Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for April 8, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/07/2010 - 04/08/2010

** EVENT NUMBERS **

General Information or Other	Event Number: 45807
Rep Org: VIRGINIA RAD MATERIALS PROGRAM Licensee: ECS MID-ATLANTIC LLC Region: 1 City: State: VA County: ROANOKE License #: 170-314-1 Agreement: Y Docket: NRC Notified By: CHARLES COLEMAN HQ OPS Officer: DONG HWA PARK	Notification Date: 04/02/2010 Notification Time: 12:17 [ET] Event Date: 04/01/2010 Event Time: [EDT] Last Update Date: 04/02/2010
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): PAUL KROHN (R1DO) ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - TROXLER GAUGE DAMAGED BY CONSTRUCTION EQUIPMENT

The following information was received from the Commonwealth of Virginia via facsimile:

"The licensee's portable density gauge (Troxler Model 3430 S/N 038435) was damaged on April 1, 2010 when it was struck by a piece of earth moving equipment. The accident occurred at a commercial construction site in Roanoke County, Virginia. The gauge operator secured the area of the gauge and telephoned the licensee's Radiation Safety Officer who performed an onsite investigation and a radiation survey. The source was in the shielded position at the time of the accident and the survey confirmed that it remained so. There was no damage to the source rod or handle and only minor damage to the gauge trigger and casing. The gauge was returned to the licensee's storage facility. There were no injuries or radiation exposures as a result of the accident."

Virginia Event Report ID No: VA-10-02

Power Reactor	Event Number: 45816
Facility: COLUMBIA GENERATING STATION Region: 4 State: WA Unit: [2] [ ] [ ] RX Type: [2] GE-5 NRC Notified By: ERIC FRANKE HQ OPS Officer: DONALD NORWOOD	Notification Date: 04/07/2010 Notification Time: 00:33 [ET] Event Date: 04/06/2010 Event Time: 17:47 [PDT] Last Update Date: 04/07/2010
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): DAVID PROULX (R4DO)

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

Event Text

INITIATION OF TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO CONTROL ROOM EMERGENCY FILTRATION SYSTEM BEING DECLARED INOPERABLE

"At 1650 PDT Columbia Generating Station entered LCO 3.0.3 as required by LCO 3.7.3 for both divisions of Control Room Emergency Filtration (CREF) [being] inoperable. Entry into LCO 3.0.3 was required by Condition E of LCO 3.7.3, 'Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B' and has a Required Action to enter LCO 3.0.3 with an immediate Completion Time. Columbia commenced a plant shutdown at 1747 as required by LCO 3.0.3.

"[Columbia Generating Station] entered into Condition E of LCO 3.7.3 when it was determined that Radwaste Building Outside Air Smoke Detectors WOA-SMD-1A and WOA-SMD-1B did not meet seismic qualifications. Actuation of these smoke detectors would cause Radwaste Building Mixed Air Fire Dampers WMA-FD-1 and WMA-FD-2 to close. These fire dampers shutting would cause all CREF airflow to cease, preventing the control room from achieving a positive pressure. Both divisions of CREF [being] inoperable is an unanalyzed condition requiring immediate entry into LCO 3.0.3.

"This event is reportable under 50.72(b)(2)(i) due to the initiation of a plant shutdown as required by Columbia's Technical Specifications. This event is also reportable under 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"WMA-FD-1 and WMA-FD-2 have been deactivated in the open position for the smoke actuation function. [Columbia Generating Station] entered RFOLCS (Requirements for Operability of Licensee Controlled Specifications) 1.10.6 for these fire dampers [being] nonfunctional. [Columbia Generating Station] completed the required actions of LCS 1.10.6.

"The CREF system remains inoperable pending completion of a TMR (Temporary Modification Request)."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM QUOC VO TO CHARLES TEAL ON 4/7/10 AT 1957 * * *

"Question posed by NRC at time of initial report: Have these smoke detectors been installed since startup?

"Response: These smoke detectors have been installed since initial plant startup.

"A temporary modification request was installed to de-energize the non-seismic detector logic that causes automatic fire damper actuation for the two dampers identified above. The alarm function of the smoke detectors remains active with this temporary modification.

"Entry into this condition was made when it was determined that the smoke detectors were not seismically qualified and there is a possible failure mode that during an earthquake the detectors would actuate the electro-thermal link and cause the associated fire damper (WOA-FD-1 or WOA-FD-2) to close, hence impacting control room emergency filtration function.

"With implementation of the temporary modification at 2218 PDT on 4/6/10, the CREF system is now considered to be in an 'operable but non-conforming' status. As such, LCOs 3.7.3 and 3.0.3 were exited at 2218 PDT on 4/6/10.

