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Event Notification Report for November 24, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/23/2015 - 11/24/2015

** EVENT NUMBERS **


50846 51537 51539 51540 51541 51542 51559 51560 51561 51562 51563

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Part 21 Event Number: 50846
Rep Org: CURTISS WRIGHT
Licensee: QUALTECH NP, HUNTSVILLE
Region: 1
City: HUNTSVILLE State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BAMBI RHOADES
HQ OPS Officer: VINCE KLCO
Notification Date: 02/23/2015
Notification Time: 17:05 [ET]
Event Date: 02/20/2015
Event Time: [CST]
Last Update Date: 11/23/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
STEVE ROSE (R2DO)
PART 21/50.55 REACT (EMAI)

Event Text

PART 21- POTENTIAL DEFECT IN A SOCKET USED SEPARATELY OR IN A CONNECTOR KIT

The following information was received by facsimile:

"[The Curtiss-Wright] letter is issued to provide notification of a potential defect in Socket (PIN: GB-1 A-5) sold separately or supplied as part of a GRAYBOOT 'A'' (GB-1A) Connector Kit. There is one affected lot of Sockets (Lot#: 092413). The potential defect is that the socket was not zone annealed which will possibly affect the ability to crimp the socket onto the wire conductor. Zone annealing is specified for the crimp barrel to return the crimp barrel to a soft condition to counteract the effects of previous heat treating required to develop spring tension in the socket tines that mate with the pin contact.

"The nine affected Customers and their associated Purchase Orders are listed below. All Customers will be notified by February 24, 2015 and supplied with the information we have at this time.

1. Vattenfall- Forsmark Kraftgrupp AB, P.O. 4500301916
2. Vattenfall- Forsmark Kraftgrupp AB, P.O. 4500301916
3. Decon International (HK) Ltd., P.O. DIL00590
4. Ringhals AB, P.O. 641511-090
5. Dremel Inc., P.O. 13-040
6. Bruce Power L.P., P.O. 00185336
7. Kanata Electronic Services Limited, P.O. 34513
8. Meggitt Safety Systems Inc., P.O. 104057
9. Meggitt Safety Systems Inc., P.O. 104345

"Based on our recent in-house testing of socket Lot #: 092413, the defective sockets appear to be more difficult to crimp than sockets that have been zone annealed. Some of the Lot #: 092413 sockets showed cracking or bending under magnification. We did not have any sockets actually break apart during the crimping process. All the test specimens crimp barrels remained intact. If a severe fracture had occurred at the time of crimping we believe it would have been very noticeable to the technician installing the contact. Once crimped, the socket appears to function well by conducting electricity and exhibiting acceptable electrical resistance. Many of these sockets from Lot #: 092413 may already be installed. Customers will need to determine if replacing the sockets is required.

"All customers listed may choose to replace already installed sockets. It is requested that any uninstalled sockets be returned for replacement. All customers requesting replacement sockets should contact Bambi Rhoades at brhoades@curtisswright.com or by phone at 256-924-7424 for arrangements or Jim Tumlinson, contact information listed below.

"Send all defective sockets to QualTech NP; 120 West Park Loop; Huntsville, AL 35806. Customer can contact Cindy Tidwell at ctidwell@curtisswright.com or by phone at (256) 924-7436 for help with international or freight collect shipping instructions. Ship all defective sockets collect to UPS Account No. 35254E.

"Additional details, corrective actions and root causes will be provided once our report of the recent testing complete. If you require additional information or would like to discuss this further please do not hesitate in contacting [Jim Tomlinson; Office Phone: (256) 924-7429; email:jtomlinson@curtisswright.com]."

* * * UPDATE AT 1304 EST ON 11/23/2015 FROM BAMBI RHOADES TO MARK ABRAMOVITZ * * *

The following report was received via fax:

"This letter provides for the formal close out of notification QTHuntsville 10CFR21-2015-01. The initial notification was made on February 20, 2015 (NRC Event# 50846). All customers were notified and received the test data. All customers were given the opportunity to receive replacement sockets, as they deemed necessary. These replacement parts have been delivered. All actions have been completed.

