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Event Notification Report for October 09, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/5/2018 - 10/9/2018

** EVENT NUMBERS **


53629 53631 53632 53633 53634 53635 53646 53647 53648 53650 53652 53653

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Agreement State Event Number: 53629
Rep Org: SC DEPT OF HEALTH & ENV CONTROL
Licensee: BLUFFTON VETERINARY HOSPITAL
Region: 1
City: BLUFFTON   State: SC
County:
License #: 921
Agreement: Y
Docket:
NRC Notified By: ADAM GAUSE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/28/2018
Notification Time: 10:21 [ET]
Event Date: 09/24/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/28/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
FRANK ARNER (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION EVENT

The following information was received via E-mail:

"On 09/24/2018 the licensee discovered unusual dose rate survey readings on the floor in the treatment area. The licensee notified the Department [South Carolina Department of Health and Environmental Control] on 09/27/2018 via telephone that a potential contamination event had occurred.

"The licensee is authorized to administer liquid Iodine 131 for the treatment of hyperthyroidism in cats. The last administration occurred on 09/04/2018, with approximately 5 mCi of I-131 administered via syringe to a cat.

"A BRH [Bureau Radiological Health] Inspector was dispatched to the facility on 09/27/2018 and confirmed contamination of an area of floor in the treatment area. Access to the contaminated area has been restricted and boundaries have been put in place to ensure the dose rate does not exceed .002 rem in any one hour. The Department is conducting an investigation into the incident."

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Agreement State Event Number: 53631
Rep Org: COLORADO DEPT OF HEALTH
Licensee: MARIOTT DENVER TECH CENTER
Region: 4
City: DENVER   State: CO
County:
License #: GL000359
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/01/2018
Notification Time: 10:23 [ET]
Event Date: 12/19/2017
Event Time: 00:00 [MDT]
Last Update Date: 10/01/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following report was received from the Colorado Department of Public Health and Environment via email:

"Marriott Denver Tech Center reported three lost tritium exit signs when conducting the annual reconciliation."

Event Report ID No.: CO180020

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: 53632
Rep Org: COLORADO DEPT OF HEALTH
Licensee: OLINGER HAMPDEN FUNERAL HOME AND CEMETARY
Region: 4
City: DENVER   State: CO
County:
License #: GL001929
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/01/2018
Notification Time: 10:27 [ET]
Event Date: 12/29/2017
Event Time: 00:00 [MDT]
Last Update Date: 10/01/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following report was received from the Colorado Department of Public Health and Environment via email:

"Olinger Hampden Funeral Home & Cemetery reported three lost tritium exit signs when conducting the annual reconciliation."

CO Event Report ID No.: CO180021

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: 53633
Rep Org: COLORADO DEPT OF HEALTH
Licensee: CANYON BAKEHOUSE
Region: 4
City: JOHNSTOWN   State: CO
County:
License #: GL002453
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/01/2018
Notification Time: 10:30 [ET]
Event Date: 12/22/2017
Event Time: 00:00 [MDT]
Last Update Date: 10/01/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following report was received from the Colorado Department of Public Health and Environment via email:

"Canyon Bakehouse reported that three tritium exit signs were not in the building when the ownership of the building was transferred."

CO Event Report ID No.: CO180023

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: 53634
Rep Org: COLORADO DEPT OF HEALTH
Licensee: KEYSTONE REPORT-PROPERTY MANAGEMENT
Region: 4
City: KEYSTONE   State: CO
County:
License #: GL000311
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/01/2018
Notification Time: 10:33 [ET]
Event Date: 06/28/2018
Event Time: 00:00 [MDT]
Last Update Date: 10/01/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following report was received from the Colorado Department of Pubic Heath and Environment via email:

"Keystone Resort-Property Management reported one tritium exit sign was unable to be located during the annual reconciliation."

CO Event Report ID No.: CO180025

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: 53635
Rep Org: COLORADO DEPT OF HEALTH
Licensee: UNITED PARCEL SERVICE
Region: 4
City: COMMERCE CITY   State: CO
County:
License #: GL000169
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/01/2018
Notification Time: 10:33 [ET]
Event Date: 07/27/2018
Event Time: 00:00 [MDT]
Last Update Date: 10/01/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following report was received from the Colorado Department of Public Health and Environment via email:

"United Parcel Service reported one tritium exit sign was lost when the building was renovated."

