Event Notification Report for April 05, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/04/2014 - 04/05/2014
Power Reactor
Event Number: 50002
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: SUNYOUNG KWON
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: SUNYOUNG KWON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/05/2014
Notification Time: 18:16 [ET]
Event Date: 04/05/2014
Event Time: 10:25 [EDT]
Last Update Date: 04/05/2014
Notification Time: 18:16 [ET]
Event Date: 04/05/2014
Event Time: 10:25 [EDT]
Last Update Date: 04/05/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 46 | Power Operation |
LOSS OF ENCLOSURE BUILDING
In preparation for a scheduled outage, maintenance personnel removed the upper and lower boots of the main steam safety valves. Upon discovery, Operations personnel declared the Enclosure Building inoperable. Maintenance re-installed the boots and the integrity of the Enclosure Building was restored and the building returned to service.
The licensee notified the NRC Resident Inspector, the State of Connecticut, and the town of Waterford.
In preparation for a scheduled outage, maintenance personnel removed the upper and lower boots of the main steam safety valves. Upon discovery, Operations personnel declared the Enclosure Building inoperable. Maintenance re-installed the boots and the integrity of the Enclosure Building was restored and the building returned to service.
The licensee notified the NRC Resident Inspector, the State of Connecticut, and the town of Waterford.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State
Event Number: 50003
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: THERMO EGS GAUGING, INC.
Region: 1
City: WILMINGTON State: MA
County:
License #: 20-6751
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: STEVE SANDIN
Licensee: THERMO EGS GAUGING, INC.
Region: 1
City: WILMINGTON State: MA
County:
License #: 20-6751
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/07/2014
Notification Time: 11:30 [ET]
Event Date: 04/05/2014
Event Time: 00:00 [EDT]
Last Update Date: 04/14/2014
Notification Time: 11:30 [ET]
Event Date: 04/05/2014
Event Time: 00:00 [EDT]
Last Update Date: 04/14/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (EMAI)
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - TWO SR-90 SEALED SOURCES FAILED PRE-SHIPMENT LEAK TEST
The following information was received from the Commonwealth of Massachusetts via email:
"On Saturday, 4/5/14, licensee left voice mail notification for this Agency (Massachusetts Radiation Control Program) of the same day determination of two potential leaking or contaminated sealed sources that had been taken out of long-term storage and intended to be shipped for eventual disposal. Notification received by Agency on Monday, 4/7/14. Follow-up contact with licensee by Agency on 4/7/14. The source was returned to storage pending licensee contact with manufacturer. Licensee reported leak lest results are preliminary in nature and were determined by licensee to be above background. There was no evidence of contamination beyond the source itself. Five-day written report from licensee to follow.
"Additional Reference: NMED Item Number TRA
"Manufacturer: Eckert & Ziegler / IPL
"Model #: SIF.D1
"Manufacture date: 3/2004 (0.100 Ci)
"Serial #: MI318 / MC915
"Isotope: Sr-90
"Isotope activity (Ci): 0.078 (4/2014)
"Leak test result (microCi): 0.002 (preliminary) / 0.0007 (preliminary)"
* * * RETRACTION FROM CARPENITO TO KLCO VIA FAX ON 4/14/2014 AT 1515 EDT * * *
"The Licensee's written report was received by the Agency on 4/10/14. The Licensee confirmed that leak test results were unchanged from the earlier report. With this new information, the Agency determined that this is not a reportable event because results were below the reportable level of 0.005 microcuries. The Agency considers this matter to be closed."
Notified the R1DO (Burritt) and FSME Events Resource via email.
The following information was received from the Commonwealth of Massachusetts via email:
"On Saturday, 4/5/14, licensee left voice mail notification for this Agency (Massachusetts Radiation Control Program) of the same day determination of two potential leaking or contaminated sealed sources that had been taken out of long-term storage and intended to be shipped for eventual disposal. Notification received by Agency on Monday, 4/7/14. Follow-up contact with licensee by Agency on 4/7/14. The source was returned to storage pending licensee contact with manufacturer. Licensee reported leak lest results are preliminary in nature and were determined by licensee to be above background. There was no evidence of contamination beyond the source itself. Five-day written report from licensee to follow.
