United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for April 3, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/02/2012 - 04/03/2012

** EVENT NUMBERS **


47693 47779 47795 47797 47798 47799 47800

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Part 21 Event Number: 47693
Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DUYEN PHAM
HQ OPS Officer: VINCE KLCO
Notification Date: 02/23/2012
Notification Time: 11:08 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 04/02/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MEL GRAY (R1DO)
MIKE ERNSTES (R2DO)
PATTY PELKE (R3DO)
RICK DEESE (R4DO)
PART 21 GRP - EMAIL ()

Event Text

PART 21 REPORT - ROSEMOUNT PRESSURE TRANSMITTERS WITH NONZERO BASED CALIBRATIONS

The following information was received by facsimile:

"During the course of qualification testing to replace certain diodes identified for obsolescence, RNII [Rosemount Nuclear Instruments, Inc.] has determined that Model 1154 Series H range code 4-8 pressure transmitters with a significantly elevated or suppressed 4 mA point may not meet the published steam pressure/temperature accuracy specification.

"The out of tolerance condition observed during steam pressure/temperature qualification testing is not related to the replacement diode changes. It is an inherent performance characteristic related to large zero elevation or suppression. The steam pressure/temperature accuracy specification will be revised to account for nonzero based calibrations with a significantly elevated or suppressed 4 mA point.

"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification.

"RNII recommends that users review the application where 1154 Series H range code 4-8 pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature specification."

Rosemount Nuclear has provided instruments to the following list of domestic U.S. customers: Alabama Power; American Electric Power; Arizona Public Service/Pinnacle West; Bechtel Power; Constellation Energy; Dominion Nuclear Connecticut/Dominion Generation; Duke Energy; ECFS MCS; Edison Material Supply; Electro Mechanics; Entergy; Exelon Generation; Florida Power and Light; FPL Energy; Georgia Power; Northern States Power-Minnesota DBA XCEL Energy; Pacific Gas and Electric; Progress Energy Florida; Progress Energy Carolinas; PSEG Nuclear; South Carolina Electric and Gas; Southern California Edison; Southern Nuclear Operating Company; STP Nuclear Operating; Tennessee Valley Authority; TXU/Luminant; Westinghouse Electric.

* * * UPDATE FROM DUYEN PHAM TO PETE SNYDER ON 4/2/12 AT 1224 EDT * * *

The following information was received by facsimile:

"This revision only affects Section 4.0 of the 23 February 2012 notification letter. The pressure values listed in Section 4.0 at 8 hours and 56 hours have been corrected. No other changes have been made."

Notified R1DO(Caruso), R2DO(Lesser), R3DO(Dickson), R4DO(Haire) and Part 21 Group via email.

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Agreement State Event Number: 47779
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: WOOD RIVER REFINERY
Region: 3
City: ROXANA State: IL
County:
License #: IL-01282-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/28/2012
Notification Time: 10:57 [ET]
Event Date: 03/26/2012
Event Time: [CDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BILLY DICKSON (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

ILLINOIS AGREEMENT STATE REPORT - SHUTTER MECHANISM FAILURE

The following information was obtained from the State of Illinois via email:

"The Radiation Safety Office for the licensee reported a second device at their facility had a shutter mechanism failure. The shutter was found stuck in the open position on March 26, 2012 during continuation of their routine maintenance check and survey. The gauge is near the top floor of a coker drum away from any routinely occupied work station. The device/area has been posted with appropriate warning notices. Measured radiation levels appear normal for this type of device with the shutter open. There are two other gauges on this vessel which are operating normally. Operators in the area have been informed of the situation and vessel access is prohibited. The area is subject to high humidity and rust build up is the suspected cause of the shutter failure. In the past, the manufacturer has recommended covers for these devices but none are available. The licensee's consultant and the vendor have been called. Both will be on-site again on March 30, 2012 as previously arranged to service a similar other device that failed last week. They will investigate this recent failure at that time."

