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Event Notification Report for December 27, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/23/2011 - 12/27/2011

** EVENT NUMBERS **


47499 47528 47535 47536 47546 47547 47549 47550 47551 47552 47553

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Power Reactor Event Number: 47499
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT STRUSINSKI
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/06/2011
Notification Time: 09:51 [ET]
Event Date: 12/06/2011
Event Time: 09:30 [EST]
Last Update Date: 12/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BINOY DESAI (R2DO)

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

Event Text

TECHNICAL SUPPORT CENTER NON-FUNCTIONAL DUE TO PLANNED MAINTENANCE

"Between December 6, 2011 and January 13, 2012, a sequence of activities are planned that will render the Technical Support Center (TSC) non-functional at times by removing the emergency ventilation system from service. These activities are being performed in support of planned preventive maintenance and extended power uprate facility upgrades. In preparation for these emergency ventilation system outages, the TSC emergency responders were notified that if an emergency occurred during these outages the Emergency Coordinator and the TSC staff involved with classification, notification and PARS should report to the control room. All other TSC personnel should report to the Operational Support Center. The duration for each of these TSC outages is expected to be less than 24 hours. The NRC Operations Center will be provided an update to this notification when the TSC emergency ventilation has been removed from service and following restoration for each time period. This 8 hour notification in accordance with 10 CFR 50.72(b)(3)(xiii)."

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

* * * UPDATE FROM CHRISTOPHER TRENT TO JOE O'HARA AT 1900 EST ON 12/7/11 * * *

The TSC is functional at this time.

The NRC Resident Inspector will be notified.

* * * UPDATE FROM BILL BURROWS TO CHARLES TEAL AT 0313 EST ON 12/14/11 * * *

The TSC has been removed from operation to continue planned maintenance.

The NRC Resident Inspector has been notified. Notified R2DO (Bartley).

* * * UPDATE FROM ROBERT STRUSINSKI TO JOHN KNOKE AT 0330 EST ON 12/15/11 * * *

The TSC is functional at this time.

The NRC Resident Inspector will be notified. Notified R2DO (Scott Freeman) via email.

* * * UPDATE FROM SEAN BLOOM TO BILL HUFFMAN AT 0306 EST ON 12/20/11 * * *

The TSC will be removed from operation to continue planned maintenance at 0330 EST today.

The NRC Resident Inspector will be notified. Notified R2DO (Freeman).

* * * UPDATE FROM SEAN BLOOM TO VINCE KLCO AT 0335 EST ON 12/21/11 * * *

The TSC has been returned to service at 0130 EST on 12/21/11.

The NRC Resident Inspector will be notified. Notified the R2DO (McCoy).

* * * UPDATE ON 12/26/2012 AT 2333 FROM JOSE VASQUEZ TO MARK ABRAMOVITZ * * *

The TSC was taken out of service at 2330 and will be out of service for several weeks.

The NRC Resident Inspector was notified. Notified the R2DO (McCoy).

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Agreement State Event Number: 47528
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: UNIVERSITY OF MINNESOTA
Region: 3
City: MINNEAPOLIS State: MN
County:
License #: 1049-206-27
Agreement: Y
Docket:
NRC Notified By: LYNN DUNBAR
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/15/2011
Notification Time: 17:43 [ET]
Event Date: 12/06/2011
Event Time: 19:00 [CST]
Last Update Date: 12/23/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HIRONORI PETERSON (R3DO)
KEVIN O'SULLIVAN (FSME)

Event Text

AGREEMENT STATE REPORT - POSSIBLE MEDICAL EVENT

The following was received from the State of Minnesota via email:

"Minnesota Department of Health (MDH) was initially notified on December 14, 2011, by a representative from the University of Minnesota about a possible HDR [High Dose Rate] medical event. As of December 15, 2011 MDH was notified of the determination of a medical event that resulted in a 50% overexposure to an unintended area."


* * * UPDATE FROM BRANDON JURAN TO DONALD NORWOOD AT 1149 EST ON 12/23/2011 VIA E-MAIL * * *

"This notification is to provide follow-up information to the medical event initially reported on 12/15/2011 by Lynn Dunbar of the Minnesota Department of Health.

"The patient was being treated for uterine cancer using iridium 192 high dose-rate (HDR) brachytherapy. The written directive called for treating the target area to approximately 600 cGy per fraction for five fractions. Instrumentation consisted of four plastic Heyman capsules, a tandem, and a pair of ovoids. Of the seven pathway options, five were identified to be used in the treatment plan for delivering the dose, and catheters were inserted into these instruments.

"The first fraction of five was delivered with the tandem catheter not fully inserted into the tandem. The second of five fractions was delivered according to the original written directive. The 3rd, 4th, 5th fractions were modified to give the treatment volume the originally intended total dose. The dose to the rectum would have been 157.5 cGy if all five fractions were completed according to the original written directive. The dose to the rectum as treated was 256.2 cGy, about 63% more than intended."

