| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/18/2007 - 10/19/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43724 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: ALLEGHENY RODNEY
Region: 1
City: NEW BEDFORD State: MA
County:
License #: G-0112
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: PETE SNYDER | Notification Date: 10/15/2007
Notification Time: 18:29 [ET]
Event Date: 10/15/2007
Event Time: 12:00 [EDT]
Last Update Date: 10/15/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RONALD BELLAMY (R1)
SCOTT FLANDERS (FSME)
| Event Text MASSACHUSETTS AGREEMENT STATE REPORT
The following agreement state report information was faxed to the NRC Operation Center.
"Description: Thickness gauge
"Investigation Pending: No
"Consultant Hired: Yes
"Corrective Action: Licensed Contractor fixed the gauge
"SUBJECT: A gauge on the Z-25 press is sometimes stuck closed. The equipment is out of use.
"Equipment problem : Shutter was not working properly. Equipment problem, capacitor fell off." |
| Power Reactor | Event Number: 43729 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: JOE O'HARA | Notification Date: 10/18/2007
Notification Time: 12:36 [ET]
Event Date: 09/15/2007
Event Time: [EDT]
Last Update Date: 10/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
RONALD BELLAMY (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 | Event Text INVALID PRIMARY CONTAINMENT ISOLATION
"This notification is being made in accordance with 10CFR50.73(a)(2)(iv)(A) to provide information pertaining to an invalid Primary Containment Isolation System (PCIS) Group 3 actuation signal that affected containment isolation valves in more than one system.
"On 09/15/07, with the reactor at 100% power, an invalid PCIS Group 3 actuation occurred from a momentary spike of the 'A' Refuel Floor radiation monitor which reached the instrument's high radiation trip setpoint. Radiation protection technicians dispatched to the refuel floor verified dose rates in the vicinity of the 'A' radiation monitors detector to be normal and below the alarm set points. The radiation monitor was verified to be indicating normally to expected radiation levels. Subsequent visual inspection and functional checks of the radiation monitor were completed satisfactory and the instrument channel was returned to service. The cause of the spurious spike is attributed to an unknown source of electrical noise.
"Both trains of the Standby Gas Treatment System started as designed and Reactor Building ventilation isolated. The train actuation was complete.
"The PCIS functioned successfully providing a complete Group 3 isolation. The PCIS Group 3 isolation involves the following systems and isolation valves:
Drywell and Suppression Chamber air purge and vent: V16-19-6, 6A, 6B, 7, 7A, 7B, 8, 9, 10, 23
Containment Makeup: V16-20-20, 22A, 22B
Containment Air Sampling: VG-23, 26, V109-76A, 76B
Containment Air compressor suction: V72-38A, 38B
Containment Air Dilution: VG-9A, 9B, 22A, 22B, NG-11A, 11B, 12A, 12B, 13A, 13B
"In accordance with 10CFR50.73(a)(i) a telephone notification is being made instead of submitting a written Licensee Event Report."
The licensee will notify the NRC Resident Inspector. | |