| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/19/2014 - 11/20/2014 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41128 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: AMY HAZELHOFF
HQ OPS Officer: BILL GOTT | Notification Date: 10/17/2004
Notification Time: 01:03 [ET]
Event Date: 10/16/2004
Event Time: 17:30 [EDT]
Last Update Date: 11/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
ROGER LANKSBURY (R3)
BILL BATEMAN (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text REACTOR VESSEL HEAD NOZZLE CRACKING
"On 10/16/04, with the Plant in Mode 6, Nuclear Management Company identified through wall cracks in the inconel buttering adjacent to the J-weld on reactor head penetrations 29 and 30. Ultrasonic examinations of the reactor vessel head were being performed in accordance with the First Revised Order, EA-03-009. The ultrasonic examinations identified leak path detection indications. Therefore, in accordance with the Order, a bare metal visual inspection of the exterior of the reactor head was performed. No evidence of leakage was discovered. A dye-penetrant examination was then performed. The dye-penetrant exam showed minor surface indications that required further examination. Following minor excavation of the weld surface, the through wall cracks were identified.
"This condition was determined to be reportable at 1730 EST for penetration 30, and at 1915 EST for penetration 29.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A).
"Reactor head penetrations 29 and 30 will be repaired prior to placing the reactor vessel head back in service.
"The licensee notified the NRC Resident Inspector."
* * * RETRACTION ON 11/19/14 AT 1434 EST FROM TERRY DAVIS TO DONG PARK * * *
"On October 17, 2004, Nuclear Management Company notified the NRC, via non-emergency event report 41128 that leak path detection indications had been identified in two reactor pressure vessel head control rod drive mechanism nozzle penetrations at Palisades. At that time, the probable cause of the identified indications was believed to be primary water stress corrosion cracking (PWSCC). As a result, event report 41128 was made in accordance with 10 CFR 50.72(b)(3)(ii)(A) as a condition that resulted in a principle safety barrier being seriously degraded.
"Based on a recently completed engineering evaluation that compared the indications found in 2004 to the indications identified in subsequent examinations, it was determined the indications originally discovered in 2004 were embedded welding indications, caused by the original welding process.
"Since the indications identified in 2004 were not caused by PWSCC, serious degradation of a principle safety barrier did not exist. Consequently, the reporting criterion of 10 CFR 50.72(b)(3)(ii)(A) is not applicable. Therefore, event report 41128 is being retracted. In addition, Palisades Licensee Event Report (LER), 2004-002, 'Leak Path Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations,' is being cancelled."
The licensee has notified the NRC Resident Inspector.
Notified R3DO (Peterson). |
| Non-Agreement State | Event Number: 50603 | Rep Org: PARKVIEW HEALTH
Licensee: PARKVIEW HEALTH
Region: 3
City: FORT WAYNE State: IN
County:
License #: 13-01284-02
Agreement: N
Docket:
NRC Notified By: YUENIAN ZHANG
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/11/2014
Notification Time: 16:25 [ET]
Event Date: 11/11/2014
Event Time: [EST]
Last Update Date: 11/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
| Person (Organization):
DAVID HILLS (R3DO)
FSME EVENTS RESOURCE (EMAI)
NMSS EVENTS RESOURCE (EMAI)
| Event Text GYNECOLOGICAL BRACHYTHERAPY TREATMENT TO LARGER AREA THAN PRESCRIBED AREA
A patient was prescribed four 550 cGy gynecologic brachytherapy treatments totaling 2200 cGy. The third treatment prescribed a treatment area of 5 cm instead of the actual treated area of 7 cm. The patient was released after the outpatient treatment. The hospital in attempting to notify the physician of the incident.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Agreement State | Event Number: 50605 | Rep Org: NEW MEXICO RAD CONTROL PROGRAM
Licensee: SPECTRATEK SERVICES
Region: 4
City: ALBUQUERQUE State: NM
County:
License #: TA 172-25
Agreement: Y
Docket:
NRC Notified By: CARL SULLIVAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/12/2014
Notification Time: 13:02 [ET]
Event Date: 10/14/2014
Event Time: [MST]
Last Update Date: 11/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
FSME EVENTS RESOURCE (EMAI)
NMSS EVENTS RESOURCE (EMAI)
OIP (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text MISPLACED RADIOACTIVE SHIPMENT
A shipment consisting of eight boxes of radioactive material was shipped from Albuquerque, New Mexico to Port Harcourt, Nigeria on 9/29/2014. The shipment was confirmed to have arrived at Lagos Airport in Nigeria on 10/14/2014, but it didn't clear customs and it was not transported to its final destination in Port Harcourt, Nigeria. The radioactive material consisted of:
"2 boxes 18"x18"x15" Iridium-192, 320 mCi Total (160mCi each box)
"3 boxes 18"x18"x15" Scandium-46, 120 mCi Total (40mCi each box)
"3 boxes 18"x18"x15" Antimony-124, 120 mCi Total (40mCi each box)"
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: 50625 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: TIM HOLLAND
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/19/2014
Notification Time: 03:39 [ET]
Event Date: 11/18/2014
Event Time: 19:00 [CST]
Last Update Date: 11/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
BOB HAGAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNANALYZED CONDITION DUE TO ALL FOUR SAFETY INJECTION ACCUMULATORS INOPERABLE
"Following shift turnover from days to nights on 11/18/2014, it was discovered that all (4) of the Safety Injection (SI) Accumulator Outlet Isolation Valve breakers were unlocked and closed. At the time of discovery, 3 of the safety injection accumulator valves were open and 1 was closed for testing. At that time the plant was in MODE 3 at normal operating pressure and temperature. The plant had been performing RCS pressure isolation valve testing prior to shift turnover. The condition was discovered during testing of valves associated with the 'C' safety injection accumulator.
