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Event Notification Report for September 19, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/18/2014 - 09/19/2014

** EVENT NUMBERS **


50425 50445 50447 50467 50468 50470

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility Event Number: 50425
Facility: B&W NUCLEAR OPERATING GROUP, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: TONY ENGLAND
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/04/2014
Notification Time: 16:49 [ET]
Event Date: 09/04/2014
Event Time: 11:00 [EDT]
Last Update Date: 09/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
Person (Organization):
DEBORAH SEYMOUR (R2DO)
BRIAN SMITH (NMSS)
FUELS OUO GROUP (EMAI)

Event Text

UNANALYZED CONDITION RELATED TO POTENTIAL MATERIAL TRANSFER CART TIPPING

"I. EVENT DESCRIPTION: On September 4, 2014 at approximately 1100 [EDT], a Nuclear Criticality Safety (NCS) engineer identified a safety concern. While working to consolidate information in the safety basis for the safe geometry storage and transport carts, it was determined that an unanalyzed condition existed that did not meet the performance requirements of 10 CFR 70.61. Tipping or impact of a cart during transport had not been considered as a credible upset condition.

"II. EVALUATION OF THE EVENT: At B&W's NOG-L [Nuclear Operations Group] facilities, safe geometry storage and transport carts are used to transfer uranium bearing materials between radiologically controlled areas. The carts are typically used to transfer scrap and waste materials in favorable volumes less than or equal to 2.5 liter containers to the Drum Count Area for 235U assay. Because the 235U content of such containers is not known until they have been assayed, they are referred to as 'unknowns' and are subject to a net weight limit. These containers are limited to a maximum of 7,000 grams net weight (approximately 15 pounds) of uranium bearing material in any form.

"There are forty storage locations on a cart, twenty per side. The locations on each side are arranged in an array of 4 columns, each column contains 5 storage locations. During transport each column of storage locations is protected by closure of a door. The four column doors on each side of the cart are secured by a common locked bar.

"The NCS evaluation of the safe geometry storage and transport carts did not address possible tipping during transit. Although unlikely, it is believed at this point the event is credible. If a cart were to tip, no controls were identified to retain the containers on the cart. Although the doors on the cart are secured by a robust locking bar, this action is taken for security purposes and is not credited as an IROFS [Item Relied On For Safety]. Assuming the containers on the cart were fully loaded (7 kg net weight) with a U-metal water mixture at optimum H/X and the cart tipped over, and more than three containers fell out of the cart, a configuration could result that would exceed the keff safety limit of 0.95 in NRC License SNM-42 for a single contingency.

"The requirement of 10 CFR 70.61 (d) states in part: '... the risk of nuclear criticality accidents must be limited by assuring that under normal and credible abnormal conditions, all nuclear processes are subcritical, including use of an approved margin of subcriticality for safety.'

"Therefore the performance requirement of 10 CFR 70.61 (d) would not be maintained during this credible abnormal condition.

"The as-found condition had no actual safety significance. There was no immediate risk or threat to the safety of the workers, the public, or the environment as a result of this condition. The safe geometry storage and transport carts did not contain any uranium bearing materials. There was no actual tipping event. The carts were immediately removed from service.

"Ill. NOTIFICATION REQUIREMENTS: B&W is making this 24 hour report in accordance with 10 CFR 70, Appendix A, (b)(1)--Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 70.61.

"IV. STATUS OF CORRECTIVE ACTIONS: The carts have been removed from service. An investigation of the root causes of this condition is ongoing. Corrective actions will be determined as a result of the investigation."

The licensee notified the NRC Resident Inspector and will be notifying the facility NMSS Project Manager (Baker).

* * * RETRACTION FROM KENNY KIRBY TO HOWIE CROUCH AT 1634 EDT ON 9/18/14 * * *

"The initially identified abnormal condition was not analyzed in the Integrated Safety Analysis. A conservative approach was taken in evaluating the condition in order to ensure compliance with the specified time period established in the regulations for reporting. Further analysis has determined the condition is not credible. Although unlikely, should more than three containers fall from the cart, it is not credible that a configuration could occur that would exceed the keff limit of 0.95 in NRC License SNM-42 for a single contingency. The performance requirements of 10 CFR 70.61 would be maintained. Following the guidance of FCSS ISG-12, Rev 0, '10 CFR Part 70, Appendix A- Reportable Safety Events', B&W is correcting Event Notification #50425 in accordance with 10 CFR 70.74(a)(4) and withdrawing the 10 CFR 70, Appendix A, (b)(1) notification."

The licensee has notified the NRC Resident Inspector.

Notified R2DO (Sykes), NMSS EO (Gonzalez) and Fuels OUO Group via email.

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Agreement State Event Number: 50445
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: SLADDEN ENGINEERING
Region: 4
City: BEAUMONT State: CA
County:
License #: 6318-33
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/10/2014
Notification Time: 14:16 [ET]
Event Date: 09/10/2014
Event Time: [PDT]
Last Update Date: 09/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE/DENSITY GAUGE

The following information was received via E-mail:

