Event Notification Report for January 26, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/25/2000 - 01/26/2000
** EVENT NUMBERS **
36558 36620 36621 36622 36623 36624 36625 36626 36627 36628
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36558 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/03/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 16:14[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/03/2000|
+------------------------------------------------+EVENT TIME: 14:45[EST]|
| NRC NOTIFIED BY: M ABRAMSKI |LAST UPDATE DATE: 01/25/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIMI YEROKUN R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE. |
| |
| During Technical Specification required surveillance testing an oil leak was |
| detected on a fitting in the HPCI hydraulic governor control system (EGR |
| actuator). It was determined that had this leak developed during accident |
| conditions, the HPCI system may not have been able to perform it's intended |
| function for the duration of time required. The licensee entered the |
| appropriate Technical Specification for declaring HPCI inoperable (7 day |
| Limiting Condition of Operation). All other Emergency Core Cooling Systems |
| and the Reactor Core Isolation Cooling system are fully operable if needed. |
| The licensee is preparing to repair the HPCI hydraulic governor control |
| system oil leak. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1412 EST ON 1/25/00 BY JAMES COSTEDIO TO FANGIE JONES * * |
| * |
| |
| The licensee has performed an engineering evaluation of the reported oil |
| leak and determined that the amount of oil expected to be lost as a result |
| would not have resulted in inadequate oil level. HPCI would have been able |
| to perform its intended function for the duration of time required. |
| Therefore, this event notification has been retracted. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The R1DO (John Rogge) has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36620 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 01/24/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 22:37[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 01/24/2000|
+------------------------------------------------+EVENT TIME: 22:15[EST]|
| NRC NOTIFIED BY: HENRY MANOS |LAST UPDATE DATE: 01/26/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|AENS 50.72(b)(1)(v) ENS INOPERABLE | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| MORE THAN 25% OF THE OFFSITE WARNING SIRENS LOST DUE TO ICE STORMS |
| |
| The licensee reported the loss of more than 25% of the offsite warning |
| sirens due to ice storms passing through the local area. The licensee will |
| be contacting the power suppliers of the sirens to take action to recover |
| them. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1315 EST ON 1/26/00 BY BLAIR WILSON TO FANGIE JONES * * * |
| |
| Greater than 75 % of the emergency sirens (86 %) have been restored to |
| service, this is the last update as the minimum number operable is met. The |
| NRC Resident Inspector has been notified. |
| |
| The R2DO (Caudle Julian) has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36621 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/25/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 06:44[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/25/2000|
+------------------------------------------------+EVENT TIME: 06:10[EST]|
| NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 01/25/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| BROKEN WINDOW IN A HIGH ENERGY LINE BREAK DOOR PLACES THE PLANT IN AN |
| UNANALYZED CONDITION |
| |
| A Broken Window in a High Energy Line Break Door which is located between |
| the Main Feed Regulating Valve Room and the Auxiliary Boiler Feed Pump Room |
| places the plant in an unanalyzed condition. Maintenance is fabricating a |
| metal replacement part to cover the opening. The Door is supposed to remain |
| closed at all times when the plant is above 350 degrees F. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36622 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 01/25/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 07:32[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 01/25/2000|
