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Event Notification Report for October 19, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/18/2011 - 10/19/2011

** EVENT NUMBERS **


47258 47340 47344 47346 47348 47349 47350 47351 47352

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Power Reactor Event Number: 47258
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BOB KLINE
HQ OPS Officer: CHARLES TEAL
Notification Date: 09/13/2011
Notification Time: 01:57 [ET]
Event Date: 09/12/2011
Event Time: 17:45 [PDT]
Last Update Date: 10/19/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GREG PICK (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

CONTROL ROOM ENVELOPE DECLARED INOPERABLE

"On September 12, 2011, at 1745 PDT operators declared the control room envelope (CRE) inoperable and entered Technical Specification (TS) 3.7.10 Action B. This was due to discovery of inadequately documented CRE in-leakage test data.

"On September 12, 2011, DCPP [Diablo Canyon Power Plant] personnel reviewing the CRE testing dated February 3, 2005 determined that the test report provided inadequate information to conclude that the most limiting alignment for control room pressurization would result in zero cubic feet per minute (CFM) in-leakage into the CRE, contrary to the Final Safety Analysis Report (FSAR) accident analysis for the most limiting design basis accident. Three of the four ventilation alignments tested had reported values of in-leakage greater than zero CFM.

"Plant staff implemented compensatory measures by placing the control room ventilation system into its pressurization accident alignment at 1828 PDT using the alignment from the test which had a reported value of zero CFM in-leakage. Additionally, administrative controls are being established to maintain post-Loss of Coolant Accident Emergency Core Cooling System leakage at a rate that would ensure operator doses are maintained less than the FSAR accident analysis results for the highest in-leakage rate reported by the test.

"Plant personnel notified the NRC Resident Inspector."


* * * UPDATE FROM MICHAEL KENNEDY TO JOHN KNOKE AT 1816 EDT ON 09/16/2011 * * *

"On 9/13/11 procedure revisions were approved with reduced limits for post-Loss of Coolant Accident Emergency Core Cooling System (ECCS) leakage. These reduced limits ensure operator doses are maintained less than the FSAR accident analysis results for the highest in-leakage rate reported by the CRE in-leakage test. Plant staff have since determined that the potential benefit of operating the control room ventilation system in its pressurization alignment was unnecessary with the ECCS leakage restriction and on 9/16/11 operators restored the control room ventilation system into its normal operating alignment."

The licensee has notified the NRC Resident Inspector. Notified R4DO (Greg Pick)


* * * UPDATE FROM SHANE GUESS TO DONALD NORWOOD AT 0042 EDT ON 10/19/2011 * * *

"This is an update to EN #47258 reported on 9/13/11 where it was reported that operators had declared the Control Room Envelope inoperable. [This report was subsequently] updated on 9/16/2011.

"On 10/18/11 at 16:45 PDT, plant staff determined that the CRE testing dated February 3, 2005 was not performed using a bounding configuration which would result in greatest consequence to the control room operators. The recorded in-leakage from the test was therefore considered to be non-bounding.

"[As a result of this determination, plant staff have] implemented additional compensatory measures by issuing a shift order requiring the use of self-contained breathing apparatus and potassium iodide tablets under certain accident conditions in accordance with Regulatory Guide 1.196 and NEI 99-03.

"Plant personnel notified the NRC Resident Inspector."

Notified R4DO (Campbell).

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Agreement State Event Number: 47340
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MD ANDERSON CANCER CENTER
Region: 4
City: HOUSTON State: TX
County:
License #: L00466
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/13/2011
Notification Time: 14:45 [ET]
Event Date: 10/12/2011
Event Time: 14:30 [CDT]
Last Update Date: 10/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
JAMES DANNA (FSME)

Event Text

AGREEMENT STATE REPORT - MALFUNCTION OF IRRADIATOR SOURCE DRIVE MECHANISM

The following information was received from the Texas Dept of Health Services Investigation Unit Radiation Branch via email:

