Event Notification Report for June 23, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/22/2000 - 06/23/2000
** EVENT NUMBERS **
37031 37095 37102 37103 37104 37105 37106 37107 37108
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37031 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 05/25/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 09:21[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/25/2000|
+------------------------------------------------+EVENT TIME: 08:32[EDT]|
| NRC NOTIFIED BY: KEVIN PHILLIPS |LAST UPDATE DATE: 06/22/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| AUXILIARY BUILDING FILTERED EXHAUST MAY NOT HAVE BEEN ABLE TO PERFORM ITS |
| DESIGN FUNCTION |
| |
| The licensee discovered both doors on the vestibule to the '1A' Centrifugal |
| Charging Pump Room not fully closed, this may have prevented the Auxiliary |
| Building filtered exhaust system from maintaining a negative pressure in |
| that room. This would render both trains of Auxiliary Building exhaust |
| inoperable per Technical Specifications 3.7.12 and would require entry into |
| Technical Specification 3.0.3. The doors were closed on discovery which |
| returned the unit to compliance with Technical Specifications. |
| |
| The licensee will followup with an investigation into when and how the doors |
| came to be open. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE ON 6/22/00 @ 1610 BY BURGESS TO GOULD * * * RETRACTION |
| |
| After further engineering evaluation, it has been determined that the plant |
| was not outside the design basis during this event. Therefore, this |
| notification is being retracted. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| The Reg 2 RDO (Landis) was informed by the NRC Operations Officer. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37095 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 06/19/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 16:22[EDT]|
| RXTYPE: [1] B&W-R-LP |EVENT DATE: 06/19/2000|
+------------------------------------------------+EVENT TIME: 15:25[EDT]|
| NRC NOTIFIED BY: CRAIG GILLIG |LAST UPDATE DATE: 06/22/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECH SPEC 3.0.3 DUE TO FAILED VALVE TESTING |
| |
| The licensee was conducting Instrument and Control testing under DB-MI-03211 |
| which failed to produce the expected response for solenoid SP6A2 on valve |
| SP6A, Steam Generator Main Feedwater Valve. The problem is with the |
| solenoid or associated limit switch. Due to a lack of specific Technical |
| Specification guidance, 3.0.3 has been entered which requires the plant to |
| initiate action to place the plant in a mode in which the specification does |
| not apply. It is expected that the plant will be able to repair and test |
| prior to a full plant shutdown. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1710 EST ON 6/19/00 BY CRAIG GILLIG TO FANGIE JONES * * * |
| |
| The licensee determined the problem was with the limit switch, has exited |
| the tech spec required shutdown, and is returning to full power from 96%. |
| |
| The licensee intends to notify the NRC Resident Inspector. The R3DO (Roger |
| Lanksbury) has been notified. |
| |
| * * * UPDATE ON 6/22/00 @ 1334 BY WOLF TO GOULD * * * RETRACTION |
| |
| The suspect limit switch for solenoid valve SVSP6A2 has been adjusted and |
| satisfactorily tested via Surveillance Test DB-MI-03211. This testing |
| confirmed that the problem was only with the limit switch. The solenoid |
| valve and associated Steam Generator Main Feedwater Control Valve SPGA |
| remained operable during this event. Therefore, the plant was not in the |
| Action Statement for Technical Specification 3.0.3, and no plant shutdown |
| was required. Therefore, the licensee desires to retract this event. |
| |
| The NRC Resident Inspector has been notified of the retraction by the |
| licensee. |
| |
| The Reg 3 RDO (Lanksbury) was informed by the NRC Operations Officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37102 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 06/22/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 09:57[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 06/22/2000|
+------------------------------------------------+EVENT TIME: 07:28[CDT]|
| NRC NOTIFIED BY: JOHN WASHKO |LAST UPDATE DATE: 06/22/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 98 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - AUTO REACTOR SCRAM FROM 98% POWER CAUSED BY LOSS OF REACTOR FEEDWATER PUMP |
| - |
| |
| At 0728 CDT on 06/22/00, LaSalle Unit 2 experienced an automatic reactor |
| scram from 98% power due to low reactor vessel water level (+12.5 inches, |
| Level 3). Normal reactor vessel water level is +36 inches. The low reactor |
| vessel water level was caused by a loss of the #2A turbine driven reactor |
| feedwater pump for unknown reasons. The lowest reactor vessel water level |
| reached was -23 inches on the wide range recorders. All control rods |
| inserted completely. Steam is being dumped to the main condenser. No |
| emergency core cooling system actuations occurred or were required during |
| the transient. All systems operated as designed with the exception of the |
| Unit 2 station air compressor, which went into a surge condition. The air |
