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Event Notification Report for September 12, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/11/2017 - 09/12/2017

** EVENT NUMBERS **


52756 52881 52944 52952 52956 52961 52962

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Part 21 Event Number: 52756
Rep Org: CURTISS WRIGHT FLOW CONTROL CO.
Licensee: CURTISS-WRIGHT
Region: 1
City: HUNTSVILLE State: AL
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: TONY GILL
HQ OPS Officer: JEFF HERRERA
Notification Date: 05/15/2017
Notification Time: 18:55 [ET]
Event Date: 03/16/2017
Event Time: [CDT]
Last Update Date: 09/11/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
MIKE ERNSTES (R2DO)
PART 21/50.55 REACTO (EMAI)

Event Text

PART 21 - POTENTIAL DEFECT IN GRAYBOOT SOCKET CONTACTS

The following information was received via email:

"This letter is issued to provide an interim notification of a potential defect in certain lots of Grayboot socket contacts supplied with EQ qualified Grayboot Connector Kits. On March 16, 2017, Curtiss-Wright, Nuclear Division, Huntsville Operations was contacted by Georgia Power Vogtle Nuclear Power Plant concerning a potential defect where the socket contact tines were in a relaxed state.

"Although we have completed some testing and verification activities, additional testing is in progress now and will provide necessary information to complete our evaluation. Current testing will be completed and final conclusions made by May 31, 2017.

"At this time, based on test results, evaluations and operating experience, Curtiss Wright is confident that any potentially affected Grayboot Assemblies will continue to perform their intended safety functions. As such, if the final recommendation is to replace the potentially defective socket contact, this can be accomplished during subsequent routine maintenance activities.

"This notification is being made to comply with 60 day interim reporting requirements as defined in 10 CFR 21.21(a)(2).

"For additional information, please contact Samuel Bledsoe, EGS Products Engineering Manager (1-256-690-7852) or Tony Gill, EGS and Trentec Quality Assurance Manager (1-256-426-4558)."

* * * UPDATE PROVIDED BY TONY GILL TO JEFF ROTTON AT 1813 EDT ON 05/31/2017 * * *

The following information was provided via email:

"This letter is issued to provide final findings associated with a potential defect concerning GRAYBOOT socket contacts. This issue was initially identified in an interim report dated May 15, 2017. As documented previously, Curtiss-Wright, Nuclear Division, Huntsville Operations was contacted by Georgia Power Vogtle Nuclear Power Plant on March 16, 2017 concerning a potential defect wherein GRAYBOOT socket contact tines were in a relaxed state. This notification of a potential defect concerns model GB-1 GRAYBOOT kits supplied with two-tined, silver-plated, 12-14 AWG socket contacts.

"Based upon this scope, potentially affected kits/parts are: 1. GB-1(12-14) GRAYBOOT kits, 2. GB-1 (12-14/ 16-18) GRAYBOOT kits, and 3. GB-1-6 GRAYBOOT 12-14 AWG socket contacts.

"This issue does not affect the following: 1. Any GRAYBOOT 'A' kits/parts, 2. Any model GB-2 or GB-3 GRAYBOOT kits/parts, or 3. Any model GB-1 GRAYBOOT kits/parts with 16-18 AWG socket contacts.

"Our evaluation is documented in Report No. EGS-TR-880708-15 and is available for review at our facility in Huntsville, AL. The results identify the most likely root cause is improper heat treating of the socket contacts during manufacturing. Additional testing and analysis was performed to confirm that any affected GRAYBOOT assemblies can still preform their safety-related function and do not present a substantial safety hazard .

"The findings outlined in Report No. EGS-TR-880708-15 provide a high level of confidence that affected GRAYBOOT assemblies do not present a substantial safety hazard. This position is further validated by the lack of negative operating experience over the last 20 plus years from properly installed GRAYBOOT assemblies. However, this condition causes the contact to be more susceptible to damage from handling during connection and disconnection, and therefore the following actions are recommended:

"1. Any affected sockets in inventory should be replaced. Affected sockets in service should be replaced during routine maintenance activities.

OR

"2. In lieu of replacement, it is acceptable to perform the following [steps 1-3] to confirm a separation force greater than 0.19 lbs. This is consistent with existing Curtiss-Wright dedication acceptance criteria. It is recommended that any contacts not meeting this criteria be replaced. 1. Crimp a spare pin contact to an appropriate piece of wire. 2. Connect a force gage or 0.19 lbs. of static weight to the opposite end of the wire. 3. Insert the pin into the socket and confirm that the pin does not separate from the socket under a minimum load of 0.19 lbs.