"On October 12, 2011, at 1552 hours CDT, the Agency was notified by the licensee's Radiation Safety Officer (RSO) that there had been a malfunction identified with [a self contained] irradiator, at the licensee's facility in Houston, Texas. The source was, and had been, in the fully shielded position and therefore did not present a risk of exposure to any individual. The owner/operator within the facility reported to the RSO's staff that the compressor failed on Friday, October 7, 2011, and they were going to get it repaired or replaced. While working to replace/repair the compressor, it was determined that the problem was not the compressor. The licensee was able to open and close the door to the irradiation chamber and apparently make up all the interlocks, but the source failed to move. Finally, it was determined on Wednesday, October 12th at approximately 1430 hrs that the source drive mechanism was failing to move the source. The owner/operator has been in contact with Shepherd to make arrangements for repair. More information will be provided as it is obtained. The irradiator has been posted as out of service. The source is properly shielded as shown by dose rate surveys conducted in the room."

Texas Incident Number: I-8892

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Agreement State Event Number: 47344
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TEAM INDUSTRIAL SERVICES INC
Region: 4
City: ALVIN State: TX
County:
License #: L00087
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/14/2011
Notification Time: 12:10 [ET]
Event Date: 10/14/2011
Event Time: [CDT]
Last Update Date: 10/14/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

TEXAS AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE FAILED TO RETRACT

The following report was received by the Texas Dept of State Health Services Investigations Unit Radiation Branch via e-mail:

"On October 14, 2011, the Agency [Texas Dept of State Health Services] was notified by the licensee that on October 14, 2011, a radiography team was unable to retract a 32 curie Iridium - 192 source to the exposure device. The QSA model 880 D exposure device was set on a pipe to perform radiography on an adjacent pipe. The exposure device fell off the pipe approximately 18 inches and the return portion of the crankout tube was crimped preventing the radiographer from fully retracting the source. The radiographer contacted his Radiation Safety Officer and notified them of the event. The radiographer is qualified to perform source recoveries, so he dismantled the crankout device, pulled the drive cable out of the crankout device, and manually retracted the source to its fully retracted and locked position. No member of the general public received any exposure during this event. The radiographer received a total of 20 millirem for the day. Visual inspection of the exposure device did not find any damage to the camera. The licensee has removed the exposure device and crankout device from service and will send them back to the manufacturer for inspection and repair. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident Number: I-8893

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Agreement State Event Number: 47346
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONSTRUCTION TESTING AND ENGINEERING, INC
Region: 4
City: OXNARD State: CA
County:
License #: 7361-56
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/14/2011
Notification Time: 17:43 [ET]
Event Date: 10/14/2011
Event Time: 07:15 [PDT]
Last Update Date: 10/14/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
JAMES DANNA (FSME)

Event Text

CALIFORNIA AGREEMENT STATE REPORT - TROXLER GAUGE LOST AND SUBSEQUENTLY RECOVERED

The following is a summary of information received from the California Department of Health - Radiologic Health Branch via e-mail:

"On October 14, 2011 Construction Testing and Engineering, Inc., contacted [the California Department of Health Radiologic Health Branch] about a portable moisture/density gauge (Troxler Model 3411B, S/N 8349, 8 mCi Cs-137, 40 mCi Am:Be-241) that was lost while being transported to a jobsite at California State University, Channel Islands. The gauge operator had picked up the gauge at their facility around 6:45-7:15 A.M. and left for the jobsite, which is approximately 8-12 miles east of their facility. When nearing the jobsite, while travelling on Laguna Rd., around 7:15 and 7:30 A.M., the gauge operator noticed that the lid on the gauge transport box was open, the operator stopped the vehicle and noticed that the gauge was gone. He immediately contacted his office and Ventura County Sherriff's to report the incident. After filing a report with the police, the gauge operator then proceeded to search for the gauge.