"On September 8, 2014, at approximately 0845 PDT, the RSO of Sladden Engineering, RML #6318-33, was contacted by RHB Brea concerning a moisture/density gauge, CPN, model MC1DRP, serial number MD40807529 (Cs-137, 0.370 GBq, Am-241, 1.85 GBq) that had been damaged when run over by construction equipment at a building site located at 123 N. Palm Canyon Drive, Palm Springs, California, on September 3, 2014, at approximately 1400 PDT. The authorized user at the construction telephoned the RSO. They then went through the radiation safety plan over the phone, and after an initial inspection of the radioactive gauge it was determined that the gauge was heavily damaged but since the source remained in the shielded position, the RSO authorized transport back to the office in the Type A transport container. A closer inspection of the radioactive gauge was conducted by the RSO on the following morning, September 4, 2014, at which time it was determined that the source rod was broken. The RSO contacted the RHB South Brea office and left voice mail messages, then contacted the emergency number and was transferred to a telephone number in Sacramento RHB and left another voice mail message. The RSO performed a leak test on the radioactive gauge and sent it to PNT Company for analysis on September 4, 2014, and received notification that the sources were negative for leakage on September 5, 2014. The RSO performed a follow-up investigation of the incident at the location of the accident and has contacted Maurer Technical Services for disposal of the radioactive gauge since it is beyond repair.

"This is being reported to the NRC Operations Center as a 24-hour report under 10CFR30.5(b)(2) since the radioactive gauge cannot be locked in the shielded position (due to the source rod being broken ) despite the fact that the Cs-137 source is in the shielded position as that was the configuration at the time of the accident."

California Report #: 5010-090314

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Agreement State Event Number: 50447
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: HOOD CONTAINER CORPORATION
Region: 1
City: WAVERLY State: TN
County:
License #: R-43003-J14
Agreement: Y
Docket:
NRC Notified By: CHARLES ARNOTT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/11/2014
Notification Time: 11:59 [ET]
Event Date: 09/10/2014
Event Time: [EDT]
Last Update Date: 09/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TODD JACKSON (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - GAUGE SHUTTER STUCK IN OPEN POSITION

The following report was received from the Tennessee Department of Environment and Conservation Division of Radiological Health via email;

"The licensee and gauge service representative called [the Tennessee Department of Environment and Conservation Division of Radiological Health] to report a gauge shutter stuck in the open position. The gauge is an Ohmart Model SHRM, SN 3307, with a 35 mCi Cs-137 Model A-5771 source. The gauge remains in the installed position. It will be replaced in the future by the service representative. The gauge will be shielded as needed if the shutter is not able to be closed before transport."

There were no over exposures and additional information will be provided, as it is received, from the State of Tennessee.

Tennessee Event Number: TN-14-172

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Power Reactor Event Number: 50467
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN TAYLOR
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/18/2014
Notification Time: 13:01 [ET]
Event Date: 09/18/2014
Event Time: 11:50 [EDT]
Last Update Date: 09/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 68 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO MISALIGNED CONTROL ROD

"During the performance of PT-Q89, Control Rod Exercise Test, Rod G-3 in Shutdown Bank 'B' misaligned (stepped in) to approximately 195-200 steps indicated with group demand at 217 steps. The movable gripper fuse was suspect, found not blown [so further] troubleshooting required. At 1150 [EDT], the decision was made to reduce power to approximately 70% within two hours per I.T.S. [Improved Technical Specification] 3.1.4.b.2.2. The plant is currently stable at 68% power. I.T.S. 3.1.5.b.1 was also entered for Shutdown Bank 'B' less than allowable insertion limits at time 1228 [EDT] to be in Mode 3 in 6 hrs. (1828 [EDT])."

The licensee notified the New York Independent System Operator, the New York Public Service Commission and the NRC Resident Inspector.

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Power Reactor Event Number: 50468
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: LARRY HAUTH
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/18/2014
Notification Time: 14:05 [ET]
Event Date: 09/18/2014
Event Time: 11:55 [CDT]
Last Update Date: 09/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
TOM ANDREWS (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

"During a review of INPO Event Report 14-33, Direct Current Circuits Challenge Appendix R Fire Analysis, it was determined that portions of the control circuits for the Turbine Generator DC Emergency Lube Oil Pump and the Emergency DC Seal Oil Pump are not properly fused to prevent overload and possible secondary fires. The review found that a fire at the motor starter cabinet in the turbine building could cause specific smart hot shorts that could cause overheating of the control cable and result in secondary fires outside the turbine building. 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).

"Hourly fire watch compensatory measures are in place in the affected areas of the Turbine Building. The presence of compensatory measures in addition to automatic fire detection and suppression in these fire areas ensures protection of the equipment."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 50470
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CHUCK JACOBS
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/18/2014
Notification Time: 18:43 [ET]
Event Date: 09/18/2014
Event Time: 12:35 [PDT]
Last Update Date: 09/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MICHAEL VASQUEZ (R4DO)

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

OFFSITE NOTIFICATION - FAILURE TO SUBMIT REQUIRED SEMI-ANNUAL AND ANNUAL SAMPLES AND REPORTS PER NPDES

"Today, at 1235 [PDT], San Onofre made the decision to notify offsite agencies (San Diego Regional Water Quality Control Board and Environmental Protection Agency if directed by SDRWQCB). Initial contact made with the San Diego Regional Water Quality Control Board was at 1333 [PDT] on 9/18/14. The subject of the report is listed below:

"On September 15, 2014, during a review of the NPDES [National Pollutant Discharge Elimination System] self-monitoring reports, SCE SONGS [Southern California Edison San Onofre Nuclear Generating Station] environmental staff discovered annual and semi-annual samples and required reports due in 2014 were not submitted on time and are now past due:

"- The missed samples and associated reports are non-radiological in nature
"- All parameters (physical and analytical data) in past Semi-annual and Annual reports have been in compliance with the NPDES permit."

The licensee informed the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, September 19, 2014
Friday, September 19, 2014