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Event Notification Report for October 14, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/10/2014 - 10/14/2014

** EVENT NUMBERS **


50471 50503 50505 50512 50523 50524 50525 50526 50527 50529 50530 50531
50532

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Agreement State Event Number: 50471
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: FRENCH & PARRELLO
Region: 1
City: WALL TOWNSHIP State: NJ
County:
License #: 507834-RAD110
Agreement: Y
Docket:
NRC Notified By: JACK TWAY
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/19/2014
Notification Time: 10:09 [ET]
Event Date: 09/19/2014
Event Time: [EDT]
Last Update Date: 10/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

The state of New Jersey provided notification that a licensee (French and Parrello) reported a Troxler moisture density gauge (Model 3430, Serial #38931) stolen. The gauge was in the possession of a contractor (employed by Aerotek staffing agency) who has not shown up for work for several days. Attempts have been made to contact the contractor. New Jersey instructed the licensee to contact local law enforcement. The gauge contains 40mCi Am-241 and 8mCi Cs-137.

NJ EVENT: 14-09-19-1107-54

* * * UPDATE FROM JACK TWAY TO HOWIE CROUCH (VIA EMAIL) ON 9/19/14 AT 1231 EDT * * *

The gauge operator contacted the Wall Township Police Department to inform them that he was in possession of the gauge and would be returning it to the licensee today.

Notified R1DO (Lilliendahl), FSME Events Resource (email), and ILTAB (email).

* * * UPDATE FROM JACK TWAY TO HOWIE CROUCH (VIA EMAIL) ON 10/10/14 AT 1019 EDT * * *

The gauge was, in fact, returned to the licensee on 9/19/14. The State of New Jersey received a written report of the event from the licensee and considers this case closed.

Notified R1DO (Bower), FSME Events Resource (email) and ILTAB (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: 50503
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: DESERT NDT LLC
Region: 4
City: ABILENE State: TX
County:
License #: 06462
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/02/2014
Notification Time: 13:55 [ET]
Event Date: 08/01/2014
Event Time: [CDT]
Last Update Date: 10/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - LOCKING MECHANISM FAILURE

The following information was received via facsimile:

"On October 2, 2014, during a complaint investigation, the Agency [Texas Department of Health Services] confirmed allegations that on August 1, 2014, one of the licensee's industrial radiography crews had experienced a mechanical failure on an INC Model IR-100 exposure device that contained a 34 curie Iridium-192 source. Following the last exposure of the day, the source failed to retract into the locked and secure position within the device. The locking mechanism had tripped while the ball stop was outside the lock. The source was inside the s-tube but not in the locked position. The source could not be cranked out of the guide tube either. The key was removed and the radiographer was unable to unlock the camera when the key was re-inserted to retract the source. The radiographer was able to manipulate the locking mechanism so that the lock reset and the source was fully retracted. The licensee reported that its investigation [had determined] no one had exceeded any dose limits as a result of this event. The licensee did not believe it was a reportable event and did not notify the Agency. The exposure device was cleaned and returned to service by the licensee. Further information will be reported in accordance with SA-300 as it is obtained."

Texas Incident #: I-9241

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Agreement State Event Number: 50505
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: SIEMENS MOLECULAR IMAGING
Region: 1
City: KNOXVILLE State: TN
County:
License #: R-47122-I15
Agreement: Y
Docket:
NRC Notified By: RUBEN CROSSLIN
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/03/2014
Notification Time: 12:22 [ET]
Event Date: 09/30/2014
Event Time: 14:35 [EDT]
Last Update Date: 10/08/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAUL KROHN (R1DO)
PAMELA HENDERSON (FSME)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - PRELIMINARY REPORT ON A CONTAMINATED EMPLOYEE

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

"Not much information is known at present, but on September 30th, an employee at Siemens was involved in some type of exposure that resulted in a skin dose contamination. No other spread of contamination has been noted. REACT/s was notified via Siemens and is being used for additional consultation. Awaiting more information from the licensee on [the type of] isotopes involved, a full detailed report of the incident, and their plan of action for the employee. Will update accordingly."

