Event Notification Report for March 22, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/19/1999 - 03/22/1999
** EVENT NUMBERS **
35487 35488 35489 35490 35491 35492 35493 35494 35495 35496
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35487 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/19/1999|
| UNIT: [] [2] [] STATE: AZ |NOTIFICATION TIME: 11:06[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/19/1999|
+------------------------------------------------+EVENT TIME: 08:24[MST]|
| NRC NOTIFIED BY: BRAD EKLUND |LAST UPDATE DATE: 03/19/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PHIL HARRELL R4 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TRAIN B OF CONTAINMENT SPRAY DECLARED INOPERABLE |
| |
| "On March 19, 1999 at approximately 0824 MST, engineering personnel |
| determined that a pipe support on the Unit 2 Train B containment spray |
| recirc line piping would not perform its function to support the |
| mini-recirculation piping and could result in a rupture of the pipe during a |
| Recirculation Actuation Signal following a loss of coolant accident. |
| |
| "Operations personnel have declared Train B containment spray system |
| inoperable per Technical Specification 3.6.6. |
| |
| "This condition is being reported because suitable redundancy for |
| Containment Spray (two trains operable) was not maintained and is therefore |
| considered outside design bases. |
| |
| "The event did not result in any challenges to the fission product barrier |
| or result in any releases of radioactive materials. There were no adverse |
| safety consequences or implications as a result of this event. The event |
| did not adversely affect the safe operation of the plant or health and |
| safety of the public. An investigation is in progress to determine the |
| cause of the event. |
| |
| "Engineering personnel are preparing a change to the piping support design |
| with expected completion within the Technical Specification allowed |
| Completion Time of 72 hours. |
| |
| "This condition does not apply to the other train of Unit 2 or Palo Verde |
| Units 1 or 3." |
| |
| The licensee informed the NRC Resident Inspector of this notification. |
| |
| * * * UPDATE AT 1635 ON 3/19/99 BY HAZELWOOD, TAKEN BY WEAVER * * * |
| The licensee desires to retract this event. The design intent of the |
| support is to restrain pipe motion in the vertical direction only. The |
| support is not intended to restrain pipe motion in the axial direction. |
| Subsequent re-inspection of the subject pipe support determined the |
| existence of a gap beneath the bottom end plate. Given the existence of |
| this gap, the pipe support will function as originally intended. |
| Accordingly, there would be no overload condition and the pipe support is |
| acceptable and in accordance with design. Following racking in the pump |
| breaker and performing a functional run, Operations declared the Train B |
| Containment Spray System operable. |
| |
| The licensee informed the NRC resident inspector. The HOO notified the R4DO |
| (Harrell). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35488 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/19/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 11:51[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/19/1999|
+------------------------------------------------+EVENT TIME: 10:00[EST]|
| NRC NOTIFIED BY: ROBERT M. PEAL |LAST UPDATE DATE: 03/19/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Main Steam Isolation Valves Fail to meet Leakage Criteria |
| |
| The following report is due to the Main Steam Isolation Valves failing the " |
| as found" Maximum Combined Pathway Leakage criteria of 300 scfh. This |
| failure requires a 4 Hr ENS notification under 10CFR50.72(b)(2)(i.). The |
| overall Total Combined Maximum Pathway Leakage can not to be determined |
| based on the inability to pressurize the 'C' Outboard and 'D' Inboard Main |
| Steam Isolation Valves. The 'as found' Minimum Combined Pathway Leakage is |
| 255 scfh, which is below the 300 scfh used in the Offsite Dose Analysis. The |
| 'as left' leakage is to be determined following rework of the 'C' Outboard |
| and 'D' Inboard Main Steam Isolation Valves. |
| |
| The licensee has notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35489 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLOWER HOSPITAL |NOTIFICATION DATE: 03/19/1999|
|LICENSEE: FLOWER HOSPITAL |NOTIFICATION TIME: 12:43[EST]|
| CITY: SYLVANIA REGION: 3 |EVENT DATE: 03/18/1999|
| COUNTY: STATE: OH |EVENT TIME: 16:45[EST]|
|LICENSE#: 34-15184-01 AGREEMENT: N |LAST UPDATE DATE: 03/19/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GEOFFREY WRIGHT R3 |
