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Event Notification Report for February 22, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/18/2011 - 02/22/2011

** EVENT NUMBERS **


46617 46622 46623 46624 46625 46626 46627 46628 46629 46630 46631 46633

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Agreement State Event Number: 46617
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UT SOUTHWESTERN MEDICAL CENTER
Region: 4
City: DALLAS State: TX
County:
License #: LO 0279
Agreement: Y
Docket:
NRC Notified By: DANNY JISHA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/15/2011
Notification Time: 19:22 [ET]
Event Date: 02/15/2011
Event Time: 16:30 [CST]
Last Update Date: 02/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
DUNCAN WHITE (FSME)

Event Text

AGREEMENT STATE REPORT - POSSIBLE MEDICAL EVENT DUE TO MISADMINISTRATION

This is a preliminary report. Details will be provided at a later date.

During a general chart review, the licensee discovered that two pediatric patients were administered doses of P-32 albumin that appear to be in excess of 100% of the prescribed doses. The first event occurred approximately four months ago. The second event occurred approximately two months ago. These events may have each provided 1000 Rads excess dose to target tissue. The events may or may not involve a dispensing error. The doses were administered to tissue surrounding extremity joints of the two pediatric patients.

Physicians do not expect any patient impact or unfavorable outcome from these misadministration.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Agreement State Event Number: 46622
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: RMA GROUP
Region: 4
City: RANCHO CUCAMONGA State: CA
County:
License #: 2700-36
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: VINCE KLCO
Notification Date: 02/17/2011
Notification Time: 20:16 [ET]
Event Date: 02/16/2011
Event Time: [PST]
Last Update Date: 02/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
DUNCAN WHITE (FSME)
ILTAB VIA EMAIL ()
MEXICO VIA FAX ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE SOURCE

The following information was received by email:

"On February 16, 2011, RHB [California Radiologic Health Branch] South RM [Radiologic Materials] was contacted by the [licensee] RSO [Radiation Safety Officer] of RMA Group, concerning a loss of the Cs-137 source from a Troxler model 3430 (S/N 25220) moisture density gauge (8 mCi Cs-137, SN 758021, 40 mCi Am:Be-241, SN 4721490). [The licensee RSO] stated that the Troxler gauge was in use at a construction site located at the on/off ramp of Interstate 10 at North Indian Canyon Drive, near Palm Springs in early February (sometime between Feb. 3 and Feb. 8, 2011). [The licensee RSO] stated that operator noticed that the readings taken had dropped significantly from his previous readings and thought that the computer in the gauge had malfunctioned and the gauge was returned to their facility and stored until it was taken in for service at Southwest Calibration and Training LN 7567 (SWCT) on February 14 or 15. On the afternoon of February 16, 2011, [The licensee RSO] was contacted by SWCT that the Cs-137 source pellets were missing due to the cap of the source capsule breaking off at the weld. [The licensee RSO] stated that Troxler service was consulted and that they were informed that this was an issue that had occurred twice previously in the past 6 years and that they had requested that the source rod be returned to them to allow them to determine how the break had occurred.

"[The licensee RSO] stated that he had been given a survey meter to be used to attempt to find the source. [The licensee RSO] stated that a survey of the storage area of their Rancho Cucamonga facility (all of the other gauges were out being used at the time) and the vehicle used to transport the gauge when the incident was likely to have occurred and did not find the source. [The licensee RSO] stated that he would attempt to find the sources at the construction site in the morning when he had determined the area that the gauge was in use when the incident occurred. [The licensee RSO] stated that the source may have already been buried under 10 inches of fill (soil) and 8-10 inches of asphalt, but he was not absolutely sure. [The licensee RSO] was informed that a 30 day report was required to be submitted to [the RHB] office.

"On February 17, 2011, [RHB] confirmed that the damaged gauge had never had any incidents or trauma that potentially could have resulted in damage to the source capsule and that the construction site was on N. Indian Canyon Drive at one of the on/off ramps to Interstate 10. The results of the search for the missing source and a confirmation of the exact location of the incident will be forwarded to NMED when the RSO has confirmed the information. An investigation into the cause of the damage of the source capsule and possible location of the source capsule is ongoing."

