Home NRC Library Document Collections Events, Reports Associated with Event Notification Reports 2019

Event Notification Report for March 11, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
3/8/2019 - 3/11/2019

** EVENT NUMBERS **

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

EN Revision Imported Date : 3/11/2019

EN Revision 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).

Agreement State	Event Number: 53899
Rep Org: NC DIV OF RADIATION PROTECTION Licensee: GENERAL ELECTRIC COMPANY Region: 1 City: MEBANE State: NC County: License #: 0318-0G Agreement: Y Docket: NRC Notified By: TRAVIS CARTOSKI HQ OPS Officer: JOANNA BRIDGE	Notification Date: 02/28/2019 Notification Time: 11:11 [ET] Event Date: 02/22/2019 Event Time: 00:00 [EST] Last Update Date: 02/28/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): DAVE WERKHEISER (R1DO) ILTAB (EMAIL) NMSS_EVENTS_NOTIFICATION (EMAIL)

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

Event Text

AGREEMENT STATE REPORT - LOSS OF LICENSED MATERIAL

The following was received via email from the state of North Carolina:

"North Carolina Radiation Protection Branch (RMB) was notified on February 22, 2019, that a General Licensee could not account for two Microderm hand-held probes containing two sources each [25 micro Ci of Sr-90 and 100 micro Ci of Tl-204]. RMB has been in communications with the General Licensee to ascertain whether or not the devices containing the sources have been returned to the vendor or are indeed lost. At this time, this cannot be verified and the RMB anticipates more information to follow on March 4, 2019. Additional details to follow to complete this event report."

NC Event Tracking ID: 190007

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

Agreement State	Event Number: 53900
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES Licensee: SCHLUMBERGER TECHNOLOGY CORP Region: 4 City: SUGAR LAND State: TX County: License #: L01833 Agreement: Y Docket: NRC Notified By: KAREN BLANCHARD HQ OPS Officer: OSSY FONT	Notification Date: 02/28/2019 Notification Time: 11:34 [ET] Event Date: 02/14/2019 Event Time: 00:00 [CST] Last Update Date: 02/28/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): RICK DEESE (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION FROM OIL FIELD EQUIPMENT

The following was received via email from the state of Texas:

"On February 27, 2019, the Agency [Texas Department of State Health Services] confirmed that access to an oil field equipment wash building had been restricted since February 14, 2019, due to radioactive material contamination.

"On February 11, 2019, a load of waste from the licensee's facility had set off the radiation alarm at the landfill. The isotope was identified as antimony-124. The load was returned to the licensee's facility later that afternoon. On February 12, 2019, the licensee began surveying and investigating, starting with the dumpster and expanding to other areas. The contamination was found to be on piece/part of a fracking pump. On February 13, 2019, contamination was identified on a fracking pump trailer. On February 14, 2019, surveys identified contamination in the trench of one of the bays in the equipment wash building.

"Access to the building was restricted that day and is still restricted. The licensee's initial sampling from the trench identified antimony-124 and scandium-46. They are waiting on analyses of a second sampling of the trench sludge after water was removed/collected, and they will be sampling the traps/separators between the trench and the sanitary sewer system.

"The licensee is not licensed for, nor did it use, these tracer materials. Their equipment was being used on a well site at which another licensee had performed a tracer study while the equipment was in use. The tracer study licensee has been involved in some of the surveying and with the collection of contaminated equipment items they took possession of to be held or disposed in accordance with their license.

"An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident #: I-9656

Agreement State	Event Number: 53901
Rep Org: COLORADO DEPT OF HEALTH Licensee: ST. ANTHONY HOSPITAL - CENTURA HEALTH Region: 4 City: LAKEWOOD State: CO County: License #: CO152-01 Agreement: Y Docket: NRC Notified By: RAMON LI HQ OPS Officer: OSSY FONT	Notification Date: 02/28/2019 Notification Time: 17:15 [ET] Event Date: 02/28/2019 Event Time: 13:00 [MST] Last Update Date: 02/28/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): RICK DEESE (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION

The following was received via email from the state of Colorado:

"At approximately 1438 MST on February 28, 2019 the RSO [Radiation Safety Officer] for CO 152-01, St. Anthony Hospital - Centura Health, notified the Department [Colorado Department of Public Health and Environment] of a Y-90 SIR-Sphere misadministration. The procedure occurred at approximately 1300 MST and it was determined that 65 percent of the prescribed dose was delivered to the patient. The RSO noted that during the procedure there were issues with the delivering catheter. During the procedure, the catheter was replaced.

