| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/08/2013 - 02/11/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48710 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: GENERAL CHEMICAL CORPORATION
Region: 1
City: FRAMINGHAM State: MA
County:
License #: G0038
Agreement: Y
Docket:
NRC Notified By: ANTHONY CARPENITO
HQ OPS Officer: DONALD NORWOOD | Notification Date: 01/31/2013
Notification Time: 15:25 [ET]
Event Date: 09/10/2012
Event Time: [EST]
Last Update Date: 01/31/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RONALD BELLAMY (R1DO)
FSME EVENTS RESOURCE (EMAI)
DARYL JOHNSON (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - GENERAL LICENSE DEVICE CONTAINING RADIOACTIVE MATERIAL MISSING
The following information was received from the Massachusetts Radiation Control Program via email:
"General licensee requested termination of GL registration G0038 on 9/13/12 noting that the registered material (two electron capture detectors [ECD]) had been shipped to another organization. Upon Agency [MA Radiation Control Program] inquiry, the receiving organization confirmed receiving only one ECD. The shipper stated the missing ECD had been physically removed from its original gas chromatograph several years earlier and was last known to be in a small cardboard box that was assumed to have been segregated during a lab cleanup and subsequently included in an overall lab equipment transfer to the receiving organization. Upon further investigation and review, the shipping organization stated on 12/20/12 that the ECD may have been inadvertently dispositioned during the lab cleanup. The ECD is a small metallic cylindrical object approximately less than one inch in diameter and four inches in length.
"The Agency considers this event to be closed."
The electron capture detector is a Hewlett Packard Model G1223A (Serial Number K0118). The source contained less than 15 mCi Ni-63.
MA Event #: 130131.
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: 48733 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MIKE FULLER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/08/2013
Notification Time: 11:50 [ET]
Event Date: 02/08/2013
Event Time: 09:45 [CST]
Last Update Date: 02/08/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DON ALLEN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | Cold Shutdown | 0 | Cold Shutdown | Event Text MINOR HYDRAULIC OIL SPILL ONSITE
"A hydraulic oil line break occurred on a crane inside of the protected area. The break resulted in a 2-gallon spill of hydraulic oil.
"Wolf Creek has notified the National Response Center and Kansas Department of Health and Environment. The oil spill is being cleaned up by our environmental group."
The licensee has notified the NRC Resident Inspector. |
| Part 21 | Event Number: 48735 | Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE PORTER
HQ OPS Officer: PETE SNYDER | Notification Date: 02/08/2013
Notification Time: 16:32 [ET]
Event Date: 02/08/2013
Event Time: [EST]
Last Update Date: 02/08/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
RAY POWELL (R1DO)
GEORGE HOPPER (R2DO)
MICHAEL KUNOWSKI (R3DO)
DON ALLEN (R4DO)
PART 21 REACTORS (EMAI)
| Event Text PART 21 - COMPLETED EVALUATION FOR POTENTIAL ERROR IN MAIN STEAM LINE HIGH FLOW CALCULATIONAL METHODOLOGY
"GEH recently discovered that some calculations of the choked flow rate in the Main Steam Lines (MSLs) of GEH BWRs were non-conservative, with potential effects on margins between choked flow conditions and existing MSL high-flow Nominal Trip Setpoints (NTSPs), Allowable Values (AVs), and Analytical Limits (ALs).
"GEH has now completed the evaluation of this condition and has determined this condition is not reportable under 10 CFR 21 for all U.S. BWR/2-6 plants. The effect of the discovered non-conservatisms in choked flow rate values was offset by unintended conservatisms in the GEH recommended formulation for calculating pressure drop across the MSL flow restrictor. As a result, GEH has determined that the flow-instrument pressure remain at conservative values (which would ensure that the associated NTSPs and AVs expressed in psid also remain at conservative values), and the MSL high-flow trip will function as designed. This update to the 60-day Interim Notification issued on December 12, 2012 (MFN 12-111 R1) will be sent to all US BWR/2-6 plants licensed using the GEH design basis and safety analysis."
See previous NRC Event Report 48350. |
| Power Reactor | Event Number: 48736 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MATTHEW GALLERANI
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/08/2013
Notification Time: 22:50 [ET]
Event Date: 02/08/2013
Event Time: 22:00 [EST]
Last Update Date: 02/10/2013 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
RAY POWELL (R1DO)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
ERIC LEEDS (NRR)
DAVE LEW (R1)
BILL DEAN (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 80 | Power Operation | 0 | Hot Shutdown | Event Text UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER
"Pilgrim Station scrammed on a loss of offsite power. All systems performed as designed. Groups I, II, VI went to completion. Reactor Core Isolation Cooling (RCIC) is injecting to the vessel controlling level. High Pressure Coolant Injection is in pressure control and slowly cooling down. Offsite power was lost multiple times. The Startup Transformer has been declared inoperable. The Unusual Event was declared under EAL SU 1.1 based on loss of offsite power greater than 15 minutes [at 2200 EST]."
