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Event Notification Report for July 17, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/16/2013 - 07/17/2013

** EVENT NUMBERS **


48062 49128 49180 49182 49188 49189 49193 49195 49196 49198 49200 49201

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Part 21 Event Number: 48062
Rep Org: NUTHERM INTERNATIONAL, INC
Licensee: KRAUS AND NAIMER
Region: 3
City: MT. VERNON State: IL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ADRIENNE SMITH
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/02/2012
Notification Time: 15:31 [ET]
Event Date: 06/26/2012
Event Time: [CDT]
Last Update Date: 07/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
JONATHAN BARTLEY (R2DO)
PART 21 GROUP ()

Event Text

PART 21 - FAULTY SWITCH RESULTING FROM A FAILED SPRING

The following was received via facsimile:

"This is to notify the Nuclear Regulatory Commission, in accordance of the provisions of 10 CFR Part 21 of a potential deviation identified by Nutherm International, Inc.

"On June 26, 2012 one M470 Spring Return Kraus and Naimer (K&N) switch (part number CA10 USN892 - 600 FT1 S0C G211 S0 M470/D1A) failed at the Nutherm facility.

"The failed switch was returned to the manufacturer for failure analysis. On July 2, 2012 the manufacturer notified Nutherm that the specific failure mechanism was spring failure on the 'spring return.' The failure was traced to a spring manufacturer supplying the manufacturing facility between November 1, 2011 and June 29, 2012.

"Based on this information, M470 spring return switches manufactured during this time period have the potential for this spring failure.

"Nutherm has determined that the following site has received these switches from Nutherm and is affected: Farley Nuclear Plant."

* * * UPDATE ON 7/16/13 AT 1221 EDT FROM ADRIENNE SMITH TO DONG PARK * * *

The following was received via facsimile:

"This written final report is in response to Event/Accession Number ML121910334 reported by Nutherm International, Inc. There were a total of three (3) switches shipped to Southern Nuclear Operating Company, Farley Nuclear Plant affected by this issue. Southern Nuclear Operating Company, Farley Nuclear Plant was notified on July 2, 2012 of this issue and provided with the specific traceability numbers of all units. None of the units had been installed at the time of the notification.

"Southern Nuclear Operating Company returned all three units on July 5, 2012. The units were subsequently destroyed by Nutherm International, Inc.

"Corrective actions have been put in place to prevent recurrence of this issue. Corrective actions include additional testing of spring return switches of this model type."

Notified R2DO (Nease) and Part 21 group via email.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 49128
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: WAYNE EPPEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/17/2013
Notification Time: 18:34 [ET]
Event Date: 06/17/2013
Event Time: 16:15 [CDT]
Last Update Date: 07/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT DALEY (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
2 N Y 82 Power Operation 82 Power Operation

Event Text

POTENTIAL UNANALYZED CONDITION - CARBON DIOXIDE FIRE SUPPRESSION SYSTEM DOES NOT MEET DESIGN REQUIREMENTS

"At approximately 1615 CDT on June 17, 2013, station personnel identified a potential unanalyzed condition based on the following:

"The 1998 design calculation for the carbon dioxide fire suppression system protecting the Relay Room is in part based on an unverified leakage rate for the enclosure. Recent testing and subsequent calculations have found the room leakage rate is higher than the leakage rate specified in the 1998 design calculation. As such, more carbon dioxide would be required to meet design requirements. The minimum required level for the system storage tank would not currently provide two shots of carbon dioxide (design requirement) to suppress a fire.

"The minimum required quantity in the tank would be sufficient to provide one shot of carbon dioxide to suppress a fire; however, since this doesn't meet the design requirement, a continuous fire watch was initiated."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION ON 7/16/13 AT 1648 EDT FROM MARK LOOSBROCK TO DONG PARK * * *

"Further evaluation determined that the as-found configuration did not meet the minimum design requirements. However, the CO2 concentration was adequate to suppress a fire within the relay and cable spreading room."

The licensee has notified the NRC Resident Inspector.

Notified R3DO (Hills).