"Additional Reference: NMED Item Number TRA
"Manufacturer: Eckert & Ziegler / IPL
"Model #: SIF.D1
"Manufacture date: 3/2004 (0.100 Ci)
"Serial #: MI318 / MC915
"Isotope: Sr-90
"Isotope activity (Ci): 0.078 (4/2014)
"Leak test result (microCi): 0.002 (preliminary) / 0.0007 (preliminary)"
* * * RETRACTION FROM CARPENITO TO KLCO VIA FAX ON 4/14/2014 AT 1515 EDT * * *
"The Licensee's written report was received by the Agency on 4/10/14. The Licensee confirmed that leak test results were unchanged from the earlier report. With this new information, the Agency determined that this is not a reportable event because results were below the reportable level of 0.005 microcuries. The Agency considers this matter to be closed."
Notified the R1DO (Burritt) and FSME Events Resource via email.
Power Reactor
Event Number: 50164
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BENJAMIN EGNEW
HQ OPS Officer: DANIEL MILLS
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BENJAMIN EGNEW
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/03/2014
Notification Time: 06:42 [ET]
Event Date: 04/05/2014
Event Time: 07:00 [EDT]
Last Update Date: 06/03/2014
Notification Time: 06:42 [ET]
Event Date: 04/05/2014
Event Time: 07:00 [EDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
PAUL KROHN (R1DO)
PAUL KROHN (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION
"This notification is being made in accordance with 10 CFR 50.73 (a)(2)(iv)(A) to provide information pertaining to an invalid Primary Containment Isolation System (PCIS) Group 3 actuation signal that affected containment valves in more than one system.
"On April 5, 2014, 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 set point. A radiation protection technician was dispatched to the refuel floor and dose rates in the vicinity of the 'A' radiation monitor detector were verified to be normal and below the alarm set points. The radiation monitor was verified to be indicating normal expected radiation levels. The detector was replaced, a functional check and calibration of the radiation monitor was completed satisfactory and the instrument channel was returned to service. The issue has been entered into the station's corrective action program.
"Both trains of Standby Gas Treatment System started as designed and Reactor Building ventilation isolated as a result of the invalid PCIS actuation.
"The PCIS functioned successfully, providing a complete Group 3 isolation. PCIS Group 3 involves the following system isolation valves:
"Drywell and Suppression Chamber Air and Vent: V16-19-6, 6A, 6B, 7, 7A, 7B, 8, 9, 10, 23
"Containment Makeup: V-16-20-20, 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
"Since no actual high radiation condition existed which required the PCIS Group 3 isolation, and the actuation was not in response to actual plant conditions satisfying the requirements for isolation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public.
"In accordance with 10 CFR 50.73(a)(1) a telephone notification is being made instead of submitting a written Licensee Event Report. The licensee has notified the NRC resident inspector."
"This notification is being made in accordance with 10 CFR 50.73 (a)(2)(iv)(A) to provide information pertaining to an invalid Primary Containment Isolation System (PCIS) Group 3 actuation signal that affected containment valves in more than one system.
"On April 5, 2014, 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 set point. A radiation protection technician was dispatched to the refuel floor and dose rates in the vicinity of the 'A' radiation monitor detector were verified to be normal and below the alarm set points. The radiation monitor was verified to be indicating normal expected radiation levels. The detector was replaced, a functional check and calibration of the radiation monitor was completed satisfactory and the instrument channel was returned to service. The issue has been entered into the station's corrective action program.
"Both trains of Standby Gas Treatment System started as designed and Reactor Building ventilation isolated as a result of the invalid PCIS actuation.
"The PCIS functioned successfully, providing a complete Group 3 isolation. PCIS Group 3 involves the following system isolation valves:
"Drywell and Suppression Chamber Air and Vent: V16-19-6, 6A, 6B, 7, 7A, 7B, 8, 9, 10, 23
"Containment Makeup: V-16-20-20, 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
"Since no actual high radiation condition existed which required the PCIS Group 3 isolation, and the actuation was not in response to actual plant conditions satisfying the requirements for isolation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public.
"In accordance with 10 CFR 50.73(a)(1) a telephone notification is being made instead of submitting a written Licensee Event Report. The licensee has notified the NRC resident inspector."