The licensee originally experienced an automatic reactor scram at 2117 EST due to a load reject with a turbine trip/reactor scram due to loss of power. Offsite power availability has been fluctuating in and out to the site. The licensee states that all systems are functioning as required. All rods fully inserted and the reactor is stable in Mode 3. Both Emergency Diesel Generators are providing power to the safety related buses. The loss of offsite power is believed to be weather related.
The licensee has notified the State and local authorities and the NRC Resident Inspector.
Notified DHS SWO, FEMA, USDA, HHS, DOE, DHS NICC, EPA, and NuclearSSA via email.
* * * UPDATE FROM PAUL GALLANT TO VINCE KLCO AT 2/10/13 AT 1108 EST* * *
Pilgrim terminated the Unusual Event and has transitioned to recovery effective at 10:55 AM on 02/10/2013. Offsite power has been restored to safety-related and non-safety-related electrical buses through the station Startup Transformer via a single 345 KV line. The other two offsite power sources remain out of service. The emergency diesel generators have been secured and are in standby. Residual heat removal is in shutdown cooling mode maintaining the reactor in cold shutdown. Fuel Pool Cooling is in service with fuel pool coolant temperatures trending down.
The licensee notified State, local authorities and the NRC Resident Inspector. Notified R1 RA (Dean), R1DO (Powell), NRR DIR(Leeds) NRR EO (Evans) and NSIR IRD (Marshall).
Notified DHS SWO, FEMA, USDA, HHS, DOE, DHS NICC, EPA, and NuclearSSA via email. |
| Power Reactor | Event Number: 48738 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNETH HUNTER
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 02/10/2013
Notification Time: 09:11 [ET]
Event Date: 02/10/2013
Event Time: 07:00 [EST]
Last Update Date: 02/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
GEORGE HOPPER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 47 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM INSERTED DUE TO DEGRADING REACTOR WATER CHEMISTRY
"During normal power operations, the crew observed condensate/feedwater conductivity begin to increase at approximately 0530 EST on 02/10/13. The crew responded to the associated alarm response procedures and entered abnormal operating procedure 34AB-N61-001-1 due to degrading reactor water chemistry parameters. A power reduction [from 100%] was initiated at 0555 EST in accordance with station procedures for responding to a suspected condenser tube leak. At 0700 EST, a manual reactor SCRAM [from approximately 47%] was inserted due to the elevated reactor water conductivity in accordance with station abnormal operating procedures. All rods inserted completely and no complications were encountered following the reactor SCRAM, normal feedwater injection remained available. Following the SCRAM, a Group 2 Primary Containment Isolation Signal (PCIS} was received as a result of reactor water level lowering below +3 inches. The lowest reactor water level observed was [minus] 2 inches and was restored to normal operating levels utilizing normal feedwater injection. Following restoration of reactor water level to the normal operating level, the Group 2 PCIS signal was reset. No ECCS injection systems actuated as a result of the reactor SCRAM."
The SCRAM was uncomplicated and the plant is stable. Decay heat removal is to the main condenser via the turbine bypass valves. The plant is in a normal offsite electrical power shutdown alignment. Efforts are in progress to isolate the condenser in-leakage. There was no impact on Unit 2.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48739 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RICHARD PROBASCO
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/10/2013
Notification Time: 20:20 [ET]
Event Date: 02/10/2013
Event Time: 14:05 [EST]
Last Update Date: 02/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
RAY POWELL (R1DO)
RON BELLAMY (R1)
MICHELE EVANS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS OF OFFSITE POWER AND SUBSEQUENT PRESS RELEASE
"On Sunday, February 10, 2013 at 1405 [EST], with the reactor at 0% core thermal power, all control rods fully inserted, and in cold shutdown conditions, the plant experienced a loss of off-site power. With Pilgrim Station aligned to off-site power via the start-up transformer (SUT), a fault on the 'B' phase of the SUT was experienced due to suspected falling ice striking the phase's insulator. This resulted in the tripping of the feeder breaker, ACB-102, and the loss of power to 4160 KV buses A1 through A4. Emergency Diesel Generators (EDGs) 'A' and 'B' auto-started as designed and are powering emergency buses.
"The loss of off-site power resulted in de-energization of both Reactor Protection System (RPS) channels resulting in a reactor scram signal and isolation of shutdown cooling. At 1418, shutdown cooling was returned to service. All other plant systems responded as designed. Station personnel are in the process of establishing back-up power in accordance with plant procedures.
"The following press release was made at 1715 hours: 'Offsite power to Pilgrim station was interrupted this afternoon. The plant is in a cold shutdown condition and Pilgrim's diesel generators are providing power to the site. There is no worker or public safety concern. Plant personnel are troubleshooting the cause of the interruption.'
"This event had no impact on the health and/or safety of the public.
"The NRC Senior Resident Inspector has been notified." | |