Event Notification Report for October 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/18/1999 - 10/19/1999
** EVENT NUMBERS **
36218 36285 36299 36305 36306 36307 36308
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36218 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 09/23/1999|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 17:08[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 08/06/1999|
+------------------------------------------------+EVENT TIME: 10:00[EDT]|
| NRC NOTIFIED BY: MICHAEL ZACCONE |LAST UPDATE DATE: 10/18/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: |VERN HODGE (FAX) NRR |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT - ABB K-LINE BREAKER DEFECT |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "This report is being made pursuant to 10 CFR 21.21 [in order] to identify a |
| substantial safety hazard with an ABB K-line breaker." |
| |
| "On August 6, 1999, Virgil C. Summer Nuclear Station (VCSNS) determined that |
| a substantial safety hazard could exist with ABB K-line breakers failing to |
| trip. Improper routing/support of the shunt trip wires during refurbishment |
| caused interference with the red trip-shaft paddle on the left side of the |
| breaker. This condition was found on a breaker installed in [a] |
| safety-related switchgear at VCSNS. This breaker condition was compared to |
| several other ABB K-line breakers at the plant site. The other breakers |
| were found to have the wires routed in a different direction, precluding |
| interference with the red trip-shaft paddle." |
| |
| "VCSNS utilizes these breakers in many applications, including the 480-VAC, |
| safety-related, electrical buses. The shunt trip wiring problem is |
| considered a defect in repair. This condition represents a potential for a |
| common mode failure for safety-related K-line breakers." |
| |
| "The vendor has been notified of the shunt trip wiring problem and has |
| agreed to modify the procedure for the refurbishment of these breakers. |
| VCSNS Engineering has determined that vendor procedure changes |
| should prevent recurrence of this problem." |
| |
| The licensee notified the NRC resident inspector. |
| |
| ********************* UPDATE AT 0934 ON 10/18/99 FROM PHIL ROSE TO LEIGH |
| TROCINE ******************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On [10/07/99], ABB Service and VCSNS personnel inspected the affected |
| breaker along with a second K-line breaker that was determined to also be |
| potentially affected at VCSNS. It was determined that the following |
| information should be provided to all licensees regarding this issue:" |
| |
| "The potentially affected breakers at ABB K-line breakers of the following |
| type: |
| * all electrically-operated breakers model K-1600, K-1600S, K-2000, |
| K-2000S, and K-225 through K-800[; and] |
| * any mechanically- or electrically-operated breakers with the above model |
| numbers which have any |
| auxiliary switches or a shunt trip." |
| |
| "The potential impact on the breakers has been assessed to be either of the |
| following: |
| * For breakers having the shunt trip coil wiring on top of the tripper |
| paddle, a trip free condition could result. |
| * For breakers which have the shunt trip coil wiring underneath the tripper |
| paddle, the overload trip could be |
| prevented from operating. The circuit breaker is capable of a manual or |
| electrical trip. This condition |
| impacts the overload trip function only." |
| |
| "It was also determined that this problem was not limited to the breaker |
| refurbishment/repair process by ABB Service. [The licensee stated that this |
| condition could occur on new breakers.]" |
| |
| "VCSNS has inspected 26 safety-related breakers. One breaker was found to |
| be affected and another potentially affected. Corrective actions have been |
| taken. VCSNS has also inspected three non-safety-related breakers with no |
| further problems identified. The remaining breakers (four safety related |
| and five non-safety related) have been added to the scope of the next |
| refueling outage." |
| |
| "[Both] VCSNS and ABB Service recommend inspection of all potentially |
| affected breakers as soon as they can be made available. The recommended |
| corrective action is to inspect and secure any wiring that could potentially |
| interfere with the proper operation of the tripper paddle." |
| |
| The licensee stated that a 30-day report regarding this issue is due to be |
| issued this week. The licensee notified the NRC resident inspector. The |
| NRC operations officer notified the R1DO (Cook), R2DO (Julian), R3DO |
| (Jorgensen), R4DO (Smith), and NRR (Hodge). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36285 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 10/13/1999|