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Agreement State Event Number: 49180
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: HOPEWELL RADIOLOGY GROUP
Region: 1
City: MONROE State: NJ
County:
License #: 453815
Agreement: Y
Docket:
NRC Notified By: RICHARD PEROS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/08/2013
Notification Time: 14:37 [ET]
Event Date: 07/08/2013
Event Time: 13:30 [EDT]
Last Update Date: 07/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM COOK (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - LEAKING SOURCE

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

"At approximately 1:30 p.m. [EDT] on Monday, July 8, 2013, the consulting health physicist for Hopewell Radiology Group called to inform the NJDEP's RMP [New Jersey Department of Environmental Protection Radioactive Materials Program] that a sealed vial source originally containing approximately 209 uCi of Cesium-137 on June 1, 2001, was found to be leaking. The source was manufactured by Eckert & Zeigler and has a serial number of 747-33-46.

"A routine semi-annual leak test of the source revealed the presence of 0.067 uCi of removable contamination, which exceeds the limit of 0.005 uCi.

"The source has been removed from service and is secured at the licensee's location. The licensee is arranging for appropriate disposal."

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Non-Agreement State Event Number: 49182
Rep Org: ST ALPHONSUS REGIONAL MED CTR
Licensee: ST ALPHONSUS REGIONAL MED CTR
Region: 4
City: BOISE State: ID
County:
License #: 11-27306-01
Agreement: N
Docket:
NRC Notified By: TIM STACK
HQ OPS Officer: DANIEL MILLS
Notification Date: 07/09/2013
Notification Time: 16:06 [ET]
Event Date: 12/20/2012
Event Time: [MDT]
Last Update Date: 07/09/2013
Emergency Class:
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
Person (Organization):
DAVID PROULX (R4DO)
FSME EVENT RESOURCE (EMAI)

Event Text

MEDICAL EVENT - DOSE DELIVERED TO OTHER SITE

On December 20, 2012, a patient was administered microspheres to treat the liver. On July 9, 2013 the administering facility learned that a biopsy identified microspheres in a slow healing gastric ulcer. The facility is assuming that the patient received a dose that exceeded the limits based on the presence of microspheres and the development of a gastric ulcer.

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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Power Reactor Event Number: 49188
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: JON PILLION
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/14/2013
Notification Time: 16:29 [ET]
Event Date: 07/14/2013
Event Time: 16:00 [CDT]
Last Update Date: 07/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JULIO LARA (R3DO)

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 OUT OF SERVICE FOR PLANNED PREVENTATIVE MAINTENANCE

"At 1600 CDT on Sunday, July 14, 2013, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) emergency ventilation system will be removed from service for planned preventative maintenance activities on the TSC air handling unit and air compressor units. During the maintenance, the TSC ventilation will be shut down. The TSC air filtration fan and dampers will be non-functional, rendering the TSC HVAC accident mode non-functional. This maintenance is scheduled to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed within 48 hours. Contingency plans are in place so that if an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing EP (Emergency Preparedness) procedures and checklists. If radiological or environmental conditions require TSC facility evacuation during ventilation system restoration, the Station Emergency Director will evacuate and relocate the TSC staff in accordance with station procedures.

"The NRC Resident Inspector has been notified."

* * * UPDATE AT 1056 EDT ON 7/17/13 FROM PILLION TO HUFFMAN * * *

"The planned TSC ventilation outage, for maintenance activities on the TSC air handling unit and air compressor units, has been extended and is now scheduled to complete on Saturday, July 20, 2013. During this maintenance, the TSC air filtration fan and dampers will continue to be non-functional."

The licensee has notified the NRC Resident Inspector. R3DO (Hills) has been notified.

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Power Reactor Event Number: 49189
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: KEVIN O'ROURKE
HQ OPS Officer: PETE SNYDER
Notification Date: 07/15/2013
Notification Time: 00:58 [ET]
Event Date: 07/15/2013
Event Time: 00:29 [EDT]
Last Update Date: 07/17/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
WILLIAM COOK (R1DO)
MICHELE EVANS (NRR)
ERIC LEEDS (NRR)
DAVID LEW (R1)
SCOTT MORRIS (IRD)

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 DECLARED DUE TO LOSS OF CONTROL ROOM ANNUNCIATORS

The licensee declared a Notice of Unusual Event resulting from a loss of control room annunciators for greater than 15 minutes. The EAL Condition is SU 4.1. Compensatory measures have been established per Abnormal Operating Procedures. The plant continues to operate at 100 percent power.

