United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for October 4, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/03/2012 - 10/04/2012

** EVENT NUMBERS **


48290 48340 48346 48367 48368 48369 48370 48372

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Power Reactor Event Number: 48290
Facility: BYRON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT LAWLOR
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/10/2012
Notification Time: 11:34 [ET]
Event Date: 09/10/2012
Event Time: 09:00 [CDT]
Last Update Date: 10/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN GIESSNER (R3DO)

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

PLANT PROCESS COMPUTER REMOVED FROM SERVICE FOR MAINTENANCE

"At 0900 CDT on September 10, 2012, the Unit 1 Plant Process Computer (PPC) was removed from service for a planned replacement in the current Unit 1 Refueling Outage. The Unit 1 PPC feeds the Safety Parameter Display System (SPDS) used in the Main Control Room (MCR) and the Technical Support Center (TSC). The Unit 1 PPC also feeds the Emergency Response Data System (ERDS).

"The Unit 1 and Unit 2 PPCs also feed the Plant Parameters Display System (PPDS) used in the MCR, TSC and Emergency Operations Facility (EOF). Meteorological data will remain available. The dose assessment program will remain functional as the Unit 2 PPC will be capable of providing the necessary data through PPDS to run the program. The dose assessment program is not affected by the Unit 1 PPC being out of service. As compensatory measures, a proceduralized backup method to fax or communicate via a phone circuit applicable data to the NRC, TSC, and EOF exists. There is no impact on the Emergency Notification System (ENS) or Health Physics Network (HPN) communication systems.

"The new Unit 1 PPC is scheduled to be functional on September 17, 2012. However, based on the Mode Unit 1 will be in, this will limit the number of points that would provide usable data. The Unit 1 PPC will be tested as Mode changes occur. The Unit 1 PPC is planned to be declared functional by Mode 2. A follow-up ENS call will be made once the Unit 1 PPC is declared functional.

"The loss of SPDS and ERDS is a 'major loss of assessment capability' and is reportable under 10CFR50.72(b)(3) (xiii).

"The NRC Senior Resident Inspector and the State of Illinois (through the Illinois Emergency Management Agency Resident Inspector) have been notified of this ENS call."

* * * UPDATE FROM BRYAN GAPINSKI TO JOHN KNOKE AT 1510 EDT ON 10/03/12 * * *

As of 1245 CDT on October 3,2012, the Unit 1 PPC is considered operational with respect to the Safety Parameter Display System (SPDS), Plant Parameter Display System (PPDS), and Emergency Response Data System (ERDS). Therefore, a major loss of assessment capability no longer exists on Unit 1. The Byron EP manager contacted the NRC ERDS Center on 10/02/2012 to conduct an ERDS test for Unit 1 to ensure the data was being satisfactorily sent to the NRC. Unit 1 and Unit 2 ERDS data to NRC was tested satisfactory lAW EP-AA-124-F01.

"The NRC Resident Inspector and the State of Illinois (through the Illinois Emergency Management Agency Resident Inspector) have been notified of this ENS update. Notified the R3DO (Dave Passehl)

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Agreement State Event Number: 48340
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: SOUTH STATE INC
Region: 1
City: BRIDGETON State: NJ
County:
License #: RAD110001-507
Agreement: Y
Docket:
NRC Notified By: PATRICIA GARDNER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/25/2012
Notification Time: 10:10 [ET]
Event Date: 09/25/2012
Event Time: 01:00 [EDT]
Last Update Date: 09/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RONALD BELLAMY (R1DO)
FSME EVENT RESOURCE (E-MA)
D. JOHNSON VIA EMAIL (ILTA)

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

Event Text

AGREEMENT STATE REPORT - LOST HUMBOLDT DENSITY GAUGE

The following report was received from the NJ Department of Environmental Protection Bureau of Environmental Radiation via facsimile:

"Licensee: South State Inc.

"Event date and time: September 25, 2012 at 01:00 am

"Event location: NJ Turnpike Interchanges 1-3 N-S

"Event type: Lost density gauge - Humboldt Model 5001EZ Serial No. 2872 (Am-241 44 mCi and Cs-137 11 mCi)

"Notifications: NJDEP BER and NJDEP Hotline

"Event Description: South State Inc. reported a missing density gauge on September 25, 2012 at 01:29 am. South State was working on the NJ Turnpike. South State reported that the gauge was lost somewhere between exits 1 and 3 on the north or south bound lanes of the turnpike. Additionally, South State is looking along the route that was taken from their office on 202 Reeves St in Bridgeton, NJ and the turnpike.