The Event Date provided in the initial report was changed (from 12/15/2011 to 12/6/2011) and the number given as the 'MDH #' (MDH #: 1049-206-27) was re-assigned as the licensee's license number based on information provided in the update.

Notified R3DO (Pelke) and FSME EO (Einberg).

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: 47535
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: KRATON POLYMERS
Region: 3
City: BELPRE State: OH
County:
License #: 31201850010
Agreement: Y
Docket:
NRC Notified By: KARL VON AHN
HQ OPS Officer: JOE O'HARA
Notification Date: 12/20/2011
Notification Time: 08:14 [ET]
Event Date: 12/19/2011
Event Time: 11:30 [EST]
Last Update Date: 12/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PATTY PELKE (R3DO)
MICHELE BURGESS (FSME)

Event Text

AGREEMENT STATE REPORT - SHUTTER FAILURE ON OHMART SH-100 PROCESS GAUGE

"At 11:30 AM December 19, 2011, the licensee's radiation safety officer provided a 24-hour telephone report notification of a shutter failure on a gauge. The gauge involved was an Ohmart SH-100, serial number 70230, containing 10 mCi of CS-137, with an assay date of Aug 1981. The shutter mechanism is a lead block screwed to a sliding aluminum plate. The licensee was removing the gauge from its mounting to replace it with a different new gauge as permitted by their license. When the licensee removed the gauge from its mounting, the lead block separated from the aluminum plate. The licensee replaced the lead shielding and secured it in place. The licensee secured the gauge from unauthorized access and will return it to the manufacturer for disposal with other gauges they are replacing. The licensee states that no personnel received radiation doses during this event."

Ohio Report #OH110005

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Agreement State Event Number: 47536
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NUCOR-YAMATO STEEL
Region: 4
City: BLYTHEVILLE State: AR
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/20/2011
Notification Time: 13:07 [ET]
Event Date: 12/19/2011
Event Time: 00:00 [CST]
Last Update Date: 12/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BOB HAGAR (R4DO)
MICHELE BURGESS (FSME)

Event Text

AGREEMENT STATE REPORT - SCRAP METAL FACILITY REJECTED LOAD

The following information was provided by the state via email:

"Nucor-Yamato Steel in Blytheville, Arkansas reported to the Arkansas Radiation Control Program on December 19, 2011, that a sealed source containing radioactive material had been found in a load of scrap metal received at their facility. The broker for this load of scrap metal was The David J. Joseph Company. The load of scrap originated in Louisiana.

"Survey readings on contact with the source using a sodium iodide detector were 1.0 mR/hr. Smears taken and counted using a thin window GM detector in the field indicates that the source does not appear to be leaking.

"The source has a glass covered flange end approximately 1.125" diameter, with a fitting on the back side of approximately 0.5" diameter. Overall length is approximately 1.0". No identifying marks have been found at this time.

"The source was contained within a small can, secured within a locked storage room. The steel mill is awaiting a consultant to pick-up, identify and dispose of the source."

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Power Reactor Event Number: 47546
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: LOURDES PORRO
HQ OPS Officer: VINCE KLCO
Notification Date: 12/22/2011
Notification Time: 09:56 [ET]
Event Date: 12/22/2011
Event Time: 10:00 [EST]
Last Update Date: 12/23/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER VENTILATION UNAVAILABLE DUE TO PREPLANNED MAINTENANCE

"On December 22, 2011, at 1000 EST, due to pre-planned refueling outage maintenance, the Control Room Emergency Ventilation system on St. Lucie Unit 1 is inoperable. The Unit 1 Control Room Emergency Ventilation system provides filtered air to the Technical Support Center (TSC) ventilation system, therefore, the TSC ventilation system has been rendered unavailable during the course of the work activities. The Control Room Emergency Ventilation system is expected to be returned to service in 38 hours, and TSC filtered ventilation restored.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Should the TSC become uninhabitable, the TSC staff will relocate to an alternate TSC location in accordance with applicable site procedures.

"This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the Control Room Emergency Ventilation system has been restored to normal operation. The NRC Resident Inspector has been notified."

Unit 1 is currently de-fueled.

* * * UPDATE FROM CHUCK MONTANA TO VINCE KLCO AT 0459 EST ON 12/23/2011* * *

"Update 12/23/2011, 0418 EST: The U1 Control Room Emergency Ventilation has been restored to operable [status] and the TSC filtered ventilation has been restored [to operable status]."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (McCoy).