"To confirm this deviation is not present in existing inventory or in future purchased lots, the following corrective actions have been or will be implemented by Curtiss-Wright: 1. Micro hardness testing was performed on all socket contact lots in inventory to verify their acceptability. Results confirmed that all lots were acceptable. 2. Acceptance criteria for dedication of socket contacts will be revised to include verification of acceptable contact hardness. This corrective action will be completed by June 9, 2017. No dedication of socket contacts will be performed until this corrective action is complete.

"A list of affected utilities and associated purchase orders is being developed and will be complete and submitted by June 9, 2017.

"For additional information, please contact Samuel Bledsoe, EGS Products Engineering Manager (1-256-690-7852) or Tony Gill, EGS and Trentec Quality Assurance Manager (1-256-426-4558)."

Notified R1DO (Bower), R2DO (Shaeffer), R3DO (Daley), R4DO (O'Keefe) and Part 21 Operating Reactors Group via email.

* * * UPDATE AT 1859 EDT ON 06/09/17 FROM TONY GILL TO JEFF HERRERA * * *

The following update was received via email:

"On May 31, 2017, Curtiss-Wright, Nuclear Division, Huntsville Operations issued a letter documenting final findings regarding a potential defect concerning model GB-1 GRAYBOOT kits supplied with two-tined, silver-plated, 12-14 AWG contacts. Please find that letter attached.

"Pursuant to the attached letter, please find attached a list of affected purchase orders.

"For additional information, please contact Samuel Bledsoe, EGS Products Engineering Manager (1-256-690-7852) or Tony Gill, EGS and Trentec Quality Assurance Manager (1-256-426-4558).

List of Sites Affected:
Arkansas Nuclear 1
Bruce Nuclear Power Development
Brunswick
Callaway
Calvert Cliffs
Clinton
Columbia
Cooper
CTEAM/CRIT
Davis-Besse
Diablo Canyon
Duane Arnold
Farley
FMM
Fort Calhoun
Gentilly
Ginna
Haddam Neck
Harris
Indian Point
Kewaunee
La Salle
Limerick
Millstone
Nine Mile Point
North Anna
Oconee
Oyster Creek
Peach Bottom
Pilgrim
Point Beach
Prairie Island
Quad Cities
River Bend
Saint Lucie
San Onofre
Sizewell B
South Texas
Summer
Turkey Point
Vermont Yankee
Vogtle
Waterford
Wolsong
Zion

Notified R1DO(Welling), R2DO(Suggs), R3DO(Orlikowski), R4DO(Rollins), Part-21 Reactors (via email).

* * * UPDATE AT 1612 EDT ON 09/11/17 FROM TONY GILL TO BETHANY CECERE * * *

The following information was received via email:

"At initial issuance, the evaluation documented in Report No. EGS-TR-880708-15 presented metallurgical analysis as well as thermal, functional and seismic testing. This report has been revised to include cycle aging, functional testing and pull-out force. Test results confirm that affected socket contacts will continue to perform their intended safety function throughout their qualified life.

"Based on these final findings, no further actions are recommended for the potentially affected utilities previously notified. Any potentially affected socket contacts, either in inventory or installed, are acceptable for use in their intended safety-related application.

"It is recommended that all utilities confirm that installation and handling of GRAYBOOT assemblies is in accordance with Installation Instructions EGS-TR-880707-02.

"For additional information, please contact Samuel Bledsoe, EGS Products Engineering Manager (1-256-690-7852) or Tony Gill, EGS and Trentec Quality Assurance Manager (1-256-426-4558)."

Notified R1DO(Dentel), R2DO(Michel), R3DO(Riemer), R4DO(Groom), Part-21 Reactors (via email).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 52881
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARK BUSSELL
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/01/2017
Notification Time: 17:00 [ET]
Event Date: 08/01/2017
Event Time: 09:34 [CDT]
Last Update Date: 09/11/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION STEAM SUPPLY VALVE FAILED TO REPOSITION

"At 0934 CDT, while appropriately removed from service for pre-planned testing, the High Pressure Coolant Injection (HPCI) inboard steam isolation valve, MO-2238, valve position indication was found to be inadequate. As a result, MO-2238 was declared inoperable in accordance with Technical Specification (TS) 3.6.1.3. This resulted in a condition that caused the HPCI system to be inoperable.

"The cause of the inadequate valve position indication is currently being investigated. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D).

"The NRC Resident Inspector has been informed."

* * * RETRACTION ON 09/11/17 AT 1144 EDT FROM BOB MURRELL TO BETHANY CECERE * * *

"The purpose of this notification is to retract a previous report made on 8/1/17 at 1700 (EDT) (EN 52881). NRC notification was initially made as a result of the High Pressure Coolant Injection (HPCI) inboard steam isolation valve, MO-2238, valve position found to be inadequate.

"Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the condition observed on 8/1/17 for MO-2238 did not exist prior to removing the system from service for pre-planned testing, but was observed during post maintenance testing. Consequently, the failure does not meet the reporting requirements of 10 CFR 50.72 or 10 CFR 50.73.