| |DR. COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DR. JUSTICE | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISADMINISTRATION |
| |
| A Cs-137 BRACHYTHERAPY source was found in a patient's stool during a |
| routine survey. The survey was conducted prior to removal of the material |
| from the patient's room. The source was one of two being used to provide |
| an intended dose to the patient of 65 Gray. Each source had an activity of |
| 11 mg Radium equivalent. The other source remained in place during the |
| treatment period. The licensee is conducting an investigation to determine |
| how and when the source became dislodged. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35490 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 03/19/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 12:58[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/12/1999|
+------------------------------------------------+EVENT TIME: 04:29[EST]|
| NRC NOTIFIED BY: GEORGE STOTLOLIS |LAST UPDATE DATE: 03/19/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTAINMENT EQUIPMENT HATCH NOT PROPERLY SECURED |
| |
| "On March 12, 1999, it was identified that air was being drawn into the |
| Beaver Valley Power Station (BVPS) Unit No. 2 containment through the closed |
| equipment hatch while the reactor was being de-fueled. Fuel movement was |
| halted until the equipment hatch bolts were re-tightened and the inleakage |
| was terminated. The inleakage was caused by a pressure differential across |
| the equipment hatch set up by the containment ventilation. The design basis |
| fuel handling accident for BVPS Unit No. 2 assumes that there is no pressure |
| differential across the containment equipment hatch since the containment |
| ventilation would be automatically secured upon a high radiation signal. It |
| was originally believed that the door would have been able to contain any |
| air transfer without the pressure differential across the door since it was |
| closed with ten bolts in place versus the four required by Technical |
| Specification 19.4 during fuel movement. |
| |
| "Information was obtained on March 19, 1999 that 1) the containment |
| equipment hatch may have become ajar due to inadequate support during an |
| equipment hatch chain hoist preventative maintenance and 2) there was a |
| sufficient separation between the containment wall and the equipment hatch |
| door to allow some light to be seen on the inside of containment coming from |
| the outside. Given this information, it could not be concluded that the |
| containment capability of the equipment hatch would have been sufficient to |
| have performed its safety function during a fuel handling accident if it |
| were postulated to occur. Since the BVPS Unit No. 2 design basis fuel |
| handling accident inside containment concludes that environmental release is |
| precluded, this condition violated the UFSAR safety analysis. Therefore this |
| indication of an air gap through the closed containment equipment hatch is |
| being reported as a condition that alone could have prevented the |
| fulfillment of the safety function of structures or systems that are needed |
| to control the release of radioactive material pursuant to 10 CFR |
| 50.72(b)(2)(iii)(C)." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35491 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/19/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 14:50[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/19/1999|
+------------------------------------------------+EVENT TIME: 14:10[EST]|
| NRC NOTIFIED BY: TOM MCKEE |LAST UPDATE DATE: 03/19/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - FREON RELEASE |
| |
| The licensee notified the New York Department of Environmental Conservation |
| of a freon leak. More than one pound of freon is believed to have leaked |
| from the air conditioning unit that supports the Technical Support Center. |
| |
| The licensee will inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35492 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 03/20/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 04:08[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/20/1999|
+------------------------------------------------+EVENT TIME: 02:50[EST]|
| NRC NOTIFIED BY: ALLEN |LAST UPDATE DATE: 03/20/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| THE "A" HPCI WAS DECLARED INOPERABLE, RESULTING IN A 7 DAY LCO ACTION |
| STATEMENT. |
| |
| THE "A" HPCI ISOLATION LOGIC WAS DE-ENERGIZED, MAKING HPCI INOPERABLE, DUE |
| TO A 130VDC BATTERY GROUND. THIS CONDITION ALSO ACTUATED VALVES "23MOV-15" |