"To prevent reoccurrence in the future, the following internal documents have been revised. The procurement and dedication guidelines for both the original GRAYBOOT and GRAYBOOT 'A' connectors were revised.

"GRAYBOOT 'A' Report No.: SAIC-TR-l038.2-03 currently at Revision P, dated July 16, 2015. GRAYBOOT Report No.: EGS-TR-880708-01 currently at Revision Y, dated July 16, 2015.

"Both the reports above now contain additional destructive testing as well as visual inspection under magnification to provide more reasonable assurance that the annealing is acceptable. Also, additional training was conducted at our sub-supplier and additional requirements have been added to our purchase orders to prevent any reoccurrence .

"Based on the above information and corrective actions, this part 21 file is considered closed. If you would like to discuss this further, please contact Tony Gill (QualTech NP Quality Assurance Manager) at 256-924-7438 (office). 256-426-4558 (mobile) or tgill@curtisswright.com.

Notified the R2DO (Ernstes) and Part-21 Group (via e-mail).

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Agreement State Event Number: 51537
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: NONDESTRUCTIVE & VISUAL INSPECTION LLC
Region: 4
City: CARTHAGE State: TX
County:
License #: 06162
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/13/2015
Notification Time: 17:29 [ET]
Event Date: 11/11/2015
Event Time: [CST]
Last Update Date: 11/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ANGELA MCINTOSH (NMSS)
PAT MILLIGAN (NSIR)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHER OVERDOSE

The following report was received via e-mail:

"On November 13, 2015, a licensee notified the Agency that one its radiographers had an overexposure. The licensee stated the radiographer cranked out the source and waited the time for the shot, then thought he cranked the source back into the camera. When he went to retrieve the film, the radiographer noticed his survey metered was pegged off scale. He immediately went back to the truck and checked his pocket dosimeter and it was off scale also. He picked up the crank and retracted the source. He checked the area with the survey meter and the radiation level had dropped. He informed his supervisor that night and the corporate radiation safety officer had the radiographers monitoring badge sent off for processing. The badge reading was DDE [Deep Dose Equivalent] of 11,453 mRem and LDE [Lens of the eye Dose Equivalent] 11,494 mRem. The radiographer is being interviewed of the details of the incident and a detailed report will be provided. The radiographer has not had any health effects at this time nor are any expected."

This incident occurred on 11/11/2015 at a job site in Pecos, TX.

Texas Incident: I-9358

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Agreement State Event Number: 51539
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: TUV RHEINLAND INDUSTRIAL SOLUTIONS
Region: 1
City: CHARLESTON State: TN
County:
License #: R-A 1026-A25
Agreement: Y
Docket:
NRC Notified By: ANDREW HOLCOMB
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/16/2015
Notification Time: 12:59 [ET]
Event Date: 10/22/2015
Event Time: 11:00 [EST]
Last Update Date: 11/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAN SCHROEDER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA FAILED TO FUNCTION PROPERLY

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

"On October 22, 2015, a radiography device belonging to TUV Rheinland Industrial Solutions failed to function properly due to a jammed selector ring; this occurred when the operator attempted to rotate from the connect to the lock position. The source was fully retracted at the time of the incident. The device was a Sentinel 880D (SN# D2620) with 29.4 Ci of Se-75 (Source #SE4627). The licensee placed the device 'out of service'. On October 26, 2015, the device was shipped back to QSA Global for repair. A follow-up report will be submitted upon receipt of further information."