| compressor has been secured and the Unit 0 station air compressor was |
| started to pick up the additional load. Unit 2 is stable in Condition 3 |
| (Hot Shutdown) with reactor vessel water level and pressure being maintained |
| in their normal bands. The licensee is investigating the cause of the #2A |
| reactor feedwater pump loss. |
| |
| This event had no effect on Unit 1 which is at 100% power. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37103 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OHIO BUREAU OF RADIATION PROTECTION |NOTIFICATION DATE: 06/22/2000|
|LICENSEE: DAVID V. LEWIN CORPORATION |NOTIFICATION TIME: 11:18[EDT]|
| CITY: TWINSBURG REGION: 3 |EVENT DATE: 06/21/2000|
| COUNTY: STATE: OH |EVENT TIME: 10:00[EDT]|
|LICENSE#: 31-210180022 AGREEMENT: Y |LAST UPDATE DATE: 06/22/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROGER LANKSBURY R3 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MIKE SNEE | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|NDAM DAMAGED GAUGE/DEVICE | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - DAMAGED CPN PORTABLE MOISTURE DENSITY GAUGE |
| |
| At 1000 on 06/21/00, a CPN portable moisture density gauge belonging to |
| David V. Lewin Corporation, Cleveland, OH, was damaged at a construction |
| site at State Route 91 a mile north of Twinsburg, OH. The gauge had been |
| struck by a backhoe while the Cs-137 source was extended from the gauge. |
| The gauge is a CPN model MC3 containing a 10 mCi Cs-137 source and a 50 mCi |
| Am-241 source. The gauge was damaged in a way that prevented the Cs-137 |
| source from being secured in the safe position. The licensee contacted CTS, |
| license #03225230000, a licensed gauge repair facility for advice. Ohio |
| Department of Health inspectors were dispatched to the site to monitor the |
| recovery. |
| |
| CTS recommended that the guide tube be cut which would allow the Cs-137 |
| source to be retracted into the safe position. The guide tube was cut and |
| the source was secured in the safe position. The source was not damaged and |
| no contamination was detected. Dose rates with the source extended were 350 |
| mrem/hr. |
| |
| The gauge was taken back to the David V. Lewin Corporation and will be |
| shipped to CTS for evaluation and possible repair. The licensee will issue |
| a report to the Ohio Department of Health within 30 days. |
| |
| Ohio Report #00-019. |
| |
| Mike Snee notified NRC Region 3 Jim Lynch. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 37104 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: GEORGE WASHINGTON UNIV. HOSPITAL |NOTIFICATION DATE: 06/22/2000|
|LICENSEE: GEORGE WASHINGTON UNIV. HOSPITAL |NOTIFICATION TIME: 16:51[EDT]|
| CITY: WASHINGTON REGION: 1 |EVENT DATE: 06/14/2000|
| COUNTY: STATE: DC |EVENT TIME: 14:30[EDT]|
|LICENSE#: 08-00216-22 AGREEMENT: N |LAST UPDATE DATE: 06/22/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROBERT SUMMERS R1 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOHNSON | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GEORGE WASHINGTON UNIVERSITY HOSPITAL REPORTED AN UNDERTREATMENT DURING |
| BRACHYTHERAPY. |
| |
| THE HOSPITAL REPORTED THAT A FEMALE PATIENT WAS BEING TREATED WITH CESIUM |
| 137 SEEDS IN THE FIRST OF A TWO PHASE TREATMENT SEQUENCE WITH EACH |
| DELIVERING APPROXIMATELY 1,680 RADS. DURING THIS TREATMENT THE DEVICE THAT |
| CONTAINED THE SEEDS SLIPPED OUT OF THE AREA BEING TREATED. IT IS NOT KNOWN |
| WHEN THIS ACTUALLY OCCURRED, BUT THE UNDERTREATMENT COULD HAVE LASTED |
| BETWEEN 3.25 - 6 HOURS. THEY ARE ESTIMATING THAT THE PATIENT MAY HAVE ONLY |
| RECEIVED 1,478.5 RADS. A CORRECTION FOR THIS UNDERTREATMENT CAN BE DONE |
| DURING THE SECOND PHASE. THERE ALSO MAY HAVE BEEN OTHER AREAS NOT DESTINED |
| FOR TREATMENT THAT WERE EXPOSED TO THE RADIATION WHEN THE DEVICE SLIPPED. |
| THE PATIENT HAS BEEN REEXAMINED A WEEK FOLLOWING THIS MISADMINISTRATION AND |
| NO ADVERSE AFFECTS WERE DETERMINED. A SECOND FOLLOWUP EXAMINATION WILL BE |
| DONE WITHIN A WEEK. THE PATIENT WAS INFORMED AND THE ATTENDING PHYSICIAN |
| WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37105 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 06/22/2000|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 17:26[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 06/22/2000|
+------------------------------------------------+EVENT TIME: 15:13[CDT]|
| NRC NOTIFIED BY: GILMORE |LAST UPDATE DATE: 06/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOE TAPIA R4 |
|10 CFR SECTION: |FRANK CONGEL IRO |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE ISSUED THE FOLLOWING PRESS RELEASE REGARDING A FIRE IN A PLANT |
| SUPPORT BUILDING: |
| |
| "BURLINGTON, KS - A small, localized fire occurred early this afternoon at |
| Wolf Creek Generating Station. The fire was contained in the welding area of |
| a support building about 150 yards from where electricity is generated. The |
| fire appears to have originated from an equipment malfunction. |
| |
| No injuries were reported. |
| |
| The plant's fire brigade responded and with assistance from the Coffey |
| County Fire Department, quickly extinguished the fire. The fire was |
| extinguished at about 1:41 p.m. |
| |
| The equipment, a plasma-arc cutter, is used to cut metal such as stainless |