"This event was initially reported pursuant to paragraph 50.72(b)(2)(i) as an initiation of a plant shutdown required by Columbia's Technical Specifications. Reporting pursuant to paragraph 50.72(b)(2)(i) is being retracted because negative reactivity was not inserted into the reactor prior to exiting the LCOs described above. Reporting pursuant to paragraph 50.72(b)(2)(i) would not be consistent with the guidance provided in NUREG-1022 in that no negative reactivity was inserted and the condition was corrected before exceeding the required action times."

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 45817
Facility: SAINT LUCIE Region: 2 State: FL Unit: [1] [2] [ ] RX Type: [1] CE,[2] CE NRC Notified By: ANDREW TEREZAKIS HQ OPS Officer: CHARLES TEAL	Notification Date: 04/07/2010 Notification Time: 16:48 [ET] Event Date: 04/07/2010 Event Time: 10:00 [EDT] Last Update Date: 04/07/2010
Emergency Class: NON EMERGENCY 10 CFR Section: 26.719 - FITNESS FOR DUTY	Person (Organization): JAY HENSON (R2DO)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	N	0	Cold Shutdown	0	Cold Shutdown
2	N	Y	100	Power Operation	100	Power Operation

Event Text

FITNESS FOR DUTY REPORT

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

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 45820
Facility: BROWNS FERRY Region: 2 State: AL Unit: [1] [2] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: RAY SWAFFORD HQ OPS Officer: PETE SNYDER	Notification Date: 04/07/2010 Notification Time: 20:28 [ET] Event Date: 04/07/2010 Event Time: 16:10 [CDT] Last Update Date: 04/07/2010
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION	Person (Organization): JAY HENSON (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
3	N	N	0	Startup	0	Startup

Event Text

SPILL OF WATER CONTAINING TRITIUM

"Browns Ferry Nuclear Plant (BFN) is notifying state and local agencies of a spill of water containing tritium as specified in section 2.2.a.iii, of Nuclear Energy Institute document NEI 07-07 entitled 'Industry Groundwater Protection Initiative.' On April 7, 2010 from 02:30 to 03:00, BFN operations personnel were transferring water from one Condensate Storage Tank (CST 3) to another Condensate Storage Tank (CST 5). At 08:25, an operator conducting rounds noticed water flowing from an open test valve near the top of CST 5. The estimated flow rate from the test valve was approximately two gallons per minute (gpm). Attempts to isolate the open test valve by plant operations personnel were unsuccessful. Plant operations personnel lowered level in CST 5 and water flowing from the test valve stopped at 10:35.

"The volume of water spilled to ground is estimated to be approximately 1,000 gallons. At 16:10, laboratory analysis results indicated this water contained 2.05 E-03 uCi/ml tritium. Mitigative actions will be developed and implemented. BFN Procedure: SPP 5.14 requires that state and local agencies be notified within one business day of verification of a discovery when: ' the spill or leak has or can potentially migrate to groundwater: 1. An unmonitored and inadvertent contaminated leak or spill of liquids of unknown volume and reasonably determined to be greater than 100 gallons to the environment occurs '

"This event is reportable as a 4-hour non-emergency notification report in accordance with 10 CFR 50.72(b)(2)(xi), 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.'"

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 45821
Facility: SALEM Region: 1 State: NJ Unit: [ ] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: MATTHEW MOG HQ OPS Officer: PETE SNYDER	Notification Date: 04/07/2010 Notification Time: 21:11 [ET] Event Date: 04/06/2010 Event Time: 08:30 [EDT] Last Update Date: 04/07/2010
Emergency Class: NON EMERGENCY 10 CFR Section: INFORMATION ONLY	Person (Organization): JAMES TRAPP (R1DO)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
2	N	Y	86	Power Operation	86	Power Operation

Event Text

STORM DRAIN SYSTEM TESTED POSITIVE FOR TRITIUM

"On 4/06/10, Salem management was notified that samples taken from the Salem Unit 2 north storm drain system were positive for tritium. Two storm drain catch basin sample results were confirmed above 1 million pico Curies per liter. The affected area of the north storm drain system has been isolated. Samples upstream of the river outfall were less than the minimum detectable level for tritium.

"NRC reporting criteria were reviewed and, although no direct reportable criteria were met, based on the public sensitivity to tritium issues, it was determined that a voluntary notification to the NRC was prudent.

"Salem is taking action to mitigate, locate, and remediate the source of the tritium. In addition to isolating the affected portion of the system, the station has increased the sample frequency for the storm drain system and ground water wells in the affected area.

"A voluntary notification has been made to the appropriate State agency and the NRC Resident Inspector."

Page Last Reviewed/Updated Thursday, March 25, 2021