"The NRC Resident Inspector has been notified."

Notified the R3DO (Riemer).

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Non-Agreement State Event Number: 52944
Rep Org: VARIAN MEDICAL SYSTEMS
Licensee: VARIAN MEDICAL SYSTEMS
Region: 1
City: GLENS FALLS State: NY
County:
License #: 45-30957-01
Agreement: Y
Docket:
NRC Notified By: KATHARINE ARZATE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/01/2017
Notification Time: 13:30 [ET]
Event Date: 08/30/2017
Event Time: [EDT]
Last Update Date: 09/08/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JON LILLIENDAHL (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
CNSC (CANADA) (FAX)

This material event contains a "Category 3 " level of radioactive material.

Event Text

IRIDIUM-192 SOURCE LOST DURING SHIPMENT

A 3.792 Curie Ir-192 source was removed from a Varian High Dose Rate afterloader and prepared for shipment by common carrier. The packaged source was picked up from Glens Falls Hospital in Glens Falls, New York by a representative of the common carrier on August 21, 2017. The destination of the source was to Alpha-Omega Services in Vinton, Louisiana for disposal. The source arrived at the common carrier's local station in Manands, New York on August 22, 2017. When the licensee checked package tracking information on August 30, 2016, the licensee noted that the package indicated that it was still at the common carrier's local station.

The licensee attempted to contact the common carrier on August 30, 2017 without success. The licensee successfully contacted the common carrier on August 31, 2017 and the common carrier initiated a 'station trace' at that time. At the present time the source has not been located. The common carrier is still searching.

* * * UPDATE ON 9/8/17 AT 1531 EDT FROM KATHARINE ARZATE TO DONG PARK * * *

The Ir-192 source was located by the common carrier at 1837 PDT on 9/1/17. The package was delivered to the recipient on 8/29/17.

Notified R1DO (Dentel), NMSS Events Notification, and Canada.

THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL

Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)

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Power Reactor Event Number: 52952
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: TIM JONES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/08/2017
Notification Time: 00:06 [ET]
Event Date: 09/07/2017
Event Time: 23:14 [EDT]
Last Update Date: 09/11/2017
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ERIC MICHEL (R2DO)
JEFFERY GRANT (IRD)
CATHERINE HANEY (R2RA)
BRIAN HOLIAN (NRR)

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

NOTIFICATION OF UNUSUAL EVENT - HURRICANE WARNING

"At 2300 today, the National Weather Service issued a hurricane warning for the area including Turkey Point Nuclear Units 3 & 4. On that basis, a Notice of Unusual Event was declared at 2314 [EDT]. In anticipation of severe weather, the site has completed proceduralized high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants.

"Both units are currently stable at 100% power level.

"The NRC Resident Inspector has been informed."

No safety systems are out of service. The electrical grid is stable but grid risk is high.

Notified DHS, FEMA, NICC, and NSSA (e-mail).

* * * UPDATE AT 0458 EDT ON 09/11/17 FROM TIM JONES TO JEFF HERRERA * * *

"At 0400 [EDT] on 09/11/17, conditions at Turkey Point Nuclear have met established exit criteria to downgrade the Notice Of Unusual Event (NOUE). The previously reported EAL [Emergency Action Level] has been exited."

"The NRC Resident Inspector has been informed."

Notified the R2DO (Michel) and R2OC (Miller), IRDMOC (Gott), NRREO (Miller), DHS, DOE, FEMA, HHS, USDA, EPA, FDA, DHS NICC, and NSSA (e-mail).

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Power Reactor Event Number: 52956
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DALE THOMAS
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/08/2017
Notification Time: 17:51 [ET]
Event Date: 09/08/2017
Event Time: 17:14 [EDT]
Last Update Date: 09/11/2017
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ERIC MICHEL (R2DO)
BRIAN McDERMOTT (NRR)
LAURA DUDES (R2 D)
JEFFERY GRANT (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

NOTIFICATION OF UNUSUAL EVENT - HURRICANE WARNING

"At time 1700 [EDT] today, the National Weather Service issued a Hurricane Warning for the area including the St. Lucie Nuclear Power Plant. On that basis, a Notice of Unusual Event was declared at time 1714 [EDT]. In anticipation of severe weather, the site has completed proceduralized high wind preparations.

"Both units are currently stable at 100% power."

The licensee notified both State and local agencies and has informed the NRC Resident Inspector.

No safety-related systems are out of service. The electrical grid is stable.

Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

* * * UPDATE ON 9/9/17 AT 1743 EDT FROM DALE THOMAS TO S. SANDIN * * *

"At 1701 [EDT] today (09/09/17), a 24-hour update was made to state and local governments following the National Weather Service issuing yesterday's hurricane warning for the area including St. Lucie Plant. On that basis, a Notice of Unusual Event was declared yesterday (09/08/17) at 1714 [EDT]. There are no changes in plant status for either Unit.

"In anticipation of severe weather, the site previously completed high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants.

"Both units are currently stable at 100% power level and will remain at that power since hurricane force winds are not currently projected to reach St. Lucie Plant.

"The NRC Resident Inspector has been informed."

Notified R2DO (Michel).

* * * UPDATE ON 9/10/17 AT 1730 EDT FROM DALE THOMAS TO DONG PARK * * *

"At 1648 [EDT] today (09/10/17), a 24-hour update was made to state and local governments following the National Weather Service issuing Friday's hurricane warning for the area including St. Lucie Plant. On that basis, a Notice of Unusual Event was declared yesterday (09/08/17) at 1714 [EDT]. There are no changes in plant status for either Unit.

"In anticipation of severe weather, the site previously completed high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants.

"Both units are currently stable at 100% power level and will remain at that power since hurricane force winds are not currently projected to reach St. Lucie Plant.

"The NRC Resident Inspector has been informed."

Notified R2IRC (Franke).

* * * UPDATE ON 9/11/17 AT 1405 EDT FROM BRIAN KELLY TO BETHANY CECERE * * *

"The Hurricane Warning has been terminated by the National Weather Service for St. Lucie County including the Plant Site. At time 1313 [EDT] on 9/11/17, St. Lucie Nuclear Power Plant has terminated from the Unusual Event Classification."

Unit 1 is currently shutdown in Mode 3, Hot Standby. Unit 2 continues to operate in Mode 1, 100 percent power.

The licensee notified State and Local Government Agencies, and the NRC Resident Inspector.

Notified R2IRC (Munday), R2DO (Michel), NRR EO (King), IRD MOC (Gott), DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, DHS NICC, USDA Ops Center, EPA Emergency Ops Center, FDA Emergency Ops Center (email), FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

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Power Reactor Event Number: 52961
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: DAN DULLUM
HQ OPS Officer: BETHANY CECERE
Notification Date: 09/11/2017
Notification Time: 15:00 [ET]
Event Date: 07/14/2017
Event Time: 14:53 [EDT]
Last Update Date: 09/11/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
GLENN DENTEL (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

"This report is being made as required by 10 CFR 50.73(a)(2)(iv)(A) to describe an automatic actuation of containment isolation valves in more than one system. Because the actuation was invalid, this 60-day telephone notification is being made instead of a written LER [Licensee Event Report], in accordance with 10 CFR 50.73(a)(1).

"On 07/14/17, at approximately 1453 hours [EDT], an electrical transient occurred due to an off-site lightning strike that de-energized one of the station's two qualified off-site power sources. This resulted in an automatic fast transfer of four 4 kV electrical buses to the alternate off-site source. The fast transfer occurred as designed without complications. The loss of power had numerous impacts on plant equipment that occurred in accordance with plant design, including a Group 2 primary containment isolation on both units. The Group 2 isolation affected multiple systems, including Reactor Water Cleanup, Instrument Nitrogen, and the Drywell Floor Drain.

"The fault on the off-site transmission line immediately cleared after the lightning strike and at 1457 hours [EDT] the transmission system operator gave the station permission to reclose the breaker to the off-site source. Following system restorations and equipment walkdowns, plant operators re-established normal connections to the off-site source on 7/14/17 at 2322 hours [EDT] in accordance with station procedures.

"The containment isolation occurred as a result of the loss of an off-site power source and was not due to actual plant conditions or parameters meeting design criteria for containment isolation. Therefore, this is considered to be an invalid actuation.

"The NRC Resident Inspector has been informed of this notification."

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Power Reactor Event Number: 52962
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: BRUCE BENNETT
HQ OPS Officer: BETHANY CECERE
Notification Date: 09/11/2017
Notification Time: 21:48 [ET]
Event Date: 09/11/2017
Event Time: 16:48 [EDT]
Last Update Date: 09/11/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ERIC MICHEL (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

Event Text

EMERGENCY DIESEL GENERATOR ACTUATION ON LOW VOLTAGE

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the Emergency Diesel Generator.

"On September 11, 2017 at 1648 [EDT] the 'A' Emergency Diesel Generator (EDG) started on the low voltage signal from Bus 1DA as a result of a 115KV grid perturbation. All emergency buses remained energized from offsite power. The EDG did not tie to the 1DA bus because the offsite power voltage recovered within the designed recovery time limit. The diesel generator has been secured, reset and is ready to auto start.

"The NRC Senior Resident Inspector has been notified."

Page Last Reviewed/Updated Tuesday, September 12, 2017
Tuesday, September 12, 2017