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Power Reactor Event Number: 46623
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES MORGAN
HQ OPS Officer: PETE SNYDER
Notification Date: 02/18/2011
Notification Time: 02:31 [ET]
Event Date: 02/18/2011
Event Time: 00:51 [EST]
Last Update Date: 02/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MARC FERDAS (R1DO)

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

Event Text

INACTIVE LEAK IDENTIFIED ON PRESURIZER HEATER WELL

"During a scheduled VT-2 boric acid examination on the Unit 2 Pressurizer lower level heater penetrations a boric acid leak was identified on heater penetration N-3."

The licensee characterized the leak as inactive. The approximate sizes of the round boric acid deposits are 1/32 inch and 1/64 inch. The licensee continues to investigate and plan recovery actions.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46624
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: KEVIN McLAUGHLIN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/18/2011
Notification Time: 09:00 [ET]
Event Date: 12/29/2010
Event Time: [EST]
Last Update Date: 02/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MARC FERDAS (R1DO)

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

INVALID SYSTEM ACTUATION DUE TO OPERATOR ERROR

"This report is being made per paragraphs 50.73(a)(1) and 50.73(a)(2)(iv)(A) to address an actuation of Emergency Diesel Generator 'A' on 12/29/10 while performing a Diesel Generator shutdown. Emergency AC Electrical Power system including Emergency Diesel Generators is a system named in 50.73(a)(2)(iv)(6).

"Emergency Diesel Generator 'A' was coasting down following a normal shutdown in accordance with steps in a routine surveillance test procedure. A manual reset was performed prior to verification that the generator had stopped rolling causing it to return to idle speed and continue to run. A procedure compliance error occurred during the conduct of the test. The control room individual did not request verification that the diesel generator had stopped rolling prior to pushing the reset pushbuttons. This is considered an INVALID signal with respect to 50.73(a)(2)(iv)(A). However the system was not fully removed from service [i.e. the diesel was not considered to be in a testing mode at the time of the event]. The re-start only affected Emergency Diesel Generator 'A'.

"Specific information required per NUREG-1022:
"a. The specific train(s) and system(s) that were actuated: The specific train(s) .and system(s) was Emergency Diesel Generator 'A'. The 'B' train was not affected by this event.
"b. Whether each train actuation was complete or partial: The actuation was considered complete (i.e. all necessary components responded to the reset signal as expected under the actual field conditions).
"c. Whether or not the system started and functioned successfully: Emergency Diesel Generator 'A' started and operated successfully until secured by Operations personnel.

"The licensee notified the NRC Resident Inspector."

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Power Reactor Event Number: 46625
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ALEX IBARRA
HQ OPS Officer: VINCE KLCO
Notification Date: 02/18/2011
Notification Time: 12:16 [ET]
Event Date: 02/18/2011
Event Time: 10:45 [CST]
Last Update Date: 02/18/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
VINCENT GADDY (R4DO)
ERIC LEEDS (NRR)
ELMO COLLINS (R4)
WILLIAM GOTT (IRD)
KNOX (DHS)
BLANKENSHIP (FEMA)

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

UNUSUAL EVENT- EXCESSIVE LEAKAGE FROM A CHARGING SYSTEM

At 1045 CST, on 2/18/11, Comanche Peak Unit 1 declared an Unusual Event related to excessive leakage from the charging system. The 40 GPM leakage was in excess of the specified limit of 25 GPM. At 1121 CST, the charging system leakage was verified isolated. Unit 1 is in stable condition and remains at 100% power. No offsite assistance is required at this time.

* * * UPDATE FROM TERRY MARSH TO DONG PARK AT 1438 EST ON 2/18/11 * * *

"At 1311 EST, Comanche Peak Nuclear Power Plant has terminated the Unusual Event. The leaking valve in the charging system has been isolated reducing the leakage to zero. Repairs to the valve are in planning."