CO Event Report ID No.: CO180024

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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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53646
Facility: COOPER
Region: 4     State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: TERRELL HIGGINS
HQ OPS Officer: VINCE KLCO
Notification Date: 10/05/2018
Notification Time: 09:52 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/24/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
THOMAS FARNHOLTZ (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

MAIN STEAM ISOLATION VALVES EXCEEDED PRIMARY CONTAINMENT LOCAL LEAK RATE ACCEPTANCE CRITERIA

"At 0520 (CDT), on October 05, 2018, it was discovered that a Primary Containment local leak rate test performed on Main Steam Isolation Valves (MSIV) exceeded its acceptance criteria.

"During Mode 1, 2, and 3, Surveillance Requirement 3.6.1.3.10 requires MSIV leakage for a single MSIV line to be less than or equal to 106 standard cubic feet per hour (scfh) when tested at 29 psig and Surveillance Requirement 3.6.1.3.12 requires the combined leakage rate for all MSIV leakage paths to be less than or equal to 212 scfh when tested at 29 psig.

"As-found for the 'C' MSIV line leakage results were unquantifiable and gave a [minimum] path value greeter than 160 scfh. This leakage rate lead to Surveillance Requirement 3.6.1.3.10 and 3.6.1.3.12 limits to be exceeded. This event is being reported as a condition of the nuclear power plant, including its principal safety barriers, being seriously degraded per 10 CFR 50.72(b)(3)(ii)(A) since the Primary Containment Isolation Valves leakage limits for MSIVs were exceeded.

"The NRC Resident Inspector has been notified."

* * * RETRACTION AT 2320 EDT ON 10/24/2018 FROM THOMAS FORLAND TO MARK ABRAMOVITZ * * *

"CNS [Cooper Nuclear Station] is retracting the 8-hour non-emergency notification made on October 5, 2018 at 0520 CDT (EN# 53646). Subsequent evaluation concluded that overall as-found 'C' MSIV leakage rate was not at a level that exceeded the surveillance requirement 3.6.1.3.10 and 3.6.1.3.12 limits and thus the Primary Containment Isolation Valve leakage rate limits for the MSIVs were not exceeded.

"The NRC Senior Resident Inspector has been notified."

Notified the R4DO (Drake).

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53647
Facility: WOLF CREEK
Region: 4     State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARCY BLOW
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/05/2018
Notification Time: 09:59 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/18/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
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

UNPLANNED LOSS OF THE ASSESSMENT CAPABILITY DUE TO TECHNICAL SUPPORT DIESEL

"At 05:52 CDT on 10/5/2018, the [Wolf Creek Nuclear Operating Corporation] (WCNOC) Technical Support Center (TSC) Diesel fuel oil transfer pump would not run. There was ongoing modification to the facility Halon system at the time. The modification process had included a jumper to the fuel oil transfer pump to allow it to continue to be available. This issue was discovered during testing as the modification was progressing. The pump was verified to function on 10/4/2018 by normal operations rounds.

"If an emergency is declared requiring the TSC activation during the time the TSC diesel is non-functional, the TSC will be staffed and activated using existing emergency planning procedure. If offsite power is lost, the TSC will relocate to the Alternate TSC using existing emergency planning procedures.

"There was no impact to the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

* * * RETRACTION ON 10/18/2018 AT 1306 EDT FROM MARCY BLOW TO ANDREW WAUGH * * *

"Event Notification (EN) 53647, made on October 8, 2018, is being retracted because during the time that the TSC Diesel fuel oil transfer pump was not available, normal power was continuously available. The Alternative TSC was also available.

"Consequently, the condition did not meet the criteria for a 8-hour notification per 10 CFR 50.72(b)(3)(xiii) for any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).

"The NRC Resident Inspector has been notified of the Event Notification retraction."

Notified R4DO (Pick).

