| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/14/2014 - 08/15/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50349 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: NIAGARA BOTTLING, LLC
Region: 1
City: ALLENTOWN State: PA
County:
License #: PA-G0243
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/07/2014
Notification Time: 11:35 [ET]
Event Date: 08/06/2014
Event Time: [EDT]
Last Update Date: 08/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENTS RESOURCE (EMAI)
DAVEY TOTTERER (ILTA)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST RADIOACTIVE GAUGE
The following information was obtained from the Commonwealth of Pennsylvania via email:
"Event Description: On July 18, 2014 the Department [PA Department of Environmental Protection] performed a routine license inspection and discovered that a gauge was unaccounted for. The licensee believed the gauge was transferred to their Philadelphia plant and began to check records to try and verify its location. On August 6, 2014 the licensee reported to the Department that the gauge could not be located and is considered missing.
"Gauge Information:
Model: Filtec FT-50B
Serial Number: 2398
Isotope: Am-241
Activity: 100 mCi
"Cause of the Event: Human error. No records were kept as required regarding the gauge.
"Actions: The Department plans to issue a Notice of Violation and also provide assistance in locating the gauge."
Pennsylvania Event Report ID No.: PA140019
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Power Reactor | Event Number: 50363 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: ALAN TUBMAN
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/14/2014
Notification Time: 01:16 [ET]
Event Date: 08/13/2014
Event Time: 23:18 [EDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
SILAS KENNEDY (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 | Event Text MOMENTARY LOSS OF SECONDARY CONTAINMENT
"Nine Mile Point Unit 1 (NMP1) had a momentary loss of Secondary Containment due to both Reactor Building Airlock doors being opened at the same time.
"At 2318 [EDT] on 8/13/2014, both Reactor Building Airlock doors at NMP1 were open simultaneously for less than 5 seconds. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored.
"Secondary Containment being inoperable is an 8 hour notification per 10 CFR 50.72(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.'
"The condition has been entered into the station's corrective action program and the NRC Senior Resident Inspector was notified." |
| Power Reactor | Event Number: 50364 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAMON HESSIG
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/14/2014
Notification Time: 08:58 [ET]
Event Date: 08/14/2014
Event Time: 07:55 [CDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHRISTINE LIPA (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 89 | Power Operation | 89 | Power Operation | Event Text SERVICE WATER RADIATION MONITOR NONFUNCTIONAL FOR PLANNED MAINTENANCE
"The service water radiation monitor system will be rendered nonfunctional during planned preventive maintenance. As a result, this represents a loss of emergency assessment capability and is reportable per 10CFR50.72(b)(3)(xiii). The planned maintenance is expected to last 4 hours. During this time, plant parameters will be monitored and sampling will be performed which will support sustaining the health and safety of the public during this planned maintenance activity.
"The NRC Resident Inspector will be notified prior to removing the service water radiation monitor from service." |
| Power Reactor | Event Number: 50370 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEREMY COBBS
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/15/2014
Notification Time: 01:19 [ET]
Event Date: 08/14/2014
Event Time: 16:31 [PDT]
Last Update Date: 08/15/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
JACK WHITTEN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 63 | Power Operation | Event Text UNIT 2 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO MULTIPLE INOPERABLE EMERGENCY DIESEL GENERATORS
"While performing scheduled maintenance on Unit 2 Emergency Diesel Generator (EDG) 2-2, Diablo Canyon Power Plant (DCPP) identified a failed capscrew on engine cylinder 1L. As part of subsequent inspections to determine whether a similar condition existed on any of the other Unit 1 or Unit 2 EDGs, a degraded capscrew was identified on EDG 2-3 cylinder 8L at 1631 PDT on 08/14/2014. No capscrew issues were identified on the Unit 1 EDGs or on Unit 2 EDG 2-1. Although all operational tests of the diesels up to the time of discovery were satisfactorily performed with no indication of degraded performance, the EDG 2-3 was declared inoperable.
"Because two Unit 2 EDGs were inoperable concurrently, this is being reported as a condition that could have prevented fulfillment of a safety function per 10 CFR 50.72(b)(3)(v). Per the requirements of TS 3.8.1, with two EDGs inoperable, a plant shutdown was commenced at 2031 PDT on 08/14/2014. Therefore, this condition is also being reported in accordance with 10 CFR 50.72(b)(2)(i).
"Offsite power remained available throughout this condition. EDG 2-2 remains out of service as part of its scheduled maintenance window.
"This condition did not result in any adverse impact on the health and safety of the public.
"A press release is planned.
"The licensee informed the NRC Resident Inspector."
The licensee also reported event notifications for 10 CFR 50.72(b)(3)(v)(C) - Control of Rad Release and 10 CFR 50.72(b)(3)(v)(D) - Accident Mitigation.
The licensee plans to continue the shutdown to Mode 3 and is developing plans to return one of the two inoperable EDGs to operable status by the time the unit reaches Mode 5. | |