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Event Notification Report for November 20, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/19/2015 - 11/20/2015

** EVENT NUMBERS **


51529 51531 51534 51551 51552 51554

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Agreement State Event Number: 51529
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: NOVA ENGINEERING & ENVIRONMENTAL, LLC
Region: 1
City: TAMPA State: FL
County:
License #: 4100-2
Agreement: Y
Docket:
NRC Notified By: FLORIDA RAD CONTROL
HQ OPS Officer: DANIEL MILLS
Notification Date: 11/11/2015
Notification Time: 16:04 [ET]
Event Date: 11/11/2015
Event Time: 10:00 [EST]
Last Update Date: 11/11/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
FRANK ARNER (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

DAMAGED TROXLER GAUGE

The following was received via email:

"At approximately 1000 [EST], a Troxler Gauge was run over by a road construction roller resulting in a cracked housing of the gauge. The instrument's source probe was not extended. Initial survey results indicated 0.5 mR/hr at 12 inches (background was less than 0.1 mR/hr). An ERCIT inspector was dispatched to investigate. [The inspector's] survey indicated 15 mR/hr on contact; his report is forthcoming."

The gauge contains Cesium-137 and Americium/Beryllium sources.

The gauge was transferred to the licensee's radwaste facility.

Florida Incident Report Number: FL-15-116

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Agreement State Event Number: 51531
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: LOCKHEED MARTIN SPACE SYSTEMS COMPANY, INC
Region: 4
City: PALO ALTO State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: GENE FORRER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/12/2015
Notification Time: 13:51 [ET]
Event Date: 10/22/2015
Event Time: [PST]
Last Update Date: 11/12/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - LEAKING NI-63 SOURCES

The following report was received via e-mail:

"On 10/27/15, the RSO [Radiation Safety Officer] contacted RHB [California Radiation Health Branch] via an email to report two Ni-63 leaking sources. On 10/22/15, Thomas Gray and Associates, the vendor contracted to run the leak test analysis had informed the licensee that two of their Ni-63 sources were leaking above the prescribed limit of 0.005 microCuries. These sources were manufactured by New England Nuclear and had an initial activity of 10 mCi as of July 1966. They do not have a S/N, but were assigned internal tag numbers of 55 and 56. Both sources have not been used in any experiments for many years and have remained in storage. As of 10/27/15, both sources had an activity of 7.11 mCi each. They were not found to be leaking or damaged in previous leak tests. [The] RSO further stated that these sources were not removed from its safe or from its container anytime in the last year. As a result, no contamination was spread through the buildings.

"[The] RSO is working with Thomas Gray and Associates to schedule a waste pick up in early 2016 to dispose of these sources."

California Event 5010-102715

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Agreement State Event Number: 51534
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: SC DEPARTMENT OF TRANSPORTATION
Region: 1
City: SUMPTER State: SC
County:
License #: 119
Agreement: Y
Docket:
NRC Notified By: LELAND CAVE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/12/2015
Notification Time: 18:36 [ET]
Event Date: 11/12/2015
Event Time: [EST]
Last Update Date: 11/12/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
FRANK ARNER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

A Troxler moisture density gauge owned by the South Carolina Department of Transportation was run over and damaged. The Am-241 and Cs-137 sources were retracted at the time of the accident. Surveys by the Radiation Safety Officer were normal. The damaged gauge will be sent to the manufacturer for refurbishment or disposal.

Sources:
Am-241: 40 mCi
Cs-137: 8 mCi

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Power Reactor Event Number: 51551
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: DIRK DRINKARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/19/2015
Notification Time: 00:56 [ET]
Event Date: 11/18/2015
Event Time: 23:33 [EST]
Last Update Date: 11/19/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
MIKE ERNSTES (R2DO)
BERNARD STAPLETON (IRD)
SCOTT MORRIS (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

AFTER-THE-FACT NOTIFICATION OF UNUSUAL EVENT

"Unit 3 experienced Loss of Offsite Power due to lockout on Unit 3 Startup transformer. The 3B EDG auto started and loaded on the 3B 4KV Bus. The 3A Sequencer was out of service and prevented the 3A EDG from auto starting and supplying 3A 4KV busses. With only 3B 4KV bus powered from an EDG and no offsite power to Unit 3, Unit 3 entered an Unusual Event.

"Core cooling was restored with 3B RHR pump at 2343 EST. At 2350 EST, 3A 4KV Bus was manually loaded onto 3A EDG and conditions for Unusual Event were terminated.

"Additionally this is a non-emergency eight hour notification in accordance with 10CFR50.72(b)(3)(iv)(A), for a valid automatic actuation of the 3B Emergency Diesel Generator."

While core cooling was lost, the core experienced a 3 degree heat up. Spent fuel pit cooling has also been restored. The cause of the transformer lockout is under investigation.

Unit 4 was unaffected and continues to operate at 100% power.

The licensee has notified state and local authorities about this event. The licensee has also notified the NRC Resident Inspector.

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Power Reactor Event Number: 51552
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: BEN HUFFMAN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/19/2015
Notification Time: 11:51 [ET]
Event Date: 11/19/2015
Event Time: 07:24 [CST]
Last Update Date: 11/19/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GREG WARNICK (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 97 Power Operation 97 Power Operation

Event Text

HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE

"At 0724 [CST] on 11-19-2015, River Bend Station declared the High Pressure Core Spray System inoperable in accordance with Technical Specification 3.8.9, Condition E (Declare High Pressure Core Spray System and Standby Service Water System Pump 2C inoperable immediately) due to Division 2 Control Room Air Conditioning System Chiller HVK-CHL1D being inoperable due to a significant lube oil leak. HVK-CHL1D tripped on Low Lube Oil Differential Pressure. Division 1 Control Building Air Conditioning System Standby Chiller HVK-CHL1A automatically started as expected.

"Actions taken to exit LCO [Limiting Condition of Operation]: Operators alternated to HVK-CHL1B in standby."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 51554
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: JAMES VRLA
HQ OPS Officer: VINCE KLCO
Notification Date: 11/19/2015
Notification Time: 19:10 [ET]
Event Date: 11/19/2015
Event Time: 13:00 [PST]
Last Update Date: 11/19/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Defueled 0 Defueled
3 N N 0 Defueled 0 Defueled

Event Text

UNANALYZED CONDITION DUE TO SPENT FUEL POOL TEMPERATURE OUTSIDE LIMITS

"A review of operations log data revealed the Unit 2 Spent Fuel Pool temperature was allowed to drift approximately two degrees below the accepted analyzed temperature of 68 degrees F. The Extent of Condition is under review and the number of instances has not been fully determined. It is possible Unit 3 may have also been affected.

"As described in the San Onofre UFSAR, Section 9.1.2.3 'Design Basis for Fuel Storage and Handling,' one of the conditions assumed in meeting the design basis, is as follows: the most adverse delta-k (reactivity change) was analyzed for a pool temperature range from 68 degree F to 160 degree F. Although the temperature decrease is considered unlikely to have a significant impact on the results of the analysis, it is being reported under 10 CFR 50.72(b)(2) as an unanalyzed condition because there is at this time no analysis of record for the reduced temperature condition.

"There were and continue to be no observed, abnormal effects from the temperature drop below 68 degrees F, and no impact on the health or safety of plant personnel of the public. Re-analysis is in progress and is expected to demonstrate that the criticality acceptance criteria of 10CFR50.68 were met at all times."

The licensee notified the Regional NRC Contact.

Page Last Reviewed/Updated Friday, November 20, 2015
Friday, November 20, 2015