The licensee has called for support staff to troubleshoot the issue. No other major components are out of service.

The licensee has notified the NRC Resident Inspector.

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

* * * UPDATE FROM KEVIN O'ROURKE TO PETE SNYDER AT 0205 EDT ON 7/15/13 * * *

Annunciator indication has returned for some time and appears to be working. Engineering and electrical instrumentation and control staff are onsite to troubleshoot but have not established any cause. The licensee remains in the Unusual Event until additional confidence can be established in annunciator indication.

Notified R1DO (Cook).

* * * UPDATE FROM STAN PAUL TO JOHN SHOEMAKER AT 2350 EDT ON 7/16/13 * * *

"The NOUE declared on July 15, 2013 at 0029 EDT hours due to loss of main control room annunciation was terminated on July 16, 2013 at 2310 EDT hours when the annunciation system was declared functional."

Plant personnel and vendors have completed diagnostic checks and testing, system voltages are normal, and the annunciator system is working normally.

The licensee has notified the NRC Resident Inspector.

Notified R1DO (Gray), NRR EO (Hiland), IRD MOC (Grant), DHS SWO, FEMA, DHS NICC and the Nuclear SSA via email.

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Power Reactor Event Number: 49193
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DAVID HOLICK
HQ OPS Officer: PETE SNYDER
Notification Date: 07/16/2013
Notification Time: 07:48 [ET]
Event Date: 07/16/2013
Event Time: 04:30 [PDT]
Last Update Date: 07/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN LANTZ (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

MAINTENANCE ON TECHNICAL SUPPORT CENTER / OPERATIONS SUPPORT CENTER VENTILATION

"Scheduled maintenance of the Technical Support Center (TSC) / Operations Support Center (OSC) HVAC system for replacement of charcoal filters started at 0430 hours [PDT] on 7/16/13 and will last approximately 37 hours (estimated time from equipment tag out back to OPERABLE). During this time the TSC and OSC will not be available for use to support emergency response activities. Established compensatory measures direct Emergency Response Organization (ERO) members normally responding to either of these facilities to respond to alternate locations. No other emergency response facilities are impacted by the scheduled TSC / OSC Facilities HVAC maintenance work.

"This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. A follow up notification will be made when HVAC maintenance to the TSC / OSC Facilities has been completed and operability of these EP Facilities has been restored."

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Power Reactor Event Number: 49195
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WALTER HUNNICUTT
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/16/2013
Notification Time: 14:20 [ET]
Event Date: 05/28/2013
Event Time: 13:39 [EDT]
Last Update Date: 07/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
EUGENE GUTHRIE (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

Event Text

60 DAY REPORT - INVALID ACTUATION OF SPECIFIED SYSTEM

"This 60-day optional report as allowed by 10 CFR 50.73(a)(1), is being made under the reporting requirement in 10 CFR 50.73 (a)(2)(iv)(A) to describe an invalid actuation of a specified system, specifically the Nuclear Service Water (RN) system. This event had no impact on public health and safety.

"During work to replace a timer associated with an RN (Nuclear Service Water) level circuit, electrical adapters and jumpers were installed incorrectly, resulting in generation of an Emergency Low Pit Level signal. This resulted in an unplanned actuation for RN to realign its suction source from Lake Wylie (normal source) to the alternate source, the SNSWP (Standby Nuclear Service Water Pond). On 5/28/13, with both units at 100% power, a lo-lo level signal was received for A Train RN Pit, initiating the realignment to the SNSWP for both A and B trains. Prior to this event, both trains of RN were aligned to the SNSWP for maintenance.

"The lo-lo level signal did initiate a start of all available RN Pumps. Associated valves, including RN crossover valve, return header isolation valves and non-essential header isolation valves closed as expected. This separated RN trains A and B. This was a complete actuation for Train A and the system performed as designed for existing plant conditions. This event was entered into the site corrective action program for resolution."

The licensee will notify the NRC Resident Inspector, as well as, the State and local governments.