"A department investigation will occur in the near future. A written report per section 7.21.4 is expected within 15 days."

Colorado Event Report ID No.: CO190003

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

Agreement State	Event Number: 53902
Rep Org: CALIFORNIA RADIATION CONTROL PRGM Licensee: KAISER PERMANENTE Region: 4 City: LOS ANGELES State: CA County: License #: 0372 Agreement: Y Docket: NRC Notified By: ROBERT GREGER HQ OPS Officer: JEFF HERRERA	Notification Date: 02/28/2019 Notification Time: 20:51 [ET] Event Date: 02/25/2019 Event Time: 00:00 [PST] Last Update Date: 02/28/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): RICK DEESE (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - UNINTENDED DOSE TO NON-TARGET TISSUE

The following was received from the state of California:

"The licensee reported an unintended dose to non-target tissue of a patient from an HDR [High Dose Rate] treatment, apparently due to mispositioning of the uterus-ovary applicator. The unintended dose occurred on the final of four fractions. The target tissue received the intended dose in each of the four fractions, but non-target tissue of the bowel received in excess of 50 rem and 150 percent of the expected dose to the non-target bowel tissue from the four fractions combined, with the excess non-target bowel dose occurring in the final fraction due to the mispositioned applicator.

"The licensee will submit a 15-day written report to the California Department of Public Health-Radiologic Health Branch (CDPH-RHB) in accordance with 10 CFR 35.3045(d), and will include the calculated dose to the non-target tissue of concern. That report will be forwarded to NRC by CDPH-RHB.

"The referring physician was informed of the unintended dose to the non-target bowel tissue."

CA 5010 Number: 022719

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

Agreement State	Event Number: 53904
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL Licensee: UNIVERSITY OF KENTUCKY (HOSPITAL) Region: 1 City: LEXINGTON State: KY County: License #: 202-049-22 Agreement: Y Docket: NRC Notified By: ANGELA WILBERS HQ OPS Officer: CATY NOLAN	Notification Date: 03/01/2019 Notification Time: 13:53 [ET] Event Date: 02/28/2019 Event Time: 00:00 [CST] Last Update Date: 03/01/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): DAVE WERKHEISER (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - UNDERDOSE OF THERASPHERE Y-90 TREATMENT

The following report was received from the Kentucky Department of Public Health via email:

"The University of Kentucky RSO [Radiation Safety Officer] reports a patent delivery system failed to deliver part of a TheraSphere Y-90 treatment on February 28, 2019. A patient written directive indicated a prescribed dose of 208 Gy. The patient only received 145 Gy.

"The RSO indicated the first vial of Y-90 was administered without difficulty. The second vial failed to empty into the administration catheter. Calls were placed to the drug representative and unsuccessful attempts made to administer the remainder of the dose. Patient treatment was stopped with only partial dose delivery. At the time of the report, March 1, 2019, the University is establishing the reason for the administration failure. The patient had been notified and the physician and referring physician are being notified. The university plans an update in 15 days."

Kentucky Event Report ID No.: Ky190002.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

Agreement State	Event Number: 53905
Rep Org: PA BUREAU OF RADIATION PROTECTION Licensee: HOLCIM (US), INC. Region: 1 City: WHITEHALL State: PA County: License #: PA-1336 Agreement: Y Docket: NRC Notified By: JOHN S. CHIPPO HQ OPS Officer: OSSY FONT	Notification Date: 03/01/2019 Notification Time: 13:56 [ET] Event Date: 02/28/2019 Event Time: 00:00 [EST] Last Update Date: 03/01/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): DAVE WERKHEISER (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL)

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

Event Text

AGREEMENT STATE REPORT - MISSING ANALYZER SOURCE

The following was received via fax from the Pennsylvania Department of Environmental Protection:

"On March 1, 2019, a manufacturer's technician from Sabia Inc. (PA-R0124) notified the Department [Pennsylvania Department of Environmental Protection] of a missing 0.9 microgram (0.5 mCi) Californium-252 source from a Sabia XL5000 analyzer at the Holcim (US), Inc. Whitehall Cement Plant (PA-1336). The manufacturer was performing replenishment of two of seven sources [on February 28, 2019]. It was discovered that the analyzer only contained six sources. The analyzer was removed and disassembled, destroying the unit, in efforts to locate the missing source but it was not located. The manufacturer technician surveyed the unit and the area multiple times and did not find the source. The remaining sources have been packaged in a drum for safe storage until shipping can be arranged.