"After discovery of the condition, Operations directed that the 'A', 'B', and 'D' SI Accumulator Outlet Isolation Valve breakers be opened and locked. This action was completed by approximately 1930 [CST] on 11/18/2014.
"The NRC Resident Inspector was notified."
The plant entered T.S. 3.0.3 for approximately 30 minutes while restoring the 'A', 'B' and 'D' accumulators to operable (breakers opened and locked with their associated outlet valves open). |
| Power Reactor | Event Number: 50627 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PATRICK HARTIG
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/19/2014
Notification Time: 09:57 [ET]
Event Date: 11/19/2014
Event Time: 09:43 [EST]
Last Update Date: 11/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
TODD JACKSON (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 EAL REQUIRED GASEOUS WASTE EFFLUENT RADIATION MONITORS REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
"The Beaver Valley Power Station (BVPS) Unit 1 Special Particulate, Iodine and Noble Gas (SPING 4) monitors were removed from service for a planned equipment upgrade/replacement. During the replacement process certain Emergency Action Level (EAL) required monitors will not be functional, therefore, alternate methods of monitoring have been placed in effect. The replacement activities are expected to take approximately 60 days. A follow-up notification will be made after the required monitors are returned to service and declared functional.
"This is an 8 hour notification per 10 CFR 50.72(b)(3)(xiii). No BVPS Unit 2 systems will be adversely affected by the Unit 1 replacement activity.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50628 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARK JANKINS
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/19/2014
Notification Time: 16:42 [ET]
Event Date: 11/19/2014
Event Time: 15:37 [CST]
Last Update Date: 11/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
BOB HAGAR (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 | Event Text POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"On 11/19/2014, Wolf Creek determined that the alternative shutdown procedure for responding to a fire in the control room does not address all potential operating modes of the credited emergency diesel generator. During the 2014 Triennial Fire Protection Inspection, it was postulated that a loss of offsite power following a fire in the control room would cause the Train B emergency diesel generator (EDG) to start and load to the bus. The fire is also postulated to cause damage to the Train B essential service water (ESW) pump control circuit and prevent the pump from automatically starting and cooling the EDG. Additionally, the fire is postulated to cause spurious operation of another large load that is not normally sequenced onto the bus following a loss of offsite power. This postulated scenario loads the EDG to approximately 53% of its rated load without cooling. This scenario was not considered when developing the control room fire response strategy. Preliminary calculations show that operators have 3.6 minutes to establish cooling prior to the EDG tripping on high jacket water temperature. Performance timing determined that operators would establish cooling in approximately 10 minutes.
"Based on this information, it was determined that this condition is unanalyzed and is potentially reportable per 10 CFR 50.72(b)(3)(ii)(B). An hourly fire watch compensatory measure is in place in the control room, consistent with procedural requirements for a Post Fire Safe Shutdown circuit analysis deficiency."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 50629 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/19/2014
Notification Time: 21:44 [ET]
Event Date: 11/19/2014
Event Time: 16:18 [EST]
Last Update Date: 11/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
FRANK EHRHARDT (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FIRE PENETRATION NOT MEETING REQUIREMENTS
"During a fire inspection activity involving inspection of fire penetrations that serve as Appendix R barriers, degradation of a fire penetration was identified that was sufficient to prevent this penetration from meeting Appendix R requirements as a 3 hour fire barrier. In the event of a postulated fire in the affected areas both safe shutdown paths on Unit 1 and 2 could be compromised. Given this information the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
"Compensatory measures were put in place in accordance with the plant's Fire Hazard Analysis (FHA) for the degraded penetration in the affected fire areas. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded conditions can be corrected."
The degraded fire penetration is located between the turbine deck and the main control room. The licensee has notified the NRC Resident Inspector. | |