"[The licensee] stated that the fire department and police were also searching for the gauge. [The licensee] stated that their employees had also looked for the gauge inside and outside of their facility and asked their neighbors if they had seen the gauge and to look out for the gauge. The gauge had been used by the same operator at the same jobsite for the last few weeks, and had used it the day before. [The licensee] also stated that the gauge should have been chained to the truck bed and should have had two locks in place.

"[Shortly after 10:00 A.M, Oxnard Fire Department reported that] the gauge had been found and one of their trucks was enroute to verify that the gauge was intact. [The] gauge had been found intact with the handle securely locked and minor scratches and that the police/fire department verified that there was no unusual radiation readings. The gauge was found in the vicinity of 601 E. Bard Rd., Oxnard, approximately 2 miles from Pacific Coast Highway. The individual who found the gauge, who works for another construction company, brought the gauge to 601 E. Bard Rd. and notified the police. The Oxnard Police and Fire Department and the gauge operator arrived at the scene and verified the gauge was intact.

"[The California Department of Health - Radiologic Health Branch informed the licensee] that a leak test was needed to be done prior to using the gauge again and that a written report needed to be provided within 30 days. While the investigation is still ongoing, pending licensee's findings in their 30 day report, the licensee is likely to be cited for improperly securing the gauge, and loss of control of the gauge. Also a site visit will be conducted to verify the licensee is properly securing their gauges during transport."

California Report Number: 101411

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Power Reactor Event Number: 47348
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL SPRINKLE
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/17/2011
Notification Time: 21:33 [ET]
Event Date: 10/17/2011
Event Time: 20:50 [EDT]
Last Update Date: 10/18/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARK LESSER (R2DO)
FREDERICK BROWN (NRR)
BILL GOTT (IRD)
BRUCE BOGER (NRR)
VICTOR McCREE (R2RA)

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

UNIT 1 DECLARED AN UNUSUAL EVENT BASED ON AMMONIA LEVELS EXCEEDING OSHA LIMITS

"Normal Operation of WBN [Watts Bar Nuclear] Unit 1 impeded in the Turbine Building, El. 685, West side of the Unit 1 Main condenser due to Toxic Gas (ammonia) concentrations of 75-79 ppm exceeding the OSHA Permissible Exposure Limit (PEL) of 50 ppm, and the ACGIH [American Conference of Governmental Industrial Hygienists] limit of 25 ppm. WBN Unit 1 returned to approximately 100% RTP on Monday, October 17, 2011, following a maintenance outage. Suspect excessive ammonia concentrations due to condenser vacuum pump continuous drains which may need throttling open to increase drain flow, following Unit startup. (Ammonia is used to treat feedwater for secondary chemistry control). There have been no injuries from this event. NRC Senior Resident [Inspector] has been notified. (Event Class 4.4.A, Toxic Gas, Unusual Event)."

The licensee informed both the State and local agencies. Notified FEMA (Blankenship) and DHS (Konopka).


* * * UPDATE FROM BILL SPRINKLE TO DONALD NORWOOD AT 0052 EDT ON 10/18/2011 * * *

At 0047 EDT on 10/18/2011, the licensee terminated the Notification of Unusual Event condition based on ammonia concentrations having been reduced to approximately 6 ppm. Normal personnel access to the affected area has been restored. Unit 1 remained at 100% power during this event with no changes or challenges to plant operations. During the event there were no additional EAL designators. During the event there were no significant changes in plant conditions. During the event there were no significant changes in plant radiological conditions. During the event there were no offsite protective recommendations made by the licensee.

The licensee notified the NRC Resident Inspector and State and local agencies.

Notified R2DO (Lesser), NRR EO (Brown), IRD (Morris), DHS (Gates), and FEMA (Blankenship).

* * * UPDATE AT 1354 EDT ON 10/18/11 FROM BILLY JOHNSON TO S. SANDIN * * *

"This information is being provided to the NRC for a 10CFR50.72(b)(2)(xi) notification.