TN ID NO.: TN-14-186

* * * UPDATE ON 10/6/14 AT 1539 EDT FROM SABRINA ROBERTSON TO DONG PARK * * *

The following report from the licensee was received from the State of Tennessee via email:

"Description of the Event

"On 9/30/2014 at approximately 2:35pm, [an employee] was drawing activity to manufacture line sources out of a stock vial of Ge-68. She drew up the required activity into a syringe and when she removed the syringe from the rubber septum of the Ge-68 DTPA stock solution vial, the vial evidently became pressurized and sprayed liquid on to her nasal facial area. Another employee in the area immediately notified the Radiation Safety Officer (RSO).

"Mitigation

"The Radiation Safety Department responded and assisted with decontamination of the affected areas. Decontamination was started approximately 15 minutes after notification of the incident. A water lavage of the facial area was performed and washing of the affected area with hand soap and shaving cream. Wet nasal swabs were used to remove contamination from the nasal passage. After decontamination it was determined that the contamination was confined to the area around her nose and mouth, including inside her nasal passage. Since that
time she has collected all nasal excretions and any sputum, as well as wipes of her skin in the affected area. Radiation surveys are done several times per day to ascertain activity reduction. We are continuing to perform surveys, nasal swabs and urine bioassays until all contamination is removed. To date all urine bioassay samples have been within the range of background. REAC/TS was contacted on October 2, 2014 to determine if they had any further ideas for contamination removal. They recommended the use of make-up removal pads on the face, but did not have any further ideas for removal of contamination from the nasal passage.

"Dose Estimation

"Using the surveys and an initial estimated activity for the contamination event of 76 microCuries in the highest affected area, VARSKIN was used to calculate dose to the skin. Initial calculations estimated the dose to remain below regulatory limits. On October 2, 2014 the Health Physicist running the VARSKIN program noticed that it was not calculating the dose from both Ge-68 and its daughter Ga-68. The calculations were revised and the results exceeded the regulatory limits. The RSO notified the State of Tennessee Division of Radiological Health on October 3, 2014. As of October 3, the calculations showed that skin dose is approximately 132 rem, which exceeds the regulatory limit of 50 rem. [The employee] has been notified of her estimated dose levels and has been involved with decontamination procedures. We will continue to adjust the total dose daily as
surveys are performed. We will submit the final dose number when all contamination is removed and calculations are completed. Our current estimated dose at 10 days from today with no further removal of contamination is 240 rem to the skin."

Notified R1DO (Bower) and FSME Events Resource via email.

* * * UPDATE FROM SABRINA ROBERTSON TO HOWIE CROUCH (VIA EMAIL) AT 0825 EDT ON 10/8/14 * * *

The following update was received from the State of Tennessee via email:

"Summary of the long-term plan for monitoring the employee We will continue to monitor the employee's nasal facial area daily, collect and count wipe samples from skin in the affected area and nasal secretions, collect and count urine bioassay samples for at least the next week (October 14, 2014) unless all measurements are within the range of background before that date. We will assess the value of continued measurements at that time.

"Contamination and projected 10-day calculated skin dose for Monday, October 6 and Tuesday, October 7, 2014. The two areas from which skin dose is being estimated are the bridge of the nose (#1) and the tip of the nose (#2). Measurements are taken using a pancake GM detector (Ludlum 44-9). Skin dose is calculated using VARSKIN.

"October 6 - contamination readings: #1 = 840 cpm; #2 = 4940; calculated skin dose @10 days = 229, 934 mrad
"October 7 - contamination readings: #1 = 740 cpm; #2 = 6040 cpm; calculated skin dose @ 10 days = 239, 070 mrad

"[Licensee staff] are trying to determine a more realistic efficiency for the Ludlum 44-9 GM detector, as we believe it is closer to that of P-32 than to F-18. The use of a higher efficiency will substantially reduce the calculated dose. As you suggested, we have contacted REAC/TS about conduct an independent verification of our skin dose calculation. They informed us they are not able to conduct independent verification. However, they did provide us with consultants who are able to provide this service.

"Finally, as we discussed [with the State of Tennessee], Siemens will provide you with a daily update of the contamination readings and 10-day projected skin dose."