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Power Reactor Event Number: 49196
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: STAN PAUL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/16/2013
Notification Time: 23:50 [ET]
Event Date: 07/15/2013
Event Time: 16:52 [EDT]
Last Update Date: 07/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
HAROLD GRAY (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

SALT SERVICE WATER SYSTEM DECLARED INOPERABLE

"On Tuesday, July 16, 2013 at 1652 [EDT], with the reactor at 100% core thermal power (CTP) the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation (LCO) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO was subsequently exited at 1830 hours when the temperature of SSW trended to below the TS limit.

"Under certain accident conditions the SSW system is required to provide cooling water to the Reactor Building Closed Cooling Water (RBCCW) system heat exchanger. When the inlet temperature to this supplied load exceeds the 75 [degrees] F limit established in the TS, the SSW system is declared inoperable until the temperature trends below this value. This condition existed for approximately 1-1/2 hours and the SSW system was declared operable and the LCO exited. A maximum temperature of 75.3 [degrees] F was recorded during this period.

"The SSW temperature is being closely monitored and trended on a continuous basis.

"This event has no impact on the health and safety of the public.

"The licensee has notified the NRC Senior Resident Inspector."

SSW temperature varies with tidal movement.

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Power Reactor Event Number: 49198
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD PERKINS
HQ OPS Officer: DANIEL MILLS
Notification Date: 07/17/2013
Notification Time: 15:05 [ET]
Event Date: 07/17/2013
Event Time: 13:35 [EDT]
Last Update Date: 07/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (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

PLANNED TESTING OF STACK RADIATION MONITORS

"Millstone Unit 2 loss of assessment capability due to pre-planned maintenance of the Millstone Station stack radiation monitor RM-8169 at 1335 EDT on 7/17/13. This event is reportable pursuant to 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability. During the maintenance, Unit 2 was at 100% power, Mode 1. We informed the State of Connecticut, Waterford dispatch, and the NRC Resident Inspector."

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Power Reactor Event Number: 49200
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JOHN CLARK
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/17/2013
Notification Time: 17:36 [ET]
Event Date: 07/17/2013
Event Time: 16:05 [EDT]
Last Update Date: 07/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
HAROLD GRAY (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

OFFSITE NOTIFICATION DUE TO A CHEMICAL SPILL ONSITE

"Today, July 17th, 2013, at approximately 1605 EDT, the New Jersey Department of Environmental Protection was notified that approximately 1 pint of sodium hypochlorite was spilled onto the lands of the State of New Jersey. The spill has been contained and cleaned-up. There was no actual or potential impact on the environment and no impact on the health and safety of the public or onsite personnel.

"Due to notification of a government agency, this event is being reported under 10CFR50.72 (b)(2)(xi)."

The spill did not reach the federal reportable quantities limit.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49201
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MIKE HETTWER
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/17/2013
Notification Time: 17:42 [ET]
Event Date: 07/17/2013
Event Time: 10:54 [EDT]
Last Update Date: 07/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
HAROLD GRAY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 85 Power Operation

Event Text

SALT SERVICE WATER SYSTEM DECLARED INOPERABLE

"On Wednesday, July 17, 2013 at 1054 hours EDT, with the reactor at 100% core thermal power (CTP) the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation (LCO) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO was subsequently exited at 1625 hours when the temperature of SSW trended to below the TS limit.

"Under certain accident conditions the SSW system is required to provide cooling water to the Reactor Building Closed Cooling Water (RBCCW) system heat exchanger. When the inlet temperature to this supplied load exceeds the 75 [degrees] F limit established in the TS, the SSW system is declared inoperable until the temperature trends below this value. This condition existed for approximately 5-1/2 hours and the SSW system was declared operable and the LCO exited. A maximum temperature of 75.5 [degrees] F was recorded during this period.

"At 1230 hours a power reduction was conducted to improve secondary plant parameters and Rx power is currently 85%.

"The SSW temperature is being closely monitored and trended on a continuous basis.

"This event has no impact on the health and safety of the public.

"The licensee has notified the NRC Senior Resident Inspector." The licensee will notify the Commonwealth of Massachusetts.

Page Last Reviewed/Updated Friday, July 19, 2013
Friday, July 19, 2013