The gauge is an Ohmart Corp. model number SHLG-2, serial number 2605CN and contains a 5 Ci Cs-137 source.

The previous failure was reported under NRC EN# 47759.

Illinois Item Number: IL12006

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Power Reactor Event Number: 47795
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/02/2012
Notification Time: 11:45 [ET]
Event Date: 04/02/2012
Event Time: 06:24 [EDT]
Last Update Date: 04/02/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
MARK LESSER (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 N 0 Refueling 0 Refueling

Event Text

INFORMATION ONLY - FIRE IN PLANT VITAL BATTERY ROOM AREA

"At 0624 EDT on 04/02/2012 the control room was notified by a plant operator that there was a fire in the plant vital battery room area on Unit 2. The fire was located in the lower compartment of inverter 2KUI. This equipment supplies power to 120V AC non-safety related components. The fire brigade captain was dispatched along with the site fire brigade. When the fire brigade captain arrived the operator was staged near the inverter with a CO2 [carbon dioxide] fire extinguisher. The fire brigade captain instructed the NLO [non-licensed operator] to extinguish the fire with the extinguisher. The fire was immediately extinguished once the CO2 was applied from the extinguisher. At 0633 EDT the fire brigade captain reported to the control room that the fire was extinguished. Upon further investigation it appears that transformer in the lower compartment of the inverter had caught fire. The fire was confined to the lower compartment of the inverter and did not affect any other components in the area. Due to the loss of the inverter the loads automatically swapped to the alternate AC source as designed and no indications or equipment were lost due to the loss of the inverter.

"At the time of this event Unit 1 was at 100% power and Unit 2 was shutdown in Mode 6 with reactor coolant system drained to 8% level with 2B Residual Heat Removal pump supplying core cooling. There was no impact to either unit as a result of this event. All equipment required to maintain core cooling, AC and DC power, and reactor coolant inventory on Unit 2 was maintained during this event."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47797
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOSE VASQUEZ
HQ OPS Officer: PETE SNYDER
Notification Date: 04/02/2012
Notification Time: 20:40 [ET]
Event Date: 04/02/2012
Event Time: 19:33 [EDT]
Last Update Date: 04/02/2012
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
MARK LESSER (R2DO)
TIM McGINTY (NRR)
VICTOR MCCREE (R2)
DAN DORMAN (NRR)
WILLIAM GOTT (IRD)

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

Event Text

UNUSUAL EVENT - FIRE FROM HYDROGEN SUPPLY TO VOLUME CONTROL TANK

"At 1933 EDT on 4/2/12, a fire was discovered on top of the Auxiliary Building Roof coming from a one inch hydrogen supply header to the U-3 Volume Control Tank.

"At 1948 EDT [Turkey Point] declared an Unusual Event due to a fire greater than 15 minutes in the protected area (HU2).

"At 1949 EDT [operators] closed the hydrogen isolation valve and hydrogen header pressure began to lower.

"At 1956 EDT a second isolation valve was closed. Header pressure continued to lower.

"At 2018 EDT the fire is out. No damage to plant equipment or adverse effect to safe shutdown systems. [Turkey Point] is currently working on a de-escalation process."

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

Notified DHS SWO, FEMA, NICC and Nuclear SSA.

* * * UPDATE FROM JOSE VASQUEZ TO PETE SNYDER T 2139 EDT ON 4/2/12 * * *

After the fire was out the pipe became cool to the touch. At 2110 EDT Turkey Point terminated the Unusual Event for Unit 3.

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

Notified DHS SWO, FEMA, NICC and Nuclear SSA via email.