Notified R1DO (Bower) and FSME Events Resource email.

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Agreement State Event Number: 50512
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: DONALD OESTERLE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/06/2014
Notification Time: 16:32 [ET]
Event Date: 10/06/2014
Event Time: [PDT]
Last Update Date: 10/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DON ALLEN (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
MEXICO (EMAI)

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

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

The following was received from State of California via email:

"On October 6, 2014, at approximately 1245 [PDT], [Deleted], RSO [Radiation Safety Officer] of RMA Group, RML [Radioactive Materials License] #2700-36, contacted RHB [Radiological Health Branch] Brea concerning the moisture/density gauge, Troxler, model 3430, serial number 28356 (Cs-137, 0.3 GBq, Am-241, 1.50 GBq) that had been stolen from a transport vehicle in front of a private residence in El Monte at approximately 0700 [PDT]. [The RSO] has contacted the Local Law Enforcement officials in El Monte to request an investigation of the private residence where the Troxler radioactive gauge was taken and to take the report of the authorized user that was in possession of the gauge prior to the theft. A copy of the theft report will be sent to RHB Brea as part of this report. [The RSO] will utilize local papers to attempt to retrieve the stolen gauge as well as notifying local servicing vendors of radioactive gauges to be alert of the serial number of the stolen gauge in case it turns up for any of their services. The investigation will continue to determine if the radioactive gauge can be recovered in a reasonable time frame. This is being reported to the NRC Operations Center as a 24-hour report under 10CFR30.50(b)(2) since the radioactive gauge has been stolen and it cannot be determined what condition the sources are currently in."

California Event No.: 100614

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: 50523
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/11/2014
Notification Time: 00:03 [ET]
Event Date: 10/10/2014
Event Time: 17:17 [CDT]
Last Update Date: 10/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT ORLIKOWSKI (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

MISSING FIRE BARRIER

"During a Fire Penetration walkdown, an opening less than 1[inch] tall under a duct was identified between the Train B Aux Feedwater Pump (AFWP) Room (Unit 1 side) and the Bus150/160 room. This constitutes a missing fire barrier between Fire Area (FA) 32 and FA 37 such that the required degree of separation for redundant safe shutdown trains is lacking.

"A firewatch has been established on the Unit 1 side of the AFWP Room and Bus 150/160 room. The compensatory fire watch will remain in place per F5 Appendix K until the fire barrier is returned to full functional status.

"The discovery of this non-compliance is being reported as an unanalyzed condition as defined by 10CFR50.72(b)(3)(ii)(B).

"The protection of the health and safety of the public was not affected by this issue.

"The licensee has notified the NRC Resident Inspector of this event."

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Power Reactor Event Number: 50524
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/12/2014
Notification Time: 05:22 [ET]
Event Date: 10/12/2014
Event Time: 02:51 [EDT]
Last Update Date: 10/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
FRED BOWER (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 1 Startup 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM DUE TO DECREASING REACTOR WATER LEVEL

"Today at approximately 0250 (EDT) [on 10/12/14], during a planned reactor power ascension with reactor power at approximately 1% of rated thermal power, reactor water level began lowering. Operators inserted a manual SCRAM at 0251 (EDT) in accordance with station procedures. The cause of the lowering reactor level is currently under investigation.

"All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient. The plant is currently shutdown and plant parameters are stable.

"This event is reportable per 10CFR50.72(b)(2)(iv)(B) - 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'"

Decay heat is being released to the main condenser and normal offsite power is being maintained.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 50525
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KYLE SAYLER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/12/2014
Notification Time: 10:29 [ET]
Event Date: 10/12/2014
Event Time: 04:26 [CDT]
Last Update Date: 10/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
DON ALLEN (R4DO)

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

Event Text

POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED OFFSITE FOR MEDICAL TREATMENT

"At 0426 CST [on 10/12/14], a potentially contaminated individual [contract employee] was transported off-site for medical attention at Nemaha County Hospital. The individual had been working in a contaminated area in the main condenser. When the Incident Commander (IC) and Emergency Medical Technicians (EMT) arrived on station the individual was no longer in the contaminated area but was still in the Radiological Controlled Area (RCA). Radiological Protection personnel were dispatched with the individual in the ambulance and surveyed him in route. At 0445 CST, prior to arrival at the hospital, it was confirmed that the individual was not contaminated."