Tennessee State Event Report ID No: TN-15-166

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Agreement State Event Number: 51540
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: MANUFACTURING SCIENCES CORPORATION
Region: 1
City: OAK RIDGE State: TN
County:
License #: S-01046
Agreement: Y
Docket:
NRC Notified By: ANDREW HOLCOMB
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/16/2015
Notification Time: 15:53 [ET]
Event Date: 11/16/2015
Event Time: 09:20 [EST]
Last Update Date: 11/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAN SCHROEDER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
PAMELA HENDERSON (NMSS)

Event Text

AGREEMENT STATE REPORT - FIRE IN AN OFF GAS DUST COLLECTOR

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

"A fire occurred in an off gas dust collector and particulate filtration system used for ventilation from a process providing oxidation of metal depleted uranium chips. Alarm engaged and fire suppression system engaged. The local fire department responded and reinforced suppression. The fire department departed by 11:20 AM. Initial indications indicate no releases to the environment based on visual indications and stack monitoring systems not alarming. Negative pressure to the building was maintained. Smears taken outside of the building and radiologically controlled area does not indicate any elevated activity outside of the building. Air samples are being pulled and analyzed for workplace and air effluent stacks. Bioassays were being conducted to assess worker and firemen. A follow-up report will be submitted upon receipt of further information."

Tennessee State Event Report ID No: TN-15-167

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Agreement State Event Number: 51541
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: TERRACON CONSULTANTS, INC.
Region: 1
City: CHATTANOOGA State: TN
County:
License #: R-33105-L09
Agreement: Y
Docket:
NRC Notified By: ANDREW HOLCOMB
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/16/2015
Notification Time: 15:53 [ET]
Event Date: 11/16/2015
Event Time: 11:15 [EST]
Last Update Date: 11/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAN SCHROEDER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED DENSITY MOISTURE GAUGE

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

"On November 16, 2015, a neutron soil density and moisture gauge belonging to Terracon Consultants, Inc. was run over by a dump truck. The source was fully retracted at the time of the incident. Initial surveys have indicated that the source remained in the shielded position after the incident. A leak test has been taken and sent off for evaluation. The device was a CPN MCIDR (SN# MD40407363) with 50 mCi of Am-241 Be (Source #7363) and 10 mCi of Cs-137 (Source #7363). The licensee placed the device 'out of service'. On November 16, 2015, the device will remain in shielded storage until Terracon Consultants, Inc. decides what they are going to do with it. A follow-up report will be submitted upon receipt of further information."

Tennessee State Event Report ID No: TN-15-168

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Agreement State Event Number: 51542
Rep Org: NORTH DAKOTA DEPARTMENT OF HEALTH
Licensee: TANEY ENGINEERING, INC.
Region: 4
City: MINOT State: ND
County:
License #: 33-53306-01
Agreement: Y
Docket:
NRC Notified By: KAREN DEIBERT
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/16/2015
Notification Time: 16:56 [ET]
Event Date: 11/15/2015
Event Time: 23:54 [MST]
Last Update Date: 11/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
CNSC (CANADA) (FAX)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST DENSITY MOISTURE GAUGE

The following was received from the State of North Dakota via email:

"Taney Engineering, Inc. (Taney) reported the loss of a moisture/density gauge (Troxler Model No. 3430, Serial No. 30530) that contained a 1.48GBq (40mCi) Am-241:Be source (Serial No. 47-27626) and a 0.3 GBq (8 mCi) Cs-137 source (Serial No. 77-13400) currently licensed under North Dakota Department of Health License No. 33-53306-01. This event was initially reported to the Minot, North Dakota Police Department at 11:54 P.M. on Sunday, 11/15/2015. At that time, the field inspector noticed the Troxler nuclear density gauge designated above to be missing from the bed of his truck at the end of the day. The field inspector stated the nuclear density gauge was in the yellow transport box secured in the bed of his truck with chains and locks to both side handles and locks on the transport case when he stopped at Wal-Mart located at 3900 S Broadway St., Minot, ND 58701. When he returned from the store, the equipment was still secure in the bed of his truck. He drove to Buffalo Wild Wings in the adjoining parking lot located at 3820 S Broadway St., Minot, ND 58701 at approximately 11:35 P.M. He placed an order for take-out and waited for food inside. He arrived home in Minot, ND 58701 before 11:50 P.M. to drop off groceries before checking in the nuclear gauge and discovered company equipment, including the gauge, missing from the back of his truck. He immediately notified the Minot Police Department, filed incident report No. 2015-00036173. He then notified Troxler Electronic Laboratories at 877-876-9537. He than notified Taney."


