified to meet Technical Specification acceptance criterion."
The NRC resident inspector will be informed of this report by the licensee.
"On January 6, 2001, during testing of the auxiliary building ventilation system, it was noted that the flow through the HEPA-charcoal train did not meet the Technical Specification acceptance criterion. Upon further investigation by plant personnel on January 7, 2001 at 0930 it was discovered that fire damper ABF13 had closed. Closure of this damper resulted in the closure of damper ABS8 (an excess flow damper). On January 8, 2001, at 1030 following further engineering evaluation, it was determined that with these dampers closed, filtration of the effluents from the pipe chase and RHR areas would not have been processed through the HEPA-charcoal absorber. This condition does not meet the assumptions of the Salem offsite dose analysis, and therefore the condition meets the reporting requirements of 10 CFR 50.72(b)(2)(iii). As of January 7, 2001 at 1605 dampers ABF13 and ABS8 were open and flow through the HEPA-charcoal train was verified to meet Technical Specification acceptance criterion."
The NRC resident inspector will be informed of this report by the licensee.
Power Reactor
Event Number: 37652
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ROBERT SMITH
HQ OPS Officer: FANGIE JONES
Region: 1 State: CT
Unit: [] [2] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ROBERT SMITH
HQ OPS Officer: FANGIE JONES
Notification Date: 01/07/2001
Notification Time: 09:50 [ET]
Event Date: 01/07/2001
Event Time: 06:00 [EST]
Last Update Date: 01/07/2001
Notification Time: 09:50 [ET]
Event Date: 01/07/2001
Event Time: 06:00 [EST]
Last Update Date: 01/07/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
JAMES NOGGLE (R1)
JAMES NOGGLE (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 |
| 3 | N | Y | 90 | Power Operation | 90 | Power Operation |
SECURITY REPORT
Safeguard system degradation related to area boundary. Immediate compensatory measures taken upon discovery. The licensee notified the NRC Resident Inspector.
Refer to HOO Log for additional details.
Safeguard system degradation related to area boundary. Immediate compensatory measures taken upon discovery. The licensee notified the NRC Resident Inspector.
Refer to HOO Log for additional details.