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Power Reactor Event Number: 47547
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: PATRICK WALSH
HQ OPS Officer: VINCE KLCO
Notification Date: 12/23/2011
Notification Time: 03:03 [ET]
Event Date: 11/07/2011
Event Time: 22:31 [EST]
Last Update Date: 12/23/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
NEIL PERRY (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

INVALID SPECIFIED SYSTEM ACTUATION DUE TO A POSSIBLE FAULTY TEMPERATURE SWITCH

"This 60-day telephone notification is being made per the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation signal affecting containment isolation valves in more than one system.

"On November 7, 2011, Nine Mile Point Unit 2 (NMP2) received a Division 2 reactor building pipe chase high ambient temperature isolation signal, which resulted in closure of isolation valves in the reactor water cleanup (RWCU) system, the reactor core isolation cooling (RCIC) system, and the residual heat removal (RHR) system (isolation valve groups 5, 6, 7, and 10). All affected isolation valves responded as designed.

"The Division reactor building pipe chase high ambient temperature isolation signal was generated by a new NUS/Scientech ambient temperature indicating switch that had recently been installed as a replacement for the original Riley temperature switch, which is no longer being manufactured. Two temperature switches (one for Division 1 and one for Division 2) monitor the reactor building pipe chase area to detect a rise in area temperature, which is indicative of a leak in the RWCU, RCIC, or RHR system piping that exists in the area. At the time of the event, operations personnel confirmed that conditions requiring isolation of the RWCU, RCIC, and RHR systems did not exist, based on a check of the Division 1 reactor building pipe chase high ambient temperature channel and area radiation monitors. Therefore, the isolation signal was determined to be invalid. The NUS/Scientech temperature switch was subsequently removed and the original Riley temperature switch was re-installed. The apparent cause for generation of the trip signal from the new temperature indicating switch was determined to be the presence of signal noise that was not adequately filtered.

"This event was entered into the [Nine Mile Point] corrective action system as Condition Report (CR) 2011-010062. There were no safety consequences or impact on the health and safety of the public as a result of this event."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47549
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DOUG HALL
HQ OPS Officer: VINCE KLCO
Notification Date: 12/23/2011
Notification Time: 10:10 [ET]
Event Date: 12/23/2011
Event Time: 06:10 [CST]
Last Update Date: 12/23/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
BOB HAGAR (R4DO)

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

Event Text

AUTOMATIC REACTOR SCRAM DUE TO A TURBINE TRIP

"At 0610 CST on 12/23/2011 with the reactor at 100% power, River Bend Station experienced an [automatic] reactor scram resulting from a RPS actuation. Following the scram, reactor water level briefly lowered below level 3, resulting in the automatic closure of containment isolation valves in the suppression pool cooling system. This isolation was confirmed to have occurred as designed. The reactor is stable with pressure and temperature being controlled by the feed water system and main steam bypass valves, respectively. The cause of the scram was due to a turbine trip. Initial indications are that the turbine tripped due to a loss speed sensor. All control rods inserted and Reactor Core Isolation Cooling was manually operated for approximately 1 minute and secured,

"The plant is conducting causal investigations to fully understand the cause of the turbine trip. As information becomes available River Bend Station will provide additional information.

"This event is being reported in accordance with 10CFR50.72(b)(iv)(B) as an automatic RPS actuation with the reactor critical."

The safety relief valves momentarily lifted immediately following the scram. The plant electrical distribution system is in a normal shutdown configuration. The scram was uncomplicated.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47550
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: DOUG FOOTE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/23/2011
Notification Time: 15:18 [ET]
Event Date: 12/23/2011
Event Time: 05:00 [PST]
Last Update Date: 12/23/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BOB HAGAR (R4DO)

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

Event Text

EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE

"At 0500 PST 12/23/2011, ERDS communication VPN (Virtual Private Network) link with the NRC was interrupted during an automatic swap between computer servers.

"Restoration of the communication link is expected to be restored by 1430 PST."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 47551
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: JOSEPH TODD
HQ OPS Officer: PETE SNYDER
Notification Date: 12/23/2011
Notification Time: 16:54 [ET]
Event Date: 12/23/2011
Event Time: 16:20 [EST]
Last Update Date: 12/23/2011
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GERALD MCCOY (R2DO)
JOSEPH GIITTER (NRR)
WILLIAM GOTT (IRD)
CHUCK CASTO (R2)
ERIC LEEDS (NRR)
VICTOR MCCREE (R2)
MIKE ARNOLD (DHS)
KEVIN O'CONNELL (FEMA)
ANTHONY PARSONS (DOE)
DAVE TIMMONS (USDA)

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

ALERT DECLARED DUE TO HALON DISCHARGE DURING TESTING

The licensee declared an alert condition based on the inadvertent discharge of Halon gas into their Emergency Bus Room during system testing. Plant operation was unaffected and the unit continued to operate at full power.