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: 51559
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FRANK SCHULTE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2015
Notification Time: 11:52 [ET]
Event Date: 11/23/2015
Event Time: 08:44 [EST]
Last Update Date: 11/23/2015
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):
MIKE ERNSTES (R2DO)

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

Event Text

MANUAL REACTOR TRIP AFTER PARTIAL MSIV CLOSURE

"At 0820 EST on 11/23/2015, Sequoyah Unit 1 was at 100% power when operators identified the Loop #3 Main Steam Isolation Valve (MSIV) came off its full open seat. This was evidenced by no OPEN indication on the main control board, dual indication on the post accident monitoring panel, and a change in both Tavg and steam pressure. Operators were dispatched locally to the MSIV and to the battery board room to investigate if a cause could be identified for the MSIV movement. The field investigation identified no issues. The operating crew manually tripped the reactor at 0844 EST due to an increasing Tavg-Tref mismatch.

"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically initiated as expected from the feedwater isolation signal.

"Unit 1 is currently being maintained in Mode 3 at normal operating temperature and pressure, approximately 547 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators and decay heat removal via the condenser steam dumps.

"There is no indication of any primary to secondary leakage. All control rods fully inserted on the reactor trip and remain inserted. The electrical alignment is normal with shutdown power supplied from off-site power. There is no operational impact to Unit 2 as it continues through the refueling outage with the core off-loaded.

"There was no impact on public health and safety. Post-trip investigation is in progress and planned restart timeline has not yet been determined.

"The licensee notified the NRC Resident Inspector."

All control rods fully inserted during the reactor trip. The atmospheric steam dumps did operate during the transient and then shut. After the trip, the MSIV re-opened.

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Power Reactor Event Number: 51560
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MATTHEW QUICK
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2015
Notification Time: 15:03 [ET]
Event Date: 11/23/2015
Event Time: 10:40 [CST]
Last Update Date: 11/23/2015
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):
AARON McCRAW (R3DO)

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

REACTOR SCRAM DUE TO A REACTOR RECIRCULATION PUMP LOCKOUT

"At 1040 CST, with the plant at 100% power, a lockout of the 11 recirculation pump occurred. Following the 11 recirculation pump lockout, at 1041 CST, a reactor scram and a Group 1 isolation occurred. All Main Steam Isolation Valves closed as a result of the Group 1 isolation signal. HPCI [High Pressure Core Injection] has been placed in service to control RPV [Reactor Pressure Vessel] pressure. HPCI did not inject into the RPV and was not needed to control RPV level.

"At 1104 CST, a Group 2 containment isolation signal was received due to RPV level less than +9 inches. The Group 2 isolation signal has been reset.

"The cause(s) of the 11 recirculation pump lockout, the reactor scram, and the Group 1 isolation are currently not known and are under investigation.

"This event is being reported under 50.72(b)(2)(iv)(B) due to the actuation of the Reactor Protection System when the reactor is critical.

"For the following reasons, this event is also being reported under 50.72(b)(3)(iv)(A):
1) This event resulted in a valid Group 2 containment isolation signal,
2) Since the cause of the Reactor Protection System actuation is not known, the event is being reported as a valid actuation of the Reactor Protection System, and
3) Since the cause of the Group 1 isolation is not known, the event is being reported as a valid primary containment isolation signal affecting multiple Main Steam Isolation Valves.

"All systems have responded as expected, all control rods fully inserted following the Reactor Protection System actuation. The plant is currently shutdown in mode 3, RPV pressure and RPV level are stable. This event did not result in any radiological release from the plant. This event did not challenge the health and safety of the public.