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Power Reactor Event Number: 47798
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: PETE SNYDER
Notification Date: 04/02/2012
Notification Time: 22:56 [ET]
Event Date: 04/02/2012
Event Time: 15:11 [CDT]
Last Update Date: 04/02/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARK HAIRE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

AUTOSTART OF DIVISION 3 DIESEL GENERATOR FOLLOWING 4160 VOLT LINE OUTAGE

"On 4/2/12 at 1511 [CDT], GGNS [Grand Gulf Nuclear Generating Station] received a valid ESF actuation for emergency AC power to Division 3 4160V bus due to degraded voltage.

"One of the two 500KV offsite feeders (Tech Spec Offsite Power Source) tripped causing a drop in grid voltage which resulted in a trip of the ESF feeder breaker for 4160 Volt Division 3 bus. The HPCS (High Pressure Core Spray) Diesel Generator automatically started and energized the bus. The HPCS system was not running and no ECCS initiation occurred during this event. The plant was in Mode 5 with RHR A in shutdown cooling. Divisions 1 and 2 ESF power monitoring instrumentation responded to the grid voltage transient but no actuation setpoints were reached. Division 1 and 2 ESF 4160V buses remained energized and shutdown cooling remained in service. The 500KV offsite feeder (Tech Spec Offsite Power Source) and additional 115 KV feeder (Tech Spec Offsite Power Source) remained in service. The 500KV feeder that tripped was restored by the dispatcher at approximately 1515 CDT. The Division 3 bus was subsequently transferred back to offsite power and the HPCS Diesel Generator was secured. This event is reportable per 10 CFR 50.72(b)(3)(iv).

"A lightning strike resulted in a voltage transient on the GGNS electrical distribution system. Due to this transient, the 'A' Control Room Air Conditioning Unit (CRAC 'A') tripped and had to be manually restarted. CRAC 'A' was not running for approximately two minutes. During this timeframe CRAC 'B' was tagged out of service. This was evaluated and determined to not be a loss of safety function."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 47799
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: BRIAN MAGNUSON
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/02/2012
Notification Time: 23:32 [ET]
Event Date: 04/02/2012
Event Time: 14:52 [CDT]
Last Update Date: 04/02/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BILLY DICKSON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 90 Power Operation

Event Text

INITIATION OF REACTOR SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS (TS) 3.8.1.F

"On April 2, 2012, at 1452 hours, Unit 1 received Panel 901-8 A7 U1 Emergency Diesel Generator (EDG) Trouble alarm. Equipment Operators were dispatched and the Unit 1 EDG was found running unloaded, without a generator field flash, and no auto start signal received. Troubleshooting identified that a 125 VDC ground had caused the Unit 1 EDG to start. As a result, the Unit 1 EDG was declared inoperable.

"At this time Unit 2 is in a refueling outage and the Unit 2 EDG is currently inoperable for repairs. Due to the inoperability of the Unit 1 and Unit 2 EDGs, at 2000 hours a Reactor Shutdown was initiated on Unit 1 in accordance with TS 3.8.1.F.

"In addition, since the EDGs supply emergency power to both Unit's Standby Gas Treatment Systems (SBGTS), emergency power was unavailable to SBGTS; however, normal power supplies remained available.

"This notification is being made in accordance with 10 CFR 50.72(b)(2)(i), and in accordance with 10 CFR 50.72(b)(3)(v)(D).

"At 2151 hours, the Unit 1 EDG was declared operable following repairs and successful operability testing."

The NRC Resident Inspector has been informed.

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Power Reactor Event Number: 47800
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/03/2012
Notification Time: 05:57 [ET]
Event Date: 04/03/2012
Event Time: 05:24 [EDT]
Last Update Date: 04/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (R3DO)

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

Event Text

SPDS AND ERDS REMOVED FROM SERVICE FOR PLANNED MAINTENACE

"On 4/03/12 at 0524 EDT, Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 80 hours. During this time, the majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 5, and will remain in Mode 5, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10 CFR 50.72(b)(3)(xiii).

"Follow up notification will be made when SPDS and ERDS have been restored."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, April 03, 2012
Tuesday, April 03, 2012