"As of 9:00 am this morning, the gauge has not been recovered and the search continues.

"Media attention: None

"NJ Event Report ID No: 12-09-25-0129-19"

* * * UPDATE ON 9/26/12 AT 1239 EDT FROM PATRICIA GARDNER TO DONG PARK * * *

The following report was received from the NJ Department of Environmental Protection Bureau of Environmental Radiation via email:

"The Humboldt Model 5001EZ Serial No. 2872 has been recovered. The gauge is back at the licensee's (South State Inc.) facility. There is no observable damage to the transportation case and/or the gauge. The NJ State Police assisted with the recovery. Details of the event are being summarized and the NMED event report will be updated when completed."

Notified R1DO (Bellamy), FSME, and ILTAB (Johnson) via email.

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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Agreement State Event Number: 48346
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: CRAIG TESTING LABORATORY
Region: 1
City: SILVER SPRING State: MD
County:
License #: MD33141-01
Agreement: Y
Docket:
NRC Notified By: ALAN JACOBSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/26/2012
Notification Time: 12:56 [ET]
Event Date: 09/24/2012
Event Time: [EDT]
Last Update Date: 09/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RONALD BELLAMY (R1DO)
FSME RESOURCES (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

A Troxler model 3411B moisture density gauge was run over by a front end loader at a construction site in Silver Spring, MD. The area was roped off and the Radiation Safety Officer and the Maryland State Inspector were able to verify that though the control rods were detached, the sources had remained in their shielded positions. The damaged gauge was placed in the transport case and will be taken to a licensed repair facility. This model gauge typically has a 9 mCi Cs-137 and a 44 mCi Am-241:Be source.

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Power Reactor Event Number: 48367
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOSEPH GIOFFRE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/03/2012
Notification Time: 07:25 [ET]
Event Date: 10/03/2012
Event Time: 00:10 [EDT]
Last Update Date: 10/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
WAYNE SCHMIDT (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

UNANALYZED CONDITION DUE TO HIGH ENERGY LINE BREAK BARRIER BEING PARTIALLY OPEN

"At 0010 [EDT] on 10/3/12, it was determined that an unanalyzed condition existed for the switchgear rooms on Unit 1. A degraded condition of a high energy line break (HELB) barrier was created during security surveillance. A HELB barrier door for the 27' elevation switchgear room was partially opened for a 14 minute period and could have allowed steam from a HELB on the 27' elevation of the Turbine Building to potentially impact equipment in both the 27' and 45' elevation switchgear rooms because these rooms are connected by a common ventilation system. The switchgear rooms are not analyzed for a steam environment. The degree of the impact could not be readily determined, but could likely affect the safety related equipment in the switchgear rooms. At 0024 [EDT] on 10/3/12, the HELB barrier door for the 27' elevation switchgear room was closed and the barrier restored which eliminated the potential unanalyzed condition. An 8 hour report to the NRC is required under 10 CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety' since there was not a reasonable expectation that the switchgear room environment could support operation of safety related equipment with the 27' elevation switchgear room door partially open. Further analysis is underway."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48368
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOSEPH GIOFFRE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/03/2012
Notification Time: 07:25 [ET]
Event Date: 10/03/2012
Event Time: 08:00 [EDT]
Last Update Date: 10/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER OUTAGE DUE TO PLANNED MAINTENANCE

"This report is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the planned loss of an Emergency Response Facility (ERF). Calvert Cliffs will be implementing a scheduled modification to renovate the site's common Technical Support Center (TSC) which will temporarily remove it from service. The planned maintenance window is expected to be three weeks beginning on 10/3/12 and concluding on 10/26/12. Should an emergency be declared requiring TSC activation during this period, the procedurally identified alternate TSC will be staffed and activated (CCNPP Simulator). All TSC responders and other key ERO personnel have been briefed on this activity and the applicable contingency actions that will be required to be taken in their specific emergency response procedures. This condition has no adverse impact to the health and safety of the public. An update will be provided once the TSC has been restored to normal operation."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48369
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ANDREW TEREZAKIS
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/03/2012
Notification Time: 12:15 [ET]
Event Date: 10/03/2012
Event Time: 08:43 [EDT]
Last Update Date: 10/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)