"TVA is planning on making a news release to local media affiliates and posting the news release on TVA's website. This news release is in reference to the Notification of Unusual Event (NOUE) Watts Bar Nuclear Plant recently entered and exited for ammonia levels exceeding OSHA limits (reference EN 47348 and update).

"The licensee notified the NRC Senior Resident Inspector."

Notified R2DO (Lesser).

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Power Reactor Event Number: 47349
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOSE A VASQUEZ
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2011
Notification Time: 03:20 [ET]
Event Date: 10/18/2011
Event Time: 00:56 [EDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARK LESSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 55 Power Operation 55 Power Operation
4 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO WASTE WATER SPILL

"This is a four (4) hour Non-Emergency notification to the NRC Operations Center for a notification to other government agency in accordance with 10CFR50.72(b)(2)(xi).

"On 10/18/2011 at 0056 EDT, the Miami-Dade County Department of Environmental Resource Management (DERM) was notified of a spill of approximately 50 gallons of waste water (ash-water sluice) from Turkey Point Units 1 and 2 fossil power plants. This spill is not related to Turkey Point Units 3 and 4 nuclear power plant operations."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47350
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BEN WESCOT
HQ OPS Officer: JOE O'HARA
Notification Date: 10/18/2011
Notification Time: 05:59 [ET]
Event Date: 10/18/2011
Event Time: 04:50 [CDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ROBERT DALEY (R3DO)

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

TECHNICAL SUPPORT CENTER EMERGENCY DIESEL GENERATOR OUT OF SERVICE

"At 0450 (CDT), on October 18, 2011, the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was removed from service for preplanned maintenance. The expected duration of the maintenance is 12 hours. Normal power to the TSC will be available for the duration of the maintenance.

"This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)


"The NRC Resident Inspector has been notified."

* * * UPDATE AT 1739 EDT ON 10/18/11 FROM STEVE BREWER TO S. SANDIN * * *

The Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was returned to service at 1637 CDT on 10/18/11.

The licensee informed the NRC Resident Inspector. Notified R3DO (Daley).

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Power Reactor Event Number: 47351
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JON LAUDENBACH
HQ OPS Officer: PETE SNYDER
Notification Date: 10/18/2011
Notification Time: 17:36 [ET]
Event Date: 10/18/2011
Event Time: 09:39 [CDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ROBERT DALEY (R3DO)

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

RANDOM FITNESS FOR DUTY TEST FAILURE

A non-licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.

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Power Reactor Event Number: 47352
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID BUTLER
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/18/2011
Notification Time: 18:21 [ET]
Event Date: 10/18/2011
Event Time: 15:45 [CDT]
Last Update Date: 10/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
VIVIAN CAMPBELL (R4DO)

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

ALUMINUM VALVE DISCOVERED INSTALLED IN CONTAINMENT

"While Unit 1 was in Mode 5, for the 15th refueling outage, an issue was identified with the valve material of an existing installed airlock hydraulic system valve. The valve was determined to have an aluminum body which is not suitable for safety related use in containment.

"The Unit 1 airlock hydraulic system penetrates the containment pressure boundary. The airlock hydraulic system achieves containment integrity by being a closed system under GDC-57. A loss of pressure boundary integrity would no longer meet General Design Criteria 57 (GDC-57) for a closed system.

"Aluminum is a restricted/limited material in containment because it is not compatible with accident conditions and has failures with multiple adverse effects. Due to this condition, the valve would potentially lose pressure integrity during a LOCA with containment spray actuation.

"Compensatory measures have been taken to prevent containment spray from affecting this valve and at this time, the airlock is operable.

"Luminant Power determined this issue to be reportable at 1545 [CDT] on 10/18 per 50.72(b)(3)(ii)(B) Comanche peak Unit 1 being in an unanalyzed condition that significantly degrades plant safety.

"The Unit 2 airlock is a different design and this condition does not apply to Unit 2."

This material was installed during original construction and discovered during a licensee self-assessment.

The licensee will notify the NRC Resident Inspector.

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Thursday, March 29, 2012