The individual was suffering from a heat related medical condition.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 50526
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEPHEN HARRIS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/12/2014
Notification Time: 12:41 [ET]
Event Date: 10/12/2014
Event Time: 09:44 [EDT]
Last Update Date: 10/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
GERALD MCCOY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 0 Startup 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DURING REACTOR STARTUP

"VEGP [Vogtle Electric Generating Plant] Unit 2 was performing startup and had taken reactor critical at 0929 EDT. When attempting to stabilize power to collect critical data, control rods were inserted with Control Bank D the expected group to insert. Control Bank A inserted instead of Control Bank D. Power had reached 6 E-2 percent as indicated by IR [intermediate range] indication when control room crew performed a manual reactor trip. AFW [auxiliary feed water] was in service to support plant conditions prior to the trip and did not receive any actuation signal. All equipment operated as expected. Unit 2 is currently stable in Mode 3 at normal operating temperature and pressure."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 50527
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MCHUGH
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/12/2014
Notification Time: 13:07 [ET]
Event Date: 10/12/2014
Event Time: 06:00 [EDT]
Last Update Date: 10/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
FRED BOWER (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

SERVICE WATER PUMPS INOPERABLE

"At 0226 [EDT on 10/12/14], the 25 Service Water Pump Traveling Screen differential pressure transmitter high side valve, 2LD2729-HIV was discovered closed while performing the monthly bubbler blow down activity. The associated 25 Service Water Pump was operable at this time. The differential pressure transmitter high side valve, 2LD2729-HIV, in the closed/discovered position would have prevented the operation of the 25 Service Water Traveling Screen due to high differential pressure. The 25 Service Water Traveling Screen needs to be operable to support 25 Service Water Pump operability. 25 Service Water Pump Traveling Water Screen was restored to operable after differential pressure transmitter high side valve, 2LD2729-HIV was reopened. The station subsequently verified all Unit 1 and 2 high side and low side differential pressure transmitter valves positions were correct.

"At 0600 [EDT on 10/12/14], it was identified that the last manipulation of differential pressure transmitter high side valve, 2LD2729-HIV was on 9/7/14. Based on the last known manipulation it is assumed that differential pressure transmitter high side valve, 2LD2729-HIV remained closed from that time until the condition was discovered. Review of other activities performed from 9/7/2014 to present determined that surveillance testing of 21 Service Water Pump resulted in 21, 22, and 23 Service Water Pumps being inoperable on 9/18/2014 for several hours. During that surveillance, combined with the mis-positioned instrument valve on 25 Service Water Pump, five of the six Service Water Pumps would have been inoperable which may have prevented the fulfillment of a safety function.

"This event is being reported under the requirements of 10CFR50.72(b)(3)(v)(B) as 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of systems that are needed to remove residual heat.'

"The licensee has notified the NRC Resident Inspector. No one was injured as a result of the failure of 25 Service Water Traveling Screen inoperability."

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Power Reactor Event Number: 50529
Facility: SURRY
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JESSIE SOTO
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/13/2014
Notification Time: 11:13 [ET]
Event Date: 10/13/2014
Event Time: 07:58 [EDT]
Last Update Date: 10/13/2014
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):
GERALD MCCOY (R2DO)

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

Event Text

AUTOMATIC REACTOR TRIP DUE TO A SPURIOUS OVERPOWER / DELTA TEMPERATURE SIGNAL

"Unit 2 reactor automatically tripped at 0758 [EDT] hours on 10/13/2014, due to a spurious overpower/delta temperature signal on all three channels. The cause of the spurious signal is unknown at this time. Currently, reactor coolant system temperature is being maintained stable at 546 [F] degrees. All three auxiliary feedwater pumps automatically initiated as designed on low-low steam generator level following the trip. All systems responded as expected with the exception [both] of the intermediate range neutron indication[s], which was determined to be under-compensated. The source range indication did not automatically energize and was energized manually. All other systems operated as required.

