Event Notification Report for April 19, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/18/2016 - 04/19/2016
Power Reactor
Event Number: 51871
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DANIELS
HQ OPS Officer: JEFF HERRERA
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DANIELS
HQ OPS Officer: JEFF HERRERA
Notification Date: 04/19/2016
Notification Time: 19:54 [ET]
Event Date: 04/19/2016
Event Time: 13:43 [CDT]
Last Update Date: 04/19/2016
Notification Time: 19:54 [ET]
Event Date: 04/19/2016
Event Time: 13:43 [CDT]
Last Update Date: 04/19/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HEATHER GEPFORD (R4DO)
HEATHER GEPFORD (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
MAIN STEAM LINE RADIATION DETECTOR DETERMINED TO BE NON FUNCTIONAL
"While performing a monthly check source on radiation monitor 1-RE-2328 (Main Steamline 1-04 Radiation Detector), the monitor was determined to be non-functional. With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 1-04 could neither be evaluated nor monitored. This unplanned condition is reportable as a major loss of assessment capability per 10 CFR 50.72(b)(3)(xiii).
"Comanche Peak Nuclear Power Plant [CPNPP] has assurance of steam generator integrity and fuel cladding integrity and there is a negligible safety significance to the current condition from a public health and safety perspective.
"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding.
"Until this radiation monitor can be restored, Operations has implemented compensatory measures to monitor main steamline 1-04 N16 Radiation Monitor for early signs of a steam generator tube leak/rupture, pre-brief radiation protection technicians on taking local readings with a geiger-mueller tube on main steam line 1-04 and reporting the reading to the Control Room.
"Corrective actions are being pursued to restore 1-RE-2328 to functional status."
The NRC Resident Inspector has been notified.
"While performing a monthly check source on radiation monitor 1-RE-2328 (Main Steamline 1-04 Radiation Detector), the monitor was determined to be non-functional. With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 1-04 could neither be evaluated nor monitored. This unplanned condition is reportable as a major loss of assessment capability per 10 CFR 50.72(b)(3)(xiii).
"Comanche Peak Nuclear Power Plant [CPNPP] has assurance of steam generator integrity and fuel cladding integrity and there is a negligible safety significance to the current condition from a public health and safety perspective.
"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding.
"Until this radiation monitor can be restored, Operations has implemented compensatory measures to monitor main steamline 1-04 N16 Radiation Monitor for early signs of a steam generator tube leak/rupture, pre-brief radiation protection technicians on taking local readings with a geiger-mueller tube on main steam line 1-04 and reporting the reading to the Control Room.
"Corrective actions are being pursued to restore 1-RE-2328 to functional status."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 51872
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: VINCE KLCO
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: VINCE KLCO
Notification Date: 04/20/2016
Notification Time: 01:52 [ET]
Event Date: 04/19/2016
Event Time: 21:59 [EDT]
Last Update Date: 04/20/2016
Notification Time: 01:52 [ET]
Event Date: 04/19/2016
Event Time: 21:59 [EDT]
Last Update Date: 04/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
INOPERABLE SECONDARY CONTAINMENT
"On April 19th, 2016 at 2159 [EDT], Secondary Containment became inoperable due to failure to meet Surveillance Requirement (SR 3.6.4.1.1) on Unit 1 and Unit 2.
"The inoperability was caused when Reactor Building differential pressure was discovered to be less than Technical Specification requirements [-0.25 inches of water gauge].
"Secondary Containment was restored April 19, 2016 at 2222 by adjusting intake louvers in accordance with off normal operating procedure ON-RBHVAC-201.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."
The licensee notified the NRC Resident Inspector.
"On April 19th, 2016 at 2159 [EDT], Secondary Containment became inoperable due to failure to meet Surveillance Requirement (SR 3.6.4.1.1) on Unit 1 and Unit 2.
"The inoperability was caused when Reactor Building differential pressure was discovered to be less than Technical Specification requirements [-0.25 inches of water gauge].
"Secondary Containment was restored April 19, 2016 at 2222 by adjusting intake louvers in accordance with off normal operating procedure ON-RBHVAC-201.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."
The licensee notified the NRC Resident Inspector.