There were no injuries or equipment damage due to the event. The licensee observed no fire or flames in the area. The licensee evacuated the area and provided ventilation to disperse the Halon.

The licensee notified the NRC Resident Inspector. Also notified HHS (Jewel Wright).

* * * UPDATE FROM BRIAN WALDSMITH TO DONALD NORWOOD ON 12/23/11 AT 1822 EST * * *

At 1810 EST on 12/23/11, Robinson terminated the Alert condition based on a return to a habitable atmosphere in the Emergency Bus Room. "The cause for the Halon System actuation appears to have been a Human Performance Error. The test/inhibit switch was placed in the incorrect position."

"There were no radiological releases for this event."

The licensee notified state, local and other governmental agencies concerning this event. Notified R2DO (McCoy), NRR EO (Giitter), IR (Gott), DHS SWO (Arnold), FEMA (O'Connell), DOE (Jackson), USDA (Walters), and HHS(Wright).

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Non-Agreement State Event Number: 47552
Rep Org: NIKE IHM, INC.
Licensee: NIKE IHM, INC.
Region: 3
City: ST CHARLES State: MO
County:
License #: GL-704113-15
Agreement: N
Docket:
NRC Notified By: RON WEISS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/24/2011
Notification Time: 20:36 [ET]
Event Date: 09/15/2011
Event Time: [CST]
Last Update Date: 12/24/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
PATTY PELKE (R3DO)
BRIAN McDERMOTT (FSME)

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

Event Text

LOSS OF CONTROL OF GENERAL LICENSED MATERIAL

On August 1, 2011, the licensee removed an Ohmart Measurex Thickness Gauge from service. The gauge contained a Strontium-90 source which had an activity level in 1995 of 100 millicuries. On August 9, 2011, the radioactive source was removed from the gauge by Industrial Maintenance Engineering, Inc., an NRC licensed company. The source was then secured in a DOT-specification steel drum and sealed with a tamper-indicating device placed over the closure ring on the drum lid. The gauge was sold to HGR Industrial Surplus, Inc., a used industrial equipment vendor, who arranged for pick-up at Nike's facility and transportation to its warehouse in Euclid, Ohio. HGR Industrial Surplus, Inc. does not hold an NRC or an agreement state radioactive material license. On September 15, 2011, the gauge and containerized source were transported to HGR's warehouse.

During the week of December 19, 2011, it was discovered that the source was not at the Nike facility. It was determined that the containerized source had been shipped with the gauge to HGR. HGR was immediately contacted by telephone. HGR confirmed that it had the containerized source and that the container had not been opened. The tamper indicating device was still on the closure ring and was still intact. HGR was instructed to not open the container and to place the container in a controlled access area until Nike could arrange return transportation to its facility.

Nike has arranged for RM Wester and Associates, an NRC-licensed company, to retrieve the containerized source. RM Wester representatives will go to the HGR warehouse, prepare the source container for shipping and arrange shipping back to their facility where it will be recycled or disposed of appropriately. This is expected to occur during the week of December 25, 2011.

Nike is conducting an investigation of this incident to determine root causes and will implement appropriate corrective actions to ensure that this does not happen again.

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: 47553
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/26/2011
Notification Time: 16:00 [ET]
Event Date: 12/26/2011
Event Time: 12:50 [EST]
Last Update Date: 12/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
NEIL PERRY (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

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN - SAFETY RELIEF VALVE DECLARED INOPERABLE

"On Monday, December 26, 2011, at 1250 hours, with the reactor at 100% core thermal power, the station entered a 24-hour action statement to initiate a controlled shutdown and be less than 104 psig reactor pressure due to suspected leakage across the first stage of safety relief valve (SRV) RV-203-3D and subsequent declaration of the SRV inoperable due to criteria specified in Pilgrim plant procedure 2.2.23.

"As background; the Pressure Relief System includes four (4) SRVs and two (2) spring safety valves (SSVs). The SRVs discharge through their individual discharge piping, terminating below the minimum suppression pool (torus) water level. The four SRVs and the two SSVs are installed on the Main Steam piping in containment between the reactor pressure vessel and the flow restrictors.

"While at full power, indication of a steam leak across the first stage pilot of RV-203-3D was determined in accordance with criteria specified in procedure 2.2.23. Specifically, the SRV is inoperable if the pilot stage thermocouple temperature is 35 degrees F below its baseline temperature (with a lower decrease at the 2nd stage thermocouple) and cannot he explained by a corresponding downpower. The safety relief valve was subsequently declared inoperable and the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.6.D was entered. Due to the valve being declared inoperable, the station is required to be shutdown and reactor coolant pressure below 104 prig within 24 hours per T.S. 3.6.D.2.

"Currently, preparations are being completed to conduct the reactor shutdown and to initiate safety relief valve repairs.

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

"The USNRC Senior Resident Inspector has been notified."

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