| steel. Workers were cutting one and one-half inch stainless when the fire |
| started. |
| |
| Wolf Creek Nuclear Operating Corporation operates Wolf Creek Generating |
| Station near Burlington, Kan. |
| Wolf Creek is owned by Kansas City Power & Light Company; KGE, a Western |
| Resources Company; and |
| Kansas Electric Power Cooperative, inc. The plant is in Coffey County, |
| Kansas, about four miles northeast of |
| Burlington. The plant is 55 miles south of Topeka, 90 miles southwest of |
| Kansas City, and 120 miles northeast |
| of Wichita." |
| |
| The fire lasted for approximately 20 minutes (1321-1341 CDT) and the only |
| damage was to the piece of equipment. |
| |
| The NRC Resident Inspector was notified by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37106 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/22/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:43[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/22/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/22/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY R3 |
| DOCKET: 0707002 |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HALCOMB | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| At 1100 hours on 06/22/00, it was determined by the Plant Shift |
| Superintendent, Engineering, and Nuclear Regulatory Affairs that Criticality |
| Accident Alarm System Technical Safety Requirement (TSR) required actions |
| were not entered as required. The concern was whether a TSR Limiting |
| Condition for Operation (LCO) should be entered prior to performing Safety |
| Analysis Review required horns and light testing. |
| |
| All previous testing has correctly been accomplished under site operability |
| procedures, even though no LCO actions were initiated due to taking credit |
| for the nitrogen system. The issue was raised due to the fact that when the |
| cascade strombos horns are sounding, the nitrogen horns could not be heard |
| to meet required LCO requirements. Currently, all plant site Criticality |
| Accident Alarm Systems are fully operable. |
| |
| This condition is reportable to the NRC per 10CFR76.120(c) "Safety Equipment |
| Failure/Actuation". The equipment is required by a TSR to be available and |
| operable and no redundant equipment is available and operable to perform the |
| required safety function. |
| |
| The DOE Site Representative and NRC Resident Inspector were notified by the |
| licensee.. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37107 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 06/22/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 18:07[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 06/22/2000|
+------------------------------------------------+EVENT TIME: 14:07[CDT]|
| NRC NOTIFIED BY: BORING |LAST UPDATE DATE: 06/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY 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 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT ENTERED A 14 DAY LCO ACTION STATEMENT DUE TO HIGH PRESSURE COOLANT |
| INJECTION (HPCI) SYSTEM BEING DECLARED INOPERABLE. |
| |
| During routine surveillance testing of the Containment Cooling Water System, |
| required system flow through the HPCI Room Cooler could not be obtained due |
| to leakage past 2-3999-252 check valve. |
| |
| With the HPCI Room Cooler inoperable, the HPCI System was declared |
| INOPERABLE, a 14 day LCO Action Statement was entered, and an action request |
| for repair of the 2-3999-252 valve was submitted. |
| |
| The NRC Resident Inspector was notified by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37108 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 06/22/2000|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 21:40[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 06/22/2000|
+------------------------------------------------+EVENT TIME: 16:16[PDT]|
| NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 06/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOE TAPIA R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AT 1616 PDT ON 06/22/00, THE LICENSEE NOTIFIED THE CALIFORNIA OFFICE OF |
| EMERGENCY SERVICES AND THE SAN DIEGO DEPARTMENT OF ENVIRONMENTAL HEALTH OF A |
| SODIUM HYPOCHLORIDE LEAK. |
| |
| At 0830 PDT on 06/22/00, a 3 to 5 gpm leak occurred from the Unit 2 sodium |
| hypochloride storage tank. As a precaution, the licensee evacuated |
| nonessential personnel from the area of the leak. The spilled liquid was |
| fully contained by a berm around the tank. This event did not pose a threat |
| to the nuclear power plant or hamper site personnel in the performance of |
| duties necessary for safe plant operation. Even though there was no threat |
| to control room personnel and plant conditions did not require it, at 1005 |
| PDT, operators manually initiated Toxic Gas Isolation Signal (TGIS) as a |
| precautionary measure in response to changing wind direction. (TGIS is |
| designed to terminate the supply of outside air to the control room and |
| initiate operation of the control room emergency HVAC system to minimize |
| operator exposure.) All system components operated as expected. |
| |
| The event was terminated at approximately 1145 PDT. There were no |
| injuries. |
| |
| The NRC Resident Inspector will be informed by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021