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Power Reactor Event Number: 53648
Facility: PILGRIM
Region: 1     State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KENNETH KNELL
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/05/2018
Notification Time: 15:39 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/05/2018
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):
JON LILLIENDAHL (R1DO)
WILLIAM GOTT (IRD)
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 LOW REACTOR WATER LEVEL

"On Friday, October 5, 2018 at 1209 hours, with the reactor at 100 percent core thermal power, Pilgrim Nuclear Power Station (PNPS) automatically tripped due to reactor water level perturbation and receipt of a low reactor water level Reactor Protection System (RPS) signal. The cause of the low reactor water level is under investigation. The plant is in hot shutdown.

"All other plant systems responded as designed. Pressure is being controlled using the Mechanical Hydraulic Control System and Main Condenser. Reactor water level is being maintained with the feedwater and condensate system.

"During the automatic reactor scram the plant experienced the following isolation signals as designed:
Group 2 Isolation: Miscellaneous containment isolation valves
Group 6 Isolation: Reactor Water Clean-up
Reactor Building Isolation System Actuation

"Due to the RPS actuation while critical, this event is being reported as a four-hour, non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B), 'any event that results in actuation of the reactor protection system (RPS) when the reactor is critical.' This notification is also being made in accordance with 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section ... ' (B)(2) 'General containment isolation signals affecting containment isolation valves in more than one system.'

"This event has no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."

The licensee will notify the Massachusetts Emergency Management Agency.

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53650
Facility: COOPER
Region: 4     State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: NATE BEGER
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/06/2018
Notification Time: 05:56 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [CDT]
Last Update Date: 11/15/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
THOMAS FARNHOLTZ (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

CONTROL ROOM EMERGENCY FILTER SYSTEM INOPERABLE

"On 10/5/2018, at 2219 CDT, the Control Room Emergency Filter (CREF) System was determined to be inoperable during a required condition of applicability due to being aligned to a Division 2 power source with its associated emergency power supply (Diesel Generator #2) removed from service earlier in the day. The power supply alignment was not identified at the time Diesel Generator #2 was removed from service (Diesel Generator #2 was rendered inoperable on 10/5/2018 at 1728 CDT). Movement of lately irradiated fuel assemblies in the Secondary Containment was in progress at the time of discovery of this condition. This condition represents an unplanned loss of safety function for a single train system during its specified condition of applicability. Movement of irradiated fuel was suspended until the power supplies to CREFs could be realigned to Division 1 which was completed at 0004 CDT on 10/6/2018.

"This represents a condition that could have prevented the fulfillment of the safety function of CREFs needed to mitigate the consequences of a fuel handling accident."

The NRC Resident Inspector has been notified.

* * * RETRACTION AT 1533 EST ON 11/15/18 FROM THOMAS FORLAND TO JEFFREY WHITED * * *

"CNS [Cooper Nuclear Station] is retracting the 8-hour non-emergency notification made on October 5, 2018 at 2219 CDT (EN# 53650). A subsequent evaluation concluded that the Control Room Emergency Filter (CREF) system remained operable in accordance with the applicable Cooper Nuclear Station Technical Specification Requirements 3.7.4 CREF System, 3.8.2 AC Sources - Shutdown, and 3.8.8 Distribution Systems - Shutdown. As a result of CREFs remaining operable throughout this period, no loss of safety function occurred. The NRC Senior Resident Inspector has been notified."

Notified R4DO (Haire)

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Power Reactor Event Number: 53652
Facility: BRAIDWOOD
Region: 3     State: IL
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC PHILLIPS
HQ OPS Officer: STEVEN VITTO
Notification Date: 10/08/2018
Notification Time: 04:13 [ET]
Event Date: 10/08/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/08/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
STEVE ORTH (R3DO)
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

REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE

"On Monday, October 8, 2018 at 0111 CDT, during the initial containment entry for unit 2 refueling outage (A2R20), reactor coolant system pressure boundary leakage was discovered at the 2D Steam Generator bowl drain line. Unit cooldown to mode 5 is in progress.

"This event is reportable under 10CFR50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'

"The licensee has notified the NRC resident inspector."