| UNIT: [] [3] [] STATE: PA |NOTIFICATION TIME: 07:12[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 10/13/1999|
+------------------------------------------------+EVENT TIME: 03:26[EDT]|
| NRC NOTIFIED BY: CAMERON CAMPBELL |LAST UPDATE DATE: 10/18/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP GENERATED DURING TESTING, PLANT ALREADY SHUTDOWN |
| |
| During refueling outage activities a 'Full Scram' signal was initiated while |
| testing the main steam line high radiation instrumentation. No control rod |
| or 'Group I' isolation valve movement occurred as a result of this signal |
| since all affected equipment was in the tripped condition due to plant |
| conditions. The only valve movement was the scram discharge volume vent and |
| drain valves which closed per design. |
| |
| The 'Full Scram' and 'Group I' isolation signal resulted as a result of |
| testing inadequacies. The signal was reset and the valves were opened per |
| plant procedures. |
| |
| The NRC Resident Inspector was informed. |
| |
| * * * RETRACTION AT 1530 ON 10/18/1999 FROM WEILGOPOLSKI TAKEN BY STRANSKY * |
| * * |
| |
| "This event involved a 4-hour report made for the inadvertent ESF actuation |
| under 10 CFR 50.72(b)(2)(ii). The event occurred while Unit 3 was in a |
| refueling outage and involved a full scram signal being initiated during |
| testing of the main steam line high radiation instrumentation. The event had |
| no control rod movement or Group 1 isolation valve movement since all |
| affected equipment was in the tripped condition during to refueling |
| activities. The only valve movement that occurred was the scram discharge |
| volume (SDV) vent and drain valves which closed. |
| |
| "Although the SDV vent and drain valves closed and are primary containment |
| isolation valves, this event is being retracted based on the following: |
| * ESF actuation signal was invalid because it was caused by a procedural |
| error; and |
| * the SDV vent and drain valve primary containment function was properly |
| removed from service as a result of |
| [Point Beach Atomic Power Station (PBAPS)] Unit 3 being in a refueling |
| outage (Mode 5) and the primary |
| containment breached." |
| |
| The NRC resident inspector has been informed of this retraction. The NRC |
| operations officer notified the R1DO (Cook). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36299 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 10/16/1999|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 06:55[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 10/16/1999|
+------------------------------------------------+EVENT TIME: 03:05[MST]|
| NRC NOTIFIED BY: JIM BLAZICK |LAST UPDATE DATE: 10/18/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |GAIL GOOD R4 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |RICHE FEMA |
| |WILLIAM BRACH NMSS |
| |TED MICHAELS REXB |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO EARTHQUAKE FELT ON SITE. (Refer to event |
| #36298 for a related event at San Onofre.) |
| |
| An earthquake of magnitude 7.0 occurred at 0247 MST at coordinates 34 |
| degrees 35.73 minutes north, 116 degrees 16.09 minutes west. This location |
| is about 32 miles north of Joshua Tree, California, and 47 miles |
| east-southeast of Barstow, California. This information is from the U.S. |
| Geological Survey Southern California Seismic Network. |
| |
| The licensee felt the earthquake, and the strong motion accelerometer |
| alarmed. An approximate intensity level of 0.015g's has been determined. |
| Unit 1 is defueled, and Units 2 and 3 are in operation with no problems. |
| Inspections were carried out per procedures as well as the declaration of |
| the Unusual Event. Engineering walkdowns and evaluations are in progress |
| per procedure. |
| |
| The Unusual Event was entered and exited at 0305 MST. |
| |
| The licensee notified the NRC Resident Inspector as well and state/local |
| authorities. |
| |
| ***************** UPDATE AT 0100 EDT ON 10/18/99 FROM DANN DAILEY TO LEIGH |
| TROCINE ***************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "This is a followup of the ENS notification at 0353 MST on 10/16/99. If |
| through subsequent reviews of this event, additional information is |
| identified that is pertinent to this event or alters the information being |
| provided at this time, another followup notification will be made via the |
| ENS or under the reporting requirements of 10CFR50.73." |
| |
| "On [10/16/99], at approximately 0247 MST, an earthquake, referred to as the |
| 'Hector Earthquake,' of approximate magnitude 7.0 occurred, its epicenter |
