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Event Notification Report for December 20, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/17/2010 - 12/20/2010

** EVENT NUMBERS **


46358 46368 46392 46476 46479 46486 46487 46488 46490 46491 46492 46493

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46358
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JIM KEPLEY
HQ OPS Officer: JOE O'HARA
Notification Date: 10/24/2010
Notification Time: 17:19 [ET]
Event Date: 10/24/2010
Event Time: 12:34 [EDT]
Last Update Date: 12/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
MARIE MILLER (R1DO)

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

Event Text

'A' TRAIN RHR INOPERABLE DUE TO TEMPERATURE SWITCH FAILURE ON 'A' CONTROL ROOM CHILLER

"On 10/24/2010, while in Mode 5 in natural circulation cooling and no fuel movement in progress, the 'A' Control Room Chiller (AK400) tripped apparently due to an equipment failure of a temperature switch. This system was providing cooling for the Safety Auxiliaries Cooling System (SACS) room coolers. This caused the 'A' train of SACS and 'A' Train of Residual Heat Removal (RHR) to be administratively declared inoperable with the remaining train out of service for maintenance. As a result of the inoperable systems, the ability to remove residual heat could have been prevented. The 'A' RHR train, the alternate 'C' RHR train and the 'A' SACS Loop remained continuously available. No personnel were injured."

The licensee is in Technical Specification 3.9.11.1 Shutdown Cooling and 3.8.1.2 for SACS inoperable. The Emergency Diesel Generators (EDG) are available but inoperable as a result of SACS being inoperable. Offsite power is not affected and plant risk remains 'Green'. There were no significant events on-going at the time of the event. The licensee is bench testing a replacement switch at this time, and the chiller has been returned to service. The licensee is maintaining natural circulation and ensuring the availability of redundant RHR once a shift.

The NRC Resident Inspector and Lower Alloyways Township have been notified.

* * * RETRACTION FROM J.R. TRAUTVETTER TO J. KNOKE AT 1015 EST ON 12/17/10 * * *

Licensee is retracting this event based on the following:

"Hope Creek Technical Specification 3.9.11 action statement (a) for no OPERABLE RHR loops is to demonstrate the operability of at least one alternate method of decay heat removal within one hour and once per 24 hours thereafter. Prior to and throughout the event, decay heat, removal was maintained via the Fuel Pooling Cooling system through the available heat exchangers with core circulation maintained by natural circulation. Use of the Fuel Pool Cooling for decay heat removal is recognized in station procedures as an alternate method of decay heat removal in technical specification action statement (TSAS) 3.9.11. This retraction is to clarify that the inoperable systems did not prevent the ability to remove residual heat. The outage risk assessment remained Green throughout the period that both RHR loops were inoperable.

"There was no loss of safety function, and therefore, the event is not reportable as an event that prevents the fulfillment of a safety function in accordance with 50.72 (b)(3)(v)(B)."

Notified the R1DO (Daniel Holody)

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46368
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: AARON CHLADIL
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/27/2010
Notification Time: 17:05 [ET]
Event Date: 10/27/2010
Event Time: 12:22 [CDT]
Last Update Date: 12/17/2010
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):
DAVID PROULX (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 81 Power Operation

Event Text

UNIT COMMENCED SHUTDOWN AFTER DECLARING CONTAINMENT SPRAY INOPERABLE

"During pressure drop testing of the backup nitrogen supply for HCV-345 (Containment Spray Header isolation valve) the accumulator failed its test. This renders HCV-345 inoperable. HCV-344 the opposite header isolation valve also has an air leak that appears to be of similar magnitude to the leak on HCV-345. Fort Calhoun Station is conservatively considering both valves inoperable and has entered technical specification 2.0.1 which requires shutting the plant down to hot standby within 6 hours. The plant shutdown began at 1513 CDT. Repair efforts are underway on HCV-345 and HCV-344."

The leakage on both valves was identified by systems engineering during testing.

The licensee informed the NRC Resident Inspector.

* * * UPDATE AT 1756 EDT ON 10/27/10 FROM AARON CHLADIL TO S. SANDIN * * *

At 1647 CDT, the licensee exited technical specification 2.0.1 after declaring HCV-344 operable. The Unit is currently at 74% power. The licensee will stabilize power at 70% and then commence power escalation.

The licensee informed the NRC Resident Inspector.

Notified R4DO (Proulx).

* * * RETRACTION FROM ERICK MATZKE TO HOWIE CROUCH AT 1155 EST ON 12/17/10 * * *

"Following the original notification, the Fort Calhoun Station reviewed and reanalyzed the acceptance criteria for the subject valve air accumulators. The analysis determined that the valves had been and were operable during the event. Therefore, the report under 10CFR50.72(b)(3)(v)(D) is being retracted."