"The Department will perform a reactive inspection. More information will be provided upon receipt."

Pennsylvania Event Report ID No: PA190006

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

Agreement State	Event Number: 53907
Rep Org: NC DIV OF RADIATION PROTECTION Licensee: JANX Region: 1 City: GRAYSBURG State: NC County: License #: 1117-2 Agreement: Y Docket: NRC Notified By: TRAVIS CARTOSKI HQ OPS Officer: JEFF HERRERA	Notification Date: 03/02/2019 Notification Time: 21:02 [ET] Event Date: 03/02/2019 Event Time: 00:00 [EST] Last Update Date: 03/02/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): DAVE WERKHEISER (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL)

This material event contains a "Category 2" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY DEVICE LEFT UNSECURED

The following report was received from the North Carolina Division of Health Service Regulation, Radioactive Materials Branch via email:

"Licensee reports that an Industrial Radiography [IR] exposure device was unaccounted for during the 15 hours following work site activities on March 1st. The IR device was left unsecured the entire time until discovered the morning of March 2nd by the radiography crew that left it. The device [Spec 150; S/N: 1251] and source [72 Ci Ir-192; Model: G-60; S/N: AA0805] are secured and in possession of the corporate RSO [Radiation Safety Officer] at the time of this report. North Carolina Radioactive Materials Branch has initiated an investigation and will update this report for completion."

NC Event Tracking ID: 190008

THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL

Category 2 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 a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

Power Reactor	Event Number: 53918
Facility: BROWNS FERRY Region: 2 State: AL Unit: [1] [2] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: STUART WETZEL HQ OPS Officer: ANDREW WAUGH	Notification Date: 03/08/2019 Notification Time: 15:51 [ET] Event Date: 03/08/2019 Event Time: 11:13 [CST] Last Update Date: 03/08/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION	Person (Organization): BINOY DESAI (R2DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Refueling

100

Power Operation

100

Power Operation

Event Text

OFFSITE NOTIFICATION FOR OIL SPILL INTO U.S. WATERS

"Browns Ferry Nuclear Plant (BFN) is notifying state and local agencies of the presence of an oil sheen in the cold water channel. Water from the cold water channel was running into a tunnel that connects to the waters of the US.

"BFN Procedure RWI-007, Spill Prevention Control and Countermeasure Plan requires the National Response Center as well as other state and local agencies be notified of any oil sheen on the water. This oil spill is reportable to the EPA (National Response Center) under 40 CFR 112. The notification was made to the National Response Center at 1113 CST under notification number 1239580. The Alabama Emergency Management Agency (AEMA) and Alabama Department of Environmental Management (ADEM) were notified at 1120 CST.

"This event is reportable as a 4-hour Non-Emergency Notification report in accordance with 10 CFR 50.72(b)(2)(xi) 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.'"

The licensee has notified the NRC Resident Inspector.

The oil is believed to come from the number one cooling tower basin due to heavy rainfall.

Power Reactor	Event Number: 53921
Facility: CALVERT CLIFFS Region: 1 State: MD Unit: [1] [2] [] RX Type: [1] CE,[2] CE NRC Notified By: BRIAN HAYDEN HQ OPS Officer: JEFF HERRERA	Notification Date: 03/09/2019 Notification Time: 13:59 [ET] Event Date: 03/09/2019 Event Time: 12:00 [EST] Last Update Date: 03/09/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION	Person (Organization): ART BURRITT (R1DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Refueling

Event Text

SEWAGE LINE BACKUP CAUSING WASTEWATER DISCHARGE TO CHESAPEAKE BAY

"A sewage line on the south end of the plant backed up causing sanitary wastewater to flow into storm drains and out to the Chesapeake Bay. This is a required notification of the Maryland Department of the Environment under COMAR [Code of Maryland Regulations] 26.08 for discharge of a pollutant into navigable waters or the adjoining shoreline. The amount has been estimated at less than 1000 gallons and the source has been isolated and storm drains have been covered to stop any flow into them and subsequently to the Chesapeake Bay. This notification is made in accordance with 10CFR50.72(b)(2)(xi) due to notification of a state agency."