"The NRC Resident Inspector has been notified."

The plant is in its normal shutdown electrical lineup. HPCI is in pressure suppression mode with RHR cooling the suppression pool.

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Power Reactor Event Number: 51561
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SCOTT BRAY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2015
Notification Time: 17:00 [ET]
Event Date: 11/23/2015
Event Time: 09:30 [EST]
Last Update Date: 11/23/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MIKE ERNSTES (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 N 0 Cold Shutdown 0 Cold Shutdown

Event Text

POSITIVE FITNESS-FOR-DUTY TEST

A non-licensed contract supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 51562
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: BRYAN HEAVILIN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2015
Notification Time: 17:50 [ET]
Event Date: 11/24/2015
Event Time: 13:30 [PST]
Last Update Date: 11/23/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARK HAIRE (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

OFFSITE NOTIFICATION OF FUEL DEFECTS

"At approximately 1100 PST, Columbia Generating Station (CGS) planned to make a non-required notification to Energy Facility Site Evaluation Council (EFSEC) regarding indications of two fuel defects. This condition has not affected full power operation at CGS, and there is no impact to the health and safety of the public or to the environment. CGS plans on making this notification to EFSEC on November 24, 2015 at 1330 PST.

"This condition is being reported pursuant to 10 CFR 50.72 (b)(2)(xi).

"The licensee notified the NRC Resident Inspector."

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Power Reactor Event Number: 51563
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN OSBORNE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/23/2015
Notification Time: 22:41 [ET]
Event Date: 11/23/2015
Event Time: 21:48 [EST]
Last Update Date: 11/24/2015
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMES DWYER (R1DO)
DAN DORMAN (R1RA)
WILLIAM DEAN (NRR)
BERNARD STAPLETON (IRD)

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

Event Text

UNUSUAL EVENT DECLARED DUE TO REACTOR COOLANT SYSTEM LEAKAGE

"At 2148 EST on November 23, 2015, Salem Unit 2 declared an Unusual Event due to reactor coolant system leakage greater than 10 gallons per minute. While performing troubleshooting to determine the source of leakage from the Emergency Core Cooling System high head safety injection piping, a motor operated valve was opened and the high head piping relief valve lifted. Indications in the control room calculated the leak rate at 16 gallons per minute based on the change in Pressurizer level. The leak was terminated when the motor operated valve was closed and the relief valve reseated. The time [duration] of the leak was about one minute."

The licensee notified the NRC Resident Inspector.

Notified DHS SWO, FEMA Ops Center, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA.

* * * UPDATE AT 0105 EST ON 11/24/15 FROM BILLY MOWER TO JEFF HERRERA * * *

The licensee terminated the Unusual Event at 0100 EST on 11/24/15. The licensee will be cooling down and depressurizing to mode 5 in order to replace the affected valve.

The licensee will be notifying the NRC Resident Inspector as well as the New Jersey State police, Delaware State Police and local emergency dispatch.

Notified the R1DO (Dwyer), NRR EO (Morris), IRD MOC (Stapleton), DHS SWO, FEMA Ops enter, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA.

* * * UPDATE FROM JOHN OSBORNE TO JOHN SHOEMAKER AT 0341 EST ON 11/24/15 * * *

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D). 'Any event of condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident,' due to inoperability of both trains of the Emergency Core Cooling System high head safety injection systems.

"The unusual event was exited at 0100 [EST] on November 24th, 2015, when the Emergency Core Cooling System high head safety injection piping inlet valves were closed, ensuring isolation of the relief valve. The criteria for exit was leakage rate was below the 10 GPM rate. The plant is in mode 3 cooling down to mode 5.

"The licensee notified the states of New Jersey and Delaware. Lower Alloways Township, and the NRC Resident Inspector."

Notified the R1DO (Dwyer).

Page Last Reviewed/Updated Tuesday, November 24, 2015
Tuesday, November 24, 2015