The licensee has notified the NRC Resident Inspector. Notified R4D0 (Howell).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46392
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/04/2010
Notification Time: 03:05 [ET]
Event Date: 11/04/2010
Event Time: 01:23 [EDT]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
JOHN WHITE (R1DO)

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

CHARGING PUMP '23' DECLARED INOPERABLE DURING SURVEILLANCE TESTING

"On November 4, 2010 at 0123 [EDT], '23' Charging Pump was declared inoperable due to not meeting required test parameters during surveillance testing. '23' Charging Pump is required for remote shutdown per Technical Specification 3.3.4, Remote Shutdown, and is a single component system intended to perform the inventory control safety function. Since '23' Charging Pump has been declared inoperable, a loss of safely function has occurred and is reportable per 10CFR50.72 (b)(3)(v)(A).

"The cause of the inoperability is under investigation. Per Technical Specification 3.3.4, Remote Shutdown, '23' Charging Pump must be restored to operable status within 30 days."

The licensee will inform the NY State PSC (Public Service Commission) and the NRC Resident Inspector.

* * * RETRACTION FROM CHARLES ROKES TO DONG PARK AT 1028 EST ON 12/20/10 * * *


The licensee notified the NRC Resident Inspector.

The R1DO (Perry) was notified.

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General Information or Other Event Number: 46476
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: OUR LADY OF BELLEFONTE HOSPITAL
Region: 1
City: ASHLAND State: KY
County:
License #: 202-144-26
Agreement: Y
Docket:
NRC Notified By: MICHELE GREENWELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/13/2010
Notification Time: 15:51 [ET]
Event Date: 03/10/2008
Event Time: [CST]
Last Update Date: 12/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
DIANA DIAZ-TORO (FSME)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT - PATIENT RECEIVED LESS THAN THE PRESCRIBED DOSE

"The Kentucky Radiation Health Branch was notified by the U.S. NRC by email on October 4, 2010 of a possible medical event occurring in the Commonwealth. There was no identification of the licensee involved. After extensive research, the Radiation Health Branch identified the licensee where the alleged medical event occurred. During an inspection of the facility, a review of medical documents identified a medical event involving the therapeutic treatment of prostate cancer with Pd-103 seeds.

"The treatment plan called for 100 Pd-103 seeds with an activity of 1.237 mCi per seed. The pretreatment plan of D90=132.78 Gy. The post treatment plan indicated the prostate received a D90=5.18 Gy. The licensee has not acknowledged a medical event. The patient involved has never been notified by the licensee. He was advised of the misadministration by another physician during a second opinion medical evaluation.

"Violations have been issued to the licensee. [An] evaluation [by the state] is ongoing."

* * * UPDATE FROM MICHELE GREENWELL TO JOE O'HARA AT 0841 ON 12/15/10 * * *

The following update was received from the Commonwealth via fax:

"The written directive had a prescribed dose for Pd-103, 100 Gy, act/seed 1.6 U, number of seeds 100."

Notified R1DO(Holody) and FSME(Villamar).

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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General Information or Other Event Number: 46479
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: ANDERSON COLUMBIA CO., INC.
Region: 1
City: LAKE CITY State: FL
County: COLUMBIA
License #: 2708-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/14/2010
Notification Time: 16:15 [ET]
Event Date: 12/14/2010
Event Time: [EST]
Last Update Date: 12/14/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
KEVIN O'SULLIVAN (FSME)
ILTAB via email ()

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

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER SOIL MOISTURE DENSITY GAUGE

The following report was received via facsimile:

At 1545 EST on 12/14/10, the Florida Bureau of Radiation Control received an initial report from the licensee concerning a stolen soil moisture density gauge. The gauge was stolen from a truck at either the employee's residence [Branford, FL] or the licensee's place of business. A chain was cut from the truck securing the case with the gauge inside. Both the case and gauge were discovered stolen. The licensee still has keys to the gauge and will offer a reward for its recovery. Jacksonville Inspection Office will investigate.

The Soil Moisture Density Gauge is a Troxler Model 3430, serial #27858, containing 40 mCi of Am/Be and 8 mCi of Cs-137 sources.