| located about 32 miles north of Joshua Tree, California. Joshua Tree, |
| California is located approximately 220 miles west of the Palo Verde Nuclear |
| Generating Station. At approximately 0248 MST, the vibratory ground motion |
| reached and actuated the Palo Verde Seismic Monitoring Instrumentation |
| switches. Specifically, the strong motion accelerometer trigger located in |
| the Unit 1 containment building tendon gallery exceeded the threshold value |
| of 0.01g. The vibratory ground motion also was felt by personnel in all |
| three Palo Verde control rooms. Operations personnel immediately retrieved |
| data from the actuated instrument and performed analysis to determine the |
| magnitude of the vibratory ground motion. Initial analysis of the Seismic |
| Monitoring Instrumentation tape recordings completed at approximately 0305 |
| MST indicated a seismic event of about 0.015g. This is well below the |
| magnitude of the 0.10g spectra Operating Basis Earthquake (OBE) and the |
| 0.20g spectra Safe Shutdown Earthquake (SSE). Based on the validation of |
| the earthquake per the Emergency Action Level 6.6 Technical Bases, the Unit |
| 1 Shift Manager declared (and immediately exited due to the event being |
| over) a Notification of an Unusual Event (NUE) applicable to all three units |
| due to a seismic event." |
| |
| "The NRC was notified at 0353 MST on 10/16/99 via the Emergency Notification |
| System (ENS). The criteria for the ENS notification were |
| 10CFR50.72(a)(1)(i) due to the declaration of an Emergency Class and |
| 10CFR50.72(b)(1)(iii) due to the natural phenomenon that poses an actual |
| threat to the safety of the nuclear power plant. Further analysis of the |
| seismic data concluded the measured motions of structures and components |
| were less than 14% of the OBE and should have no effect upon facility |
| features important to safety. Based on the low magnitude of the vibratory |
| ground motion and satisfactory plant walkdowns, an actual threat to safety |
| did not exist. The ENS notification per 10CFR50.72(b)(1)(iii) is hereby |
| retracted. The initial notification stated a press release was expected to |
| be made; therefore, 10CFR50.72(b)(2)(vi) also applied. No media interest |
| existed; therefore, no press release was made. The ENS notification per |
| 10CFR50.72(a)(1)(i) remains valid." |
| |
| "Following declaration of the NUE, the Maricopa County Sheriff's Office and |
| the Arizona Department of Public Safety were notified at approximately 0313 |
| MST via the Notification and Alert Network (NAN). The Palo Verde Emergency |
| Coordinator recommended that no protective actions be taken. No protective |
| actions were implemented by state or county agencies." |
| |
| "Operations personnel performed an immediate walkdown of plant equipment. |
| No abnormalities caused by the seismic event were observed. There were no |
| structures, systems, or components that were inoperable that contributed to |
| this event. There were no failures that rendered a train of a safety system |
| inoperable, and no failures of components with multiple functions were |
| involved. No engineered safety feature (ESF) actuations occurred, and none |
| were required. The event did not result in any challenges to the fission |
| product barrier or result in any releases of radioactive materials. The |
| event did not adversely affect the safe operation of the plant or health and |
| safety of the public." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R4DO (Good), NRR EO (Bateman), and IRO (Congel). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36305 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/18/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 12:53[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/1999|
+------------------------------------------------+EVENT TIME: 10:55[CDT]|
| NRC NOTIFIED BY: SCOTT SWANSON |LAST UPDATE DATE: 10/18/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|BAAA 20.1906(d) SURFACE CONT/ EXT RAD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 93 Power Operation |93 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SHIPMENT RECEIVED WITH SURFACE CONTAMINATION IN EXCESS OF SHIPPING LIMITS. |
| |
| A shipment containing a portable demineralizer resin tank received from the |
| Point Beach Nuclear Station had external removable contamination in excess |
| of shipping limits. Smears taken from the shipment were placed in a |
| radiation detector, and readings of up to 52,800 dpm were observed. The |
| licensee has contacted the shipper (Hitman). |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36306 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ST. JOHN'S HOSPITAL |NOTIFICATION DATE: 10/18/1999|