| (INBOARD STEAM ISOLATION VALVE) AND "23MOV-58" (INBOARD TORUS SUCTION |
| VALVE). BOTH PENETRATIONS HAVE BEEN ISOLATED AND DE-ENERGIZED WITHIN 1 |
| HOUR AS REQUIRED BY TECH SPECS. THE CAUSE OF THE GROUND IS UNKNOWN AND |
| BEING INVESTIGATED. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35493 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 03/20/1999|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 15:11[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/20/1999|
+------------------------------------------------+EVENT TIME: 14:01[EST]|
| NRC NOTIFIED BY: ROBERT SOCHIA |LAST UPDATE DATE: 03/20/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 90 Power Operation |90 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - SODIUM HYPOCHLORITE LEAK |
| |
| A sodium hypochlorite leak was discovered emanating from the SW/ESW sodium |
| hypochlorite tank into its surrounding dike. The leak of about 1500 gallons |
| is completely contained within the dike. The licensee notified the U.S. |
| EPA, the Ohio EPA, the U.S. Coast Guard and Lake County. |
| |
| The NRC resident inspector was informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35494 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/20/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 20:20[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/20/1999|
+------------------------------------------------+EVENT TIME: 18:57[EST]|
| NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 03/20/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RCIC INOPERABLE |
| |
| The licensee declared Reactor Core Isolation Cooling (RCIC) inoperable |
| because of a problem found during a surveillance. Relay 13A-k30 contacts 1 |
| - 7 were found to have a high resistance. These contacts close to provide |
| the 'A' channel input to the RCIC high level shutdown. A high resistance |
| across these contacts may prevent the actuating relay (13A-k38) from |
| energizing, and thereby prevent a shutdown of RCIC on a high reactor vessel |
| water level. The RCIC high water level shutdown requires both channels 'A' |
| and 'B' signals be present to occur. |
| |
| The licensee entered a 14 day LCO because of this condition. Repair |
| efforts are in progress. RCIC remains available for use in the event of an |
| emergency. |
| |
| The licensee will inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35495 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/21/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 05:18[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/21/1999|
+------------------------------------------------+EVENT TIME: 03:30[CST]|
| NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 03/21/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 99 Power Operation |99 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ROD BLOCK MONITORS 7&8 ARE OUT OF SERVICE AND THE PLANT ENTERED AN LCO. |
| |
| THE ROD BLOCK MONITORS (RBM) WERE FOUND TO HAVE INOPERABLE LPRM COUNT |
| CIRCUITS. DEPENDING ON THE CONTROL ROD SELECTED, BOTH RBM 7&8 DETECTED MORE |
| LPRM INPUTS THAN WERE ACTUALLY PRESENT. WITH THIS CONDITION OCCURRING, THE |
| RBM WOULD NOT PROVIDE THE REQUIRED "INOP" TRIP (ROD BLOCK DUE TO TOO FEW |
| INPUTS). THE HI ROD BLOCK TRIP WAS ALSO NON-CONSERVATIVE SINCE LPRM SIGNALS |
| NOT ASSOCIATED WITH THE SELECTED LPRM STRING ROD GROUP WERE BEING AVERAGED |
| IN WITH THAT GROUP'S NORMAL INPUTS. AS REQUIRED BY THE LCO ACTION |
| STATEMENT, ONE (#8) OF THE RBM CHANNELS WAS TRIPPED AND TAKEN OUT OF |
| SERVICE. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35496 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/21/1999|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 12:43[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/21/1999|
+------------------------------------------------+EVENT TIME: 11:38[CST]|
| NRC NOTIFIED BY: HAL DODD |LAST UPDATE DATE: 03/21/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 38 Power Operation |37 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| The licensee commenced a plant shutdown at 1138 CST because of non-isolable |
| pressure boundary leakage in the 'B' recirculation loop. A drywell entry |
| was initiated due to an increase in the drywell activity reading. A leak |
| was discovered from flow element 3-261-9B tap at a tee in a welded fitting |
| that attaches to the flow venturi. The leak rate is estimated to be 0.25 |
| gpm. |
| |
| The licensee plans to bring the plant to cold shutdown to make repairs. The |
| plant is expected to come off line at 1400 CST and be in cold shutdown by |
| approximately 1800 CST. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021