FL Incident No.: FL10-120

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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Fuel Cycle Facility Event Number: 46486
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: JULIE OLIVIER
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/17/2010
Notification Time: 09:04 [ET]
Event Date: 12/16/2010
Event Time: 10:44 [EST]
Last Update Date: 12/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
Person (Organization):
JAY HENSON (R2DO)
JACK DAVIS (NMSS)

Event Text

BOTH HF DETECTORS IN GHS TEST LOOP FAILED TO BE AVAILABLE AND OPERABLE

"During a performance of internal procedure to verify functionality of installed HF detectors in the Test Loop (TL) Gas Handling System (GHS) room, it was discovered at about 1044 [EST on] 12/16/10, that both IROFS TL-HF-01 and IROFS TL-HF-02 failed to pass internal test requirements. At least one of these HF detector IROFS is required to be available and operable to meet 10 CFR 70.61 performance requirements.

"The installed HF detector electrochemical sensors performance appears to have been degraded as a result of low room 'relative humidity' as a result of unusually cold outdoor conditions. The independent IROFS TL-HF-04 (an administrative control) remained intact, thus no unsafe condition existed. While one documented IROFS remained functional (TL-HF-04) to assure the consequence of chemical and radiological exposure is maintained low, TL-HF-04 could not alone meet 10 CFR 70.61 performance requirements.

"No loss of UF6 containment occurred in affected process equipment. The degradation of TL-HF-01 and TL-HF-02 was observed as part of the IROFS' periodic surveillance. This event is therefore being reported pursuant to the requirements of 10 CFR 70 Appendix A(b)(2) within 24 hours. The affected TL bench scale experiment equipment will remain shutdown pending further investigation and implementation of associated corrective actions.

"SAFETY SIGNIFICANCE OF EVENTS - Low safety significance - the discovery did not result in an unsafe condition.

"SAFETY EQUIPMENT STATUS - Required IROFS TL-HF-01 and TL-HF-02 functionality being re-established.

"STATUS OF CORRECTIVE ACTIONS - The affected TL process operation remains shutdown pending investigation and implementation of corrective actions."

The licensee will be contacting NRC Region 2, state and local government agencies.

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Fuel Cycle Facility Event Number: 46487
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: CALVIN PITTMAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/17/2010
Notification Time: 14:12 [ET]
Event Date: 12/17/2010
Event Time: 09:37 [CST]
Last Update Date: 12/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
JAY HENSON (R2DO)
JACK DAVIS (NMSS)

Event Text

DIESEL FUEL OIL SPILL CONTAINED ON SITE - FEDERAL AND STATE OFFICIALS NOTIFIED

"At 0937 CST, 12/17/2010, the Kentucky Emergency Response Team (Report Number 2321984), the Kentucky Department for Environmental Protection, and the National Response Center (Report Number 962502) were notified of the following issue: a diesel fuel oil leak occurred from a pressure indicating line from storage tank located at [Bldg] C-600. The amount of diesel fuel that leaked from the storage tank is greater than the reportable quantity of 75 gallons. The secondary containment drain valve leaked which allowed the diesel fuel to reach the oil containment underflow dam at outfall 008. The diesel fuel is currently contained in the oil containment underflow dam. The effluent from outfall 008 has been tested and does not contain any detectable diesel fuel. Additionally, no visible sheen was observed from the effluent from outfall 008. Cleanup of the diesel fuel is in progress.

"This event is reportable as 'USEC shall notify NRC of any event or situation, related to the health and safety of the public or on-site 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. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'

"The NRC Resident Inspector has been notified of this event.

"PGDP Event Report No. PAD-2010-13."

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Power Reactor Event Number: 46488
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: BILL STUCKER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/17/2010
Notification Time: 17:38 [ET]
Event Date: 12/17/2010
Event Time: 15:35 [CST]
Last Update Date: 12/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
LINDA HOWELL (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

UNANALYZED CONDITION - POTENTIAL EQUIPMENT ACTUATIONS DUE TO ELECTRICAL SHORT CIRCUITS

"A post-fire safe shutdown (PFSSD) circuit analysis identified the potential for a fire in the Control Room to cause multiple proper polarity hot shorts causing the Pressurizer Power Operated Relief Valves (PORV) to open. This postulated failure would require at least three separate 'smart' hot shorts including 1) a positive external hot short, 2) a negative external hot short, and 3) a short across the control room hand switch to cause each PORV to open. This could result in a loss of coolant accident inside the containment building.

"This circuit analysis also identified that a fire in the control room could cause the recirculation dampers associated with the 'B' Essential Service Water Pump Room and 'B' Emergency Diesel Generator Room to fail open, closed, or anywhere in between. This could cause the room temperatures to drop below the minimum or rise above maximum design temperatures depending on ambient conditions.