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 53922
Facility: BROWNS FERRY Region: 2 State: AL Unit: [] [] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: DAVID HALL HQ OPS Officer: OSSY FONT	Notification Date: 03/10/2019 Notification Time: 00:48 [ET] Event Date: 03/09/2019 Event Time: 23:12 [CST] Last Update Date: 03/10/2019
Emergency Class: UNUSUAL EVENT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED	Person (Organization): BINOY DESAI (R2DO) JEFFERY GRANT (IRD) CATHY HANEY (R2RA) HO NIEH (DNRR) CHRIS MILLER (NRR EO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

A/R

100

Power Operation

Hot Shutdown

Event Text

NOTICE OF UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER

At 0012 EST on 3/10/2019, Browns Ferry Unit-3 declared an Unusual Event due to a spurious trip of the generator breaker, resulting in a loss of AC power to the 4 kV shutdown boards greater than 15 minutes. All diesel generators started and loaded to supply onsite power. The reactor auto-scrammed, with all rods fully inserting. The Main Steam Isolation Valves opened and shutdown cooling was being conducted via the condenser. The licensee will exit the emergency declaration once offsite power is restored. There is no estimated restart date.

Browns Ferry Unit 1 remains in Mode-1 (100%), Unit 2 remains in Mode-5 for a refueling outage.

The NRC Resident Inspector has been notified.

This event is related to EN 53923.

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

* * * UPDATE ON 3/10/19 AT 1419 EDT FROM JOHN HOLLIDAY TO BETHANY CECERE * * *

At 1310 CDT, Browns Ferry Unit-3 exited the Unusual Event when 161 kV lines were made available. The licensee is executing procedures for securing the diesel generators while alternate offsite power methods are utilized. Switchyard damage evaluation is in progress.

The licensee will notify the NRC Resident Inspector.

Notified R2DO (Desai), R2RA (Haney), DNRR (Nieh), NRR EO (Miller), and IRD (Grant).

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

Power Reactor	Event Number: 53923
Facility: BROWNS FERRY Region: 2 State: AL Unit: [] [] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: DAVID HALL HQ OPS Officer: JEFFREY WHITED	Notification Date: 03/10/2019 Notification Time: 04:38 [ET] Event Date: 03/09/2019 Event Time: 22:59 [CST] Last Update Date: 03/10/2019
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): BINOY DESAI (R2DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

A/R

100

Power Operation

Hot Shutdown

Event Text

AUTOMATIC SCRAM RESULTING IN RPS AND ECCS ACTUATION

"At 2259 CST on 3/9/2019, Browns Ferry Unit-3 received an automatic SCRAM on Main Generator Breaker Failure and Turbine Load Reject. Unit-3 declared a Notification of Unusual Event SU1 for loss of offsite AC power to Unit-3 specific 4kV Shutdown Boards for greater than 15 minutes.

"Primary Containment Isolation Systems (PCIS) Groups 1, 2, 3, 6, and 8 isolation signals were received. Upon receipt of these signals, all required components actuated as required. Main steam relief valves lifted on the initial transient. High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) initiated on low reactor water level. HPCI remains in service for reactor level and pressure control. RCIC is not in service at this time, the station is investigating low flow from the pump. All four Unit-3 Diesel Generators started and loaded as expected. Residual Heat Removal System is in service for suppression pool cooling.

"4kV Station Unit Boards have been restored from the 161kV system. Actions are in progress to restore 4kV Shutdown Boards to offsite power.

"This event is reportable within 1 hour in accordance with 10 CFR 50.72(a)(1)(i) for declaration of the Licensees Emergency Plan. Complete as documented on EN 53922.

"This event requires a 4 hour report per 10 CFR 50.72(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.'

"This event also requires an 8 hour report per 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), (1) Reactor protection system (RPS) including: reactor scram or reactor trip, (2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs), (4) ECCS [Emergency Core Cooling System] for boiling water reactors (BWRs) including: core spray systems; high-pressure coolant injection system; low pressure injection function of the residual heat removal system, (5) BWR reactor core isolation cooling system; isolation condenser system; and feedwater coolant injection system, and (8) Emergency AC electrical power systems, including: Emergency diesel generators (EDGs).'

"The NRC resident inspector has been notified."

As of the event report, the MSIVs were opened and decay heat was being removed via the bypass valves to the condenser.

Page Last Reviewed/Updated Wednesday, March 24, 2021