"This notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) for 4-hour notification of reactor protection system activation and 10 CFR 50. 72(b )(3)(iv)(A) for 8-hour notification of automatic actuation of auxiliary feedwater. The NRC resident has been notified of this event and is on site.

"There were no radiation releases due to this event, nor were there any personnel injuries or contamination events."

There was no testing in progress when the reactor trip occurred. The reactor trip was considered uncomplicated. All control rods fully inserted. Decay heat is being released via main feedwater and the condenser steam dumps. Normal offsite power is available. There was no effect on Surry Unit 1 which continues to operate at 100% power. The licensee is investigating the cause of the overpower/delta temperature actuation.

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Power Reactor Event Number: 50530
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KYLE SAYLER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/13/2014
Notification Time: 15:39 [ET]
Event Date: 10/13/2014
Event Time: 13:27 [CDT]
Last Update Date: 10/13/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DON ALLEN (R4DO)

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

Event Text

OFFSITE NOTIFICATION - DROPPED CONTROL ROD DURING REFUELING OPERATIONS

"At 1530 CDT on 10/13/14, Cooper Nuclear Station will make a press release to the local media. This press release is with regards to the control rod blade which was dropped over the core during refueling operations when the control rod blade fell from the lifting tool and came to rest on the reactor vessel top guide in a section that contained no fuel. This press release was authorized at 1327 CDT."

The control rod was dropped on 10/11/2014. There was no damage to the reactor fuel. The control rod is being replaced and is in the spent fuel pool.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 50531
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMANN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/13/2014
Notification Time: 20:48 [ET]
Event Date: 10/13/2014
Event Time: 14:25 [CDT]
Last Update Date: 10/13/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)

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

Event Text

UNANALYZED CONDITION DUE TO A MISSING FIRE BARRIER

"As part of a fire modeling analysis evaluating a missing fire barrier reported in ENS notification 50475 (a gap where the ventilation duct passes through the wall from the Bus 150/160 room to the Auxiliary Feedwater (AFW) pump room), an additional missing fire barrier was identified. The barrier is related to separation of redundant pressurizer heater banks credited for safe shutdown. For Fire Area 32 (AFW pump room), Group E Pressurizer Heaters are credited for safe shutdown because Group A and Group B Pressurizer Heater cables could be affected by a fire in this area. It was determined that a cable associated with the Group C, D, and E Pressurizer Heaters is routed in Fire Area 32. Therefore, a fire in Fire Area 32 could affect all five Pressurizer Heater Groups. An evaluation has previously demonstrated that Mode 3 Hot Standby could be maintained with no charging pumps or pressurizer heaters available, but it has not been determined if Mode 5 could be achieved. Therefore, this missing fire barrier meets the reporting criteria for 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety.

"The protection of the health and safety of the public was not affected by this issue. Unit 1 is in mode 6 and no fire has occurred. Compensatory measures (fire watches) are in place for Fire Area 32.

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

Unit 2 has a different cable routing and is not affected.

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Power Reactor Event Number: 50532
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: THOMAS YURKON
HQ OPS Officer: VINCE KLCO
Notification Date: 10/14/2014
Notification Time: 01:30 [ET]
Event Date: 10/13/2014
Event Time: 19:35 [EDT]
Last Update Date: 10/14/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
FRED BOWER (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

HIGH PRESSURE CORE INJECTION DEGRADED ACCIDENT MITIGATION CAPABILITY

"During the plant response to the trip of the B Recirculating water pump, reactor water level rose to the HPCI [High Pressure Core Injection] high water level trip setpoint as indicated on the associated instrumentation. With this high water level trip actuated, the HPCI high drywell pressure initiation signal would not have allowed the HPCI system to perform its intended safety function if required. If the HPCI system received the low water level initiation signal, the system would have been able to perform Its intended safety function. This high water level signal was actuated from 1935 [EDT] until reset at 1940 [EDT]. This is reportable under 50.72(b)(3)(v)."

The licensee notified NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, October 14, 2014
Tuesday, October 14, 2014