Approximately 0.1 gpm was leaking from the drain line. LCO 3.4.13 was entered and the licensee anticipates being in mode 5 within a couple of hours. The leak will be repaired prior to exiting the refueling outage.

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Part 21 Event Number: 53653
Rep Org: CURTISS WRIGHT
Licensee: CURTISS WRIGHT
Region: 3
City: CINCINNATI   State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TIM FRANCHUK
HQ OPS Officer: OSSY FONT
Notification Date: 10/08/2018
Notification Time: 14:54 [ET]
Event Date: 08/07/2018
Event Time: 00:00 [EDT]
Last Update Date: 03/08/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
STEVE ORTH (R3DO)
- PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 NOTIFICATION - NAMCO LIMIT SWITCH FAILED TEST DUE TO INSUFFICIENT LUBRICATION

The following information was received via email from Curtiss Wright:

"Curtiss-Wright was notified on August 7, 2018 by Exelon's Dresden Plant that a Curtiss-Wright Supplied Namco Limit Switch, P/N: EA700-90964 had failed during a planned maintenance test.

"The switch contacts were found to be sluggish in returning to the normal shelf state after actuation, or would not return at all. The switch was identified as Curtiss-Wright Tag Number 5T34603 and was provided as a safety related component to Exelon in September 2005. According to Exelon, the item was stored for 8 years, then failure occurred approximately 5 years into service. The part has a manufacturer date coded as August 2005.

"The switch was subsequently sent to Exelon Powerlabs where a detailed failure evaluation was performed. Exelon Powerlabs confirmed the failure mode and determined that there was insufficient lubrication in place to support normal switch function. The switch was then sent to Namco for further evaluation and Namco confirmed the lack of lubricant was the likely cause of the failure.

"Curtiss-Wright is currently investigating this issue and will provide a follow up report by November 15, 2018."


* * * UPDATE FROM TIM FRANCHUK TO DONALD NORWOOD AT 1335 EST ON 11/16/2018 * * *

The following information was received via E-mail:

"In reference to the Curtiss-Wright Interim Notification Report dated 10/8/2018 for an EA700-90964 limit switch failure, the following clarifications and updates are provided.

"The subject switch was originally supplied by Curtiss-Wright to Exelon's Dresden plant. Subsequently Dresden transferred the switch to Quad Cities where it was installed and found degraded and inoperable during a planned maintenance test. The initial notification of failure to Curtiss-Wright was by Quad Cities personnel, and not Dresden personnel. The switch was previously identified as Curtiss-Wright Tag Number 5T34603, which was incorrect. The actual Tag Number of the failed unit is 5T36403.

"The failure is still under investigation and Curtiss-Wright has been in communication with the manufacturer, Quad Cities personnel and Exelon Powerlabs personnel concerning the failure and application. A key factor in the failure appears to be heat related, specifically the switches operating temperature. As such, additional operating temperature data is being taken by Exelon personnel which will conclude in late February or early March 2019. Once this data is made available, a final conclusion as to the root cause of the failure can be determined.

"We therefore request additional time to complete our evaluation and should have our final report issued by March 8th, 2019."

Notified R3DO (Peterson) and Part 21/50.55 Reactors E-mail group.

* * * UPDATE ON 3/8/2019 AT 1320 EST FROM MARGIE HOOVER TO ANDREW WAUGH * * *

The following information was received via email:

"In reference to the Curtiss-Wright Interim Notification Report dated 10/8/2018 for an EA700-90964 limit switch failure, the following updates are provided.

"Curtiss-Wright's investigation is ongoing, with the current focus being the evaluation of in-service switch operating temperatures and results from a recent disassembly/inspection of similar switches (same model but different date codes). Additional inspection of other switches currently in-service at the plant is needed to finish the investigation. Evaluation of these switches is expected to be completed by mid-May. Once this data is made available, a final conclusion as to the root cause of the failure can be determined.

"We therefore request additional time to complete our evaluation and should have our final report issued by May 31, 2019."

Notified R3DO (Hills) and Part 21/50.55 Reactors group (email).


Page Last Reviewed/Updated Friday, May 03, 2019
Friday, May 03, 2019