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

Event Text

FAILURE OF STARTUP TRANSFORMER CAUSED UNDERVOLTAGE CONDITION ON ESSENTIAL BUS

"On October 3, 2012, with Unit 2 in a defueled condition, a failure occurred on the 2B Startup Transformer, causing an undervoltage condition on an essential bus and resulted in the automatic start and loading of the 2B Emergency Diesel Generator (EDG). Prior to the event, the 2B EDG was available and not required by Technical Specifications; however, the 2B EDG was inoperable. Additionally, the 2A EDG is available. All equipment responded as expected. Currently maintaining the plant in a defueled condition. Decay heat removal is being supplied by the 2A Fuel Pool Cooling train and was never interrupted. There was no impact on the Shutdown Safety Assessment.

"This event is reportable pursuant to 10CFR50.72(b)(3)(iv)(A).

"Due to common high side feed, the loss of the 2B Startup Transformer resulted in the loss of the 1B Startup Transformer. Prior to the event, the 1A EDG was out of service for maintenance. As a result, Unit 1 entered Technical Specification 3.8.1.1 Action C. due to the loss of one offsite AC circuit and one diesel generator inoperable."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48370
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/03/2012
Notification Time: 12:26 [ET]
Event Date: 08/05/2012
Event Time: 21:25 [EDT]
Last Update Date: 10/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation
2 N Y 98 Power Operation 98 Power Operation

Event Text

RPS SUB-COMPONENT FAILURE CAUSED HALF SCRAM WITH GROUP 2 PCIV ACTUATION

"On August 5, 2012, at 21:25 EDT, Unit 1 received a Reactor Auto SCRAM System 'A' Trip signal in the main control room. The annunciator was initially reset by operators, but the operating crew noted that some white SCRAM lights and some Group 2 PCIV indication lights were flickering in the control room. This anomaly coupled with the ability to reset the annunciated condition immediately indicated an issue with fluctuating voltage on the power supply for RPS [Reactor Protection System] 'A'. Approximately 30 seconds after the annunciator was reset, the 'A' RPS bus tripped, causing a half SCRAM in conjunction with the automatic actuation of the Standby Gas Treatment system (SGT) and isolation of PCIVs in multiple systems, both of which are normal responses to this loss of the 'A' RPS bus. The crew entered the appropriate abnormal operating procedures and confirmed the actuations automatically occurred as required given the loss of the RPS bus. They investigated the 'A' RPS Motor/Generator (M/G) set, placed the 'A' RPS bus on its alternate supply, reset the SGT and PCIV actuation logic, and returned the PCIVs to their normal position.

"Upon investigation, the 'A' RPS M/G set was found running, but the Over Voltage Relay in the power monitoring cabinet was chattering. The field investigation team determined that the RPS trip was caused by the failure of its voltage regulator which was then replaced. The 'A' RPS M/G set was consequently returned to service as the primary RPS power source on August 6, 2012. Maintenance personnel subsequently determined that a voltage regulator subcomponent was defective. Because the malfunctioning subcomponent caused the loss of RPS 'A' as the initiating event rather than a valid SGT or PCIV actuation signal, the resulting actuation of SGT and the isolation of multiple PCIVs are considered invalid actuations. Based on that information, 10CFR50.73(a){2)(iv) allows this event to be reported via a telephone notification within 60 days instead of submitting a written LER."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48372
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/03/2012
Notification Time: 20:22 [ET]
Event Date: 10/03/2012
Event Time: 16:00 [EDT]
Last Update Date: 10/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
WAYNE SCHMIDT (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

FIRE SAFE SHUTDOWN ANALYSIS FAILED TO IDENTIFY UNPROTECTED CABLE

"During logic and cable routing reviews for Multiple Spurious Operations (MSO), an existing unprotected cable issue was identified that impacts the D22 emergency Diesel Generator (EDG) output breaker. This unprotected cable could fail due to fire damage in fire area 067W when the associated 4kV safeguard bus is credited for Post-Fire Safe Shutdown.

"The single spurious fire induced cable failure identified can cause the D22 EDG output breaker to spuriously close when the 4kV safeguard bus is credited using the offsite power source. The existing fire safe shutdown analysis failed to identify this cable required protection in order to credit the 4kV safeguard bus in area 067W postulated fire."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, October 04, 2012
Thursday, October 04, 2012