The licensee notified the NRC Resident Inspector. The licensee notified the Texas Department of Public Safety and will be making a press release to the local press.

Notified R4DO (Gaddy), IRD (Gott), NRR EO (Thorp), DHS (McDonald) and FEMA (Via).

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Power Reactor Event Number: 46626
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GREG ELKINS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/19/2011
Notification Time: 06:10 [ET]
Event Date: 02/19/2011
Event Time: 00:50 [EST]
Last Update Date: 02/19/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (R1DO)

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

SAFETY PARAMETER DISPLAY SYSTEM INOPERABLE DUE TO PLANT COMPUTER PROBLEM

"At 1650 EST on Friday, February 18, 2011 , the Unit 1 Plant Process Computer was taken out of service for a planned outage for pre-modification testing. The Process Computer was successfully restarted at 0040 on Saturday, February 19, and all Computer functions were operational. However, at 0058, the Unit 1 Control Room received the annunciator for the Process Computer trouble. At the same time, all Process Computer displays stopped updating, including Safety Parameter Display System SPDS.

"All Control Room panel indicators and annunciators continued to respond properly providing operators with non-computer based emergency assessment capability. An additional Plant Operator was called out in accordance with Technical Specification 6.2.2.a for minimum shift complement with the process computer out of service.

"Repairs were completed and the Plant Process Computer was returned to service at 0450 on February 19, 2011."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46627
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: NATE DEMASTER
HQ OPS Officer: VINCE KLCO
Notification Date: 02/19/2011
Notification Time: 22:24 [ET]
Event Date: 02/19/2011
Event Time: 19:20 [EST]
Last Update Date: 02/19/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
LAURA KOZAK (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

OFFSITE NOTIFIECTION DUE TO INADVERTENT CHEMICAL DISCHARGE

"At 1920 [EST] on 2-19-11, a chemistry technician notified the Shift Manager that more than the expected amount of Sodium Bisulfite was inadvertently added to the Circulating Water System discharge. The Spill Prevention Control & Countermeasures (SPCC) Plan was referenced for required actions. 17 additional gallons of Sodium Bisulfite was discharged to surface waters of Lake Michigan. This amount of Sodium Bisulfite is less than the reportable quantity of 417 gallons per the SPCC Plan. However, since it was released to surface water (Lake Michigan), a notification to the District Water Quality Division (DWQD) was made at 2020 [EST] by the site's Senior Environmental Specialist (SES). The DWQD requested that additional notifications be made to state (Pollution Emergency Alert System - PEAS) and local (911 operator) agencies. PEAS was notified at 2020 [EST] by the SES and Van Buren County dispatch (911) was notified by the Control Room staff at 2047 [EST]."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46628
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVE NOYES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/20/2011
Notification Time: 00:55 [ET]
Event Date: 02/20/2011
Event Time: 00:00 [EST]
Last Update Date: 02/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
MARC FERDAS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 60 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN-REACTOR BUILDING CLOSED COOLING WATER TRAIN INOPERABLE

"At 0000 hours on Sunday, February 20, 2011, the Pilgrim Nuclear Power Station (PNPS) commenced a controlled shutdown of the reactor due to the 'B' train of Reactor Building Closed Cooling Water (RBCCW) being declared inoperable at 1250 hours on February 18, 2011 and expected to exceed its 72-hour Limiting Condition for Operability (LCO) as required by TS prior to return to operable status.

"With the plant operating at 100% power, leakage of Salt Service Water (SSW) was detected in the RBCCW system due to high chloride levels and increased inventory in the system. An investigation into the event determined that the source of the SSW was isolated to the 'B' RBCCW heat exchanger which is designed to cool RBCCW under normal and post-accident conditions. The quantity of the leakage was determined to exceed the design limits established to ensure post-accident operation of the system and the 'B' train of RBCCW was subsequently declared inoperable.

"The leak identification and repair activities are expected to exceed the TS LCO for the RBCCW system and therefore a controlled shutdown of the reactor was initiated.