"Compensatory measures are established for early detection and extinguishment of a fire associated with these circuits in the Control Room. Procedure changes are also being developed for Control Room Evacuation."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46490
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/19/2010
Notification Time: 01:39 [ET]
Event Date: 12/19/2010
Event Time: 00:08 [CST]
Last Update Date: 12/19/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
LINDA HOWELL (R4DO)
MICHELE EVANS (NRR)
JEFFERY GRANT (IRD)
FRED HILL (DHS)
DAVID BARDEN (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

QUICKLY CONCLUDED NOTICE OF UNUSUAL EVENT DUE TO A LOSS OF COMMUNICATIONS

"At 2355 CST, on 12/18/2010, the Control Room was notified by security of the inability of offsite personnel to call into the plant. [At] 0008 CST, on 12/19/2010, the control room verified that the ENS Phone, Conference Operation Network (COP), Security Building, Training Center, and Blair Phone Lines were not functional. At 0011 CST, a Notice of Unusual Event (NOUE) was declared per IC SU6 EAL 2. This also meets the criteria for a Major Loss of Communications Capability under 10 CFR 50.72(b)(3)(xiii).

"At 0028 CST, the control room was notified by security that Huntel Communications was attempting to correct the communications issue. At 0030 CST, the COP phone was restored. At 0046 CST, the ENS phone was verified to be functional.

"At 0050 [CST], the criteria to exit the NOUE [was met] and the event was terminated. At 0059 [CST], the NRC Senior Resident Inspector was notified."

The state and local agencies were notified. The NRC Operations Center conducted a satisfactory test of the ENS line.

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Power Reactor Event Number: 46491
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HANS BISHOP
HQ OPS Officer: PETE SNYDER
Notification Date: 12/20/2010
Notification Time: 01:09 [ET]
Event Date: 12/20/2010
Event Time: 00:21 [EST]
Last Update Date: 12/20/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JAY HENSON (R2DO)
LUIS REYES (R2)
MICHELE EVANS (NRR)
BRUCE BOGER (NRR)
JEFFERY GRANT (IRD)
CHIP STRANGFELD (DHS)
STEPHEN HOLLIS (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

FIRE IN FUEL HANDLING BUILDING HVAC PANEL

"Smoke and sparks were identified as coming from a level 4 Control Building Normal Fuel Handling Building HVAC Heater Control Panel. The heater control panel was deenergized. The fire team was dispatched. The fire was contained in the heater control panel. Smoke removal is in progress."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM HANS BISHOP TO PETE SNYDER AT 0219 EST ON 12/20/10 * * *

At 0218 the licensee terminated the Notice of Unusual Event.

Notified R2DO (Henson), NRR EO (Evans), DHS (Strangfeld), and FEMA (Hollis).

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Power Reactor Event Number: 46492
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE TUTHILL
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/20/2010
Notification Time: 03:47 [ET]
Event Date: 12/20/2010
Event Time: 00:50 [EST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAY HENSON (R2DO)
MICHELE EVANS (NRR)
JEFFERY GRANT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO A FIRE IN THE MAIN GENERATOR BUS DUCT

"At 0050 EST on 12/20/2010, Unit 1 reactor was manually tripped due to a reported fire inside the Unit 1 main generator bus duct.

"A fire was reported at 0045 EST in the Unit 1 bus duct which is located inside the turbine building. The Unit 1 reactor was tripped to remove power from the generator bus. After the reactor trip, the fire was extinguished by the application of water to the bus duct by the fire brigade. The fire was reported extinguished at 0100 EST.

"Method of decay heat removal is via steam dumps. Current temperature and pressure: Temp. 548 degrees and stable; Pressure 2239 psig and stable. No indication of any primary/secondary leakage. All rods are inserted. Electrical alignment is normal, supplied from off-site power. No impact to Unit 2, [and] Unit 2 is operating at 100% power [in] Mode 1."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46493
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CHRIS WEICHLER
HQ OPS Officer: PETE SNYDER
Notification Date: 12/20/2010
Notification Time: 05:15 [ET]
Event Date: 12/20/2010
Event Time: 07:00 [EST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DANIEL HOLODY (R1DO)

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

Event Text

TECHNICAL SUPPORT CENTER VENTILATION MAINTENANCE

"On 12/20/10, at 0700, planned maintenance is being performed on the Onsite Technical Support Center (TSC) Ventilation System. Air handling unit #1 for the TSC supply ventilation is undergoing its 5 year PM. The TSC ventilation system will be tested following maintenance and returned to normal in service lineup. The system is expected to be out of service for a total time of 8 hours.

"This report is being submitted pursuant to 10CFR50.72(b)(3)(xiii) as a result of a reduction in the effectiveness of the Onsite Technical Support Center."

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012