|LICENSEE: ST. JOHN'S HOSPITAL |NOTIFICATION TIME: 14:35[EDT]|
| CITY: DETROIT REGION: 3 |EVENT DATE: 09/07/1999|
| COUNTY: STATE: MI |EVENT TIME: [EDT]|
|LICENSE#: 21-03210-01 AGREEMENT: N |LAST UPDATE DATE: 10/18/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRUCE JORGENSEN R3 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WALTER NIKESCH | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION |
| |
| While performing a monthly audit, the licensee discovered that a patient, |
| who had been prescribed a dose of 200 mCi of I-131 for thyroid ablation, was |
| administered a dose of 264 mCi of I-131. The misadministration occurred on |
| 9/7/1999. The attending physician has been informed of the |
| misadministration. The licensee has also contacted NRC Region III (J. |
| Cameron). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36307 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 10/18/1999|
|LICENSEE: MILLER PACIFIC ENGINEERING GROUP |NOTIFICATION TIME: 19:00[EDT]|
| CITY: SANTA ROSA REGION: 4 |EVENT DATE: 10/18/1999|
| COUNTY: STATE: CA |EVENT TIME: 02:00[PDT]|
|LICENSE#: 5411-21 (CA) AGREEMENT: Y |LAST UPDATE DATE: 10/18/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONALD BUNN | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN MOISTURE/DENSITY GAUGE |
| |
| A representative of the California State Radiation Control Program reported |
| the theft of a CPM Model MC-1DR moisture/density gauge from a state |
| licensee. The gauge contains one 10-mCi Cs-137 source, and one 40-mCi |
| Am-241/Be source. The local police are investigating the theft and plan to |
| file a report with the state. The licensee has issued a press release |
| regarding the theft. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36308 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/18/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 20:28[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/18/1999|
+------------------------------------------------+EVENT TIME: 15:12[CDT]|
| NRC NOTIFIED BY: WILLIAM B. GREEN |LAST UPDATE DATE: 10/18/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SPURIOUS BUS UNDERVOLTAGE ALARM CAUSES VARIOUS ESF ACTUATIONS. |
| |
| "At 1512 CDT on 10/18/99, 4160 bus 1B [undervoltage annunciator] alarmed and |
| 4160 bus 1B breaker 1BG, the normal power supply to essential 4160 bus 1G, |
| tripped. The emergency transformer, through breaker 1GS, began supplying |
| power to essential 4160 bus 1G. Diesel generator #2 automatically started on |
| the undervoltage condition but did not load since essential bus 1G was being |
| supplied by the emergency transformer as designed. |
| |
| "Primary containment isolation system (PCIS) Group isolations for [the] |
| reactor water cleanup system and reactor building isolation occurred due to |
| a loss of power. Emergency Operating Procedure 5A, Secondary Containment |
| Control, was entered due to reactor building pressure going positive, the |
| maximum value reached during the transient was +0.01 inches water gage. Both |
| trains of standby gas treatment started on the Group 6 isolation and |
| returned reactor building pressure to a negative value. |
| |
| "PCIS Group Isolations 2 and 7 had some valves reposition. These valves were |
| consistent with valves that would reposition on a loss of power. However, |
| two valves normally actuated by a half group isolation on the division 2 |
| side did not reposition. It is believed that this condition occurred due to |
| the speed of actuation of relays in the PCIS system and is being |
| investigated. |
| |
| "Circulating water pump 1C tripped during the transient, and the steam jet |
| air ejectors (SJAE) isolated during the electrical transient. These |
| conditions caused main condenser vacuum to lower to a point that the turbine |
| generator low vacuum pre-trip alarm was received at 25 inches Hg lowering. |
| The SJAEs were reset, and vacuum in the main condenser began to rise. The |
| lowest vacuum indicated was 24.5 inches Hg. Vacuum is currently 26.5 inches |
| Hg. |
| |
| "At the time of the event, Electrical Maintenance Personnel were installing |
| monitoring equipment in the condensate pump B cubicle. |
| |
| "4160 Bus 1G is currently being supplied from the emergency transformer, and |
| diesel generator #2 [was] returned to a normal standby lineup at 1634 [CDT]. |
| The electrical grid is stable, and the reactor and secondary plant are in a |
| stable condition. |
| |
| "The undervoltage alarm for 4160 bus 1B is still actuated even though an |
| actual undervoltage does not exist on the bus. A team of personnel is |
| investigating the undervoltage condition at this time." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021