"This event had no impact on the health and/or safety of the public.

"The licensee has notified the NRC Senior Resident Inspector.

"This 4-hour notification is being made in accordance with 10 CFR 50.72 (b)(2)(i)."

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Power Reactor Event Number: 46629
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN WALKOWIAK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/20/2011
Notification Time: 10:47 [ET]
Event Date: 02/20/2011
Event Time: 08:53 [EST]
Last Update Date: 02/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (R1DO)

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

TONE ALERT RADIO EMERGENCY NOTIFICATION SYSTEM OUT OF SERVICE

The licensee has been notified by Oswego County Emergency Management that the Tone Alert Radio Emergency Notification System had been out of service since 0853 EST and is still out of service at this time.

The County Alert Sirens which also function as part of the Public Prompt Notification System remain operable.

Compensatory measures have been verified to be available should the Prompt Notification System be needed.

The licensee has notified the State and the NRC Resident Inspector.

* * * UPDATE FROM JOHN WALKOWIAK TO VINCE KLCO ON 2/20/2011 @ 1228 * * *

At 1129 [EST], Fitzpatrick was notified by Oswego County Emergency Management that the Tone Alert Radio Emergency Notification System was restored to service at 1124 [EST] on 2/20/2011.

The licensee notified the State and the NRC Resident Inspector.

Notified the R1DO (Ferdas).

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Power Reactor Event Number: 46630
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DON SHEEHAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/20/2011
Notification Time: 12:02 [ET]
Event Date: 02/20/2011
Event Time: 08:53 [EST]
Last Update Date: 02/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

TONE ALERT RADIO EMERGENCY NOTIFICATION SYSTEM OUT OF SERVICE

"On Sunday, February 20, 2011, at 1007 EST, James A. Fitzpatrick (JAF) Nuclear Station Shift Manager (SM), John Walkowiak, notified Nine Mile Point [NMP], and NYS Warning Point, via the RECS Line, of a loss of the Tone Alert System for greater than one hour from the National Weather Service as of 0853 [EST]. Site Emergency Procedures define a loss of Tone Alert System for greater than one hour, as a significant loss of Emergency Communications (EPIP-EPP-30).

"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) Population for the NMP and JAF Nuclear Power Plants. This failure meets NRC 8-Hour reporting criteria 10 CFR 50.72(b)(3)(xiii).

"The County Alert Sirens, which also function as part of the Public Prompt Notification System, remained operable.

"The loss of the Tone Alert System constitutes a significant loss of Emergency Off-Site Communications capability. Compensatory measures were verified to be available should the Prompt Notification System be needed. This consists of utilizing the hyper-reach system, which is a reverse 911 feature available from the county 911 center. Local law enforcement personnel are also available for 'Route Alerting' of the affected areas of the EPZ.

"As of 1124 hours on February 20, 2011, Nine Mile Point was notified by the Oswego County 911 Center that the Tone Alert System has been returned to service."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46631
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/20/2011
Notification Time: 17:47 [ET]
Event Date: 02/20/2011
Event Time: 10:34 [EST]
Last Update Date: 02/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARC FERDAS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A N 0 Hot Shutdown 0 Hot Shutdown

Event Text

REACTOR PROTECTION SYSTEM ACTUATION WHILE SHUTDOWN

"On Sunday, February 20, 2011, at 1034 EST with the reactor shutdown and all control rods fully inserted a valid Reactor Protection System (RPS) low reactor water initiation signal (+12 inch) was received. The RPS actuation signal resulted in reactor scram and actuation of the Primary Containment Isolation Systems for Group II - Primary Containment Isolation and Reactor Building Isolation System (RBIS), and Group VI - Reactor Water Cleanup System (RWCU). At the time of the event, a controlled reactor shutdown and cooldown was in progress. The Reactor Mode Selector Switch was in 'Startup' and a cooldown was being controlled using the Mechanical Hydraulic Control (MHC) System. Initial event review indicates that the turbine by-pass valve controlling the cooldown closed causing a 'shrink' on indicated reactor water level to briefly lower to +12 inches (lowest observed water level).

"Reactor water level was immediately restored, the isolations (Group II and VI) were reset, and the RPS signal was reset at 1135 EST. All systems operated as expected, in accordance with design.

"This event had no impact on the health and/or safety of the public.

"The US NRC Senior Resident Inspector was in the Main Control Room at the time of the event."

The licensee will be notifying the State.

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Power Reactor Event Number: 46633
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRADFORD ROBINSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/22/2011
Notification Time: 02:23 [ET]
Event Date: 02/21/2011
Event Time: 20:01 [MST]
Last Update Date: 02/22/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
VINCENT GADDY (R4DO)
FREDERICK BROWN (NRR)

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

Event Text

AUTO START AND LOAD OF EDGs ON UNITS 1&3 FOLLOWING LOSS OF START-UP TRANSFORMER

"On February 21, 2011, at approximately 2001 Mountain Standard Time (MST) a valid actuation of the Palo Verde Nuclear Generating Station Unit 1 Train 'B' Emergency Diesel Generator (EDG) and Unit 3 Train 'A' Emergency Diesel Generator occurred as a result of undervoltage on their respective safety buses. Both EDGs started and loaded as designed to energize the respective safety buses. No Emergency Plan declaration was made and none was required.

"The loss of power to the Unit 1 and Unit 3 safety buses was the result of protective relay actuations on the A-E-NANX02 Startup Transformer which deenergized the transformer and the Unit 1 13.8KV Intermediate Bus 1-E-NAN-S06 and the Unit 3 13.8KV Intermediate Bus 3-E-NAN-SOS. The affected intermediate buses provide power to the Unit 1 safety bus 1-E-PBB-S04 and the Unit 3 safety bus 3-E-PBA-S03 respectively. The Auxiliary Operators responded to inspect the Startup Transformer and affected buses and determined that there was no fire or smoke and no obvious equipment damage to transformers or associated 13.8 KV Buses. At the time of the actuations, the Unit 1 Control Room received alarms for Startup Transformer A-E-NAN-X02 'Phase, Winding Ground Differential Trip'.

"Subsequent inspection by the Electricians identified damage to the cabling from the 'Y' winding of A-E-NAN-X02 Start-Up Transformer to the alternate supply breaker on Unit 2 Intermediate Bus 2-E-NAN-SOS. Unit 1 and Unit 3 entered Technical Specification LCO 3.8.1, Condition 'A', for one (of two) required offsite circuits inoperable. Unit 2 currently has the 'B' EDG out of service for a planned maintenance outage and the Unit 2 safety buses and required offsite circuits were unaffected by the Startup Transformer trip. Unit 2 safety buses are being supplied by Startup Transformers A-E-NAN-X01 and A-E-NAN-X03.

"Both Unit 1 and Unit 3 were at approximately 100% power, at normal operating temperature and pressure prior to and following the EDG actuations. No other ESF actuations occurred and none were required. No major equipment was inoperable prior to the event that contributed to the event.

"The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.

"The NRC Resident Inspector has been notified of the ESF actuations and this ENS notification."

The licensee is working to restore normal electrical power to the affected safety buses from alternate available sources on Startup Transformers X01 and X03. The licensee stated that no significant non-safety related equipment has been deenergized. The licensee noted that while the cause of the damaged cabling noted in the above report is still under investigation, water intrusion repairs were recently conducted near the location where the current damages were found.

* * * UPDATE AT 0356 EST ON 2/22/11 FROM ROBINSON TO HUFFMAN * * *

The licensee has restored offsite power to the affected safety buses. The Unit 3 safety bus was restored from Startup Transformer X03 at 0106 MST. The Unit 1 safety bus was restored from Startup Transformer X01 at 0153 MST. The EDGs are in the process of being shutdown and reset. The LCO for required offsite power source to the buses has been exited.

R4DO (Gaddy) notified.

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