+------------------------------------------------+EVENT TIME: 07:07[EST]|
| NRC NOTIFIED BY: JAMES BRIGGS |LAST UPDATE DATE: 01/25/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 95 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE ORGANIZATION (ERO) ABILITY REDUCED BY HEAVY SNOW STORM |
| |
| |
| The plant is operating at 95% power. Unusually heavy snow has reduced the |
| ability of the ERO organization to respond to the site in a timely manner. |
| Plant equipment is operating normally. The licensee is trying to get |
| vehicles that can be used to transport essential personnel to their EOF and |
| the TSC if they are needed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 1725 EST ON 1/25/00 BY MIKE WEBER TO FANGIE JONES * * * |
| |
| Weather conditions have improved and the roads are cleared such that ERO |
| manning can be accomplished in required time. The licensee notified the NRC |
| Resident Inspector. |
| |
| The R2DO (Caudle Julian) has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36623 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 01/25/2000|
| UNIT: [2] [] [] STATE: SC |NOTIFICATION TIME: 08:45[EST]|
| RXTYPE: [2] W-3-LP |EVENT DATE: 01/25/2000|
+------------------------------------------------+EVENT TIME: 07:50[EST]|
| NRC NOTIFIED BY: BAUCOM |LAST UPDATE DATE: 01/26/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| LOSS OF AC POWER TO 23 OF 45 EMERGENCY SIRENS DUE TO SNOW AND ICE. |
| |
| Due to recent accumulation of snow and ice, sporadic power outages have |
| occurred in the area. This has resulted in "loss of AC power" indications |
| for 23/45 Public Warning Sirens per their remote siren monitoring system. |
| This is considered a loss of off-site response capability . Actions are |
| being initiated to restore operability. Local surrounding counties will be |
| notified of this condition. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 1509 EST ON 1/25/00 BY PETER YANDOW TO FANGIE JONES * * * |
| |
| Power outages continue to be a problem in the Darlington, Lee, and |
| Chesterfield counties affecting the public warning sirens. A total of 31 of |
| 45 have been out-of-service, but restorations have brought the number down |
| to 26 of 45 out-of-service. The NRC Resident Inspector has been notified. |
| |
| The R2DO (Caudle Julian) has been informed. |
| |
| * * * UPDATE AT 1533 EST ON 1/26/00 BY PETER YANDOW TO FANGIE JONES * * * |
| |
| Greater than 75 % of the emergency sirens (only 9 of 45 remain |
| out-of-service) have been restored to service, this is the last update as |
| the minimum number operable is met. The NRC Resident Inspector has been |
| notified. |
| |
| The R2DO (Caudle Julian) has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36624 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 01/26/2000|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 04:29[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/26/2000|
+------------------------------------------------+EVENT TIME: 00:39[EST]|
| NRC NOTIFIED BY: JEFF EPPERSON |LAST UPDATE DATE: 01/26/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|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
+------------------------------------------------------------------------------+
| UNIT 2 ENTERED TECH SPEC 3.0.3 DUE TO BOTH TRAINS SAFETY INJECTION |
| INOPERABLE |
| |
| "AT 0039 EST ON 1/26/2000 BOTH TRAINS OF THE SAFETY INJECTION PUMPS (SIPs) |
| OF SEQUOYAH UNIT 2 WERE RENDERED INOPERABLE. THE '2A' SAFETY INJECTION PUMP |
| AND ITS ROOM COOLER WERE TAGGED OUT UNDER THE SITES TAGOUT PROCEDURE FOR |
| MAINTENANCE. EITHER OF THESE COMPONENTS [SI PUMP OR ITS ASSOCIATED ROOM |
| COOLER] BEING TAGGED MADE THE PUMP INOPERABLE. WHILE THE '2A' SI PUMP WAS |
| INOPERABLE, MAINTENANCE WORKERS MISTAKENLY DRAINED THE OIL FROM THE '2B' |
| SAFETY INJECTION PUMP MOTOR BEARING FOR A PERIOD OF TIME WHICH MADE IT |
| INOPERABLE AND UNAVAILABLE. THIS OIL CHANGING EVOLUTION REQUIRED |
| APPROXIMATELY 30 MINUTES TO ACCOMPLISH. THE SIMULANTEOUS INOPERABILITY OF |
| BOTH UNIT 2 SI PUMPS REQUIRED ENTRY INTO TECHNICAL SPECIFICATION LCO 3.0.3 |
| ACTION. IMMEDIATE STEPS WERE INITIATED TO RESTORE OPERABILITY TO '2B' SI |
| PUMP. AT 0316 EST ON 1/26/2000 THE '2B' SI PUMP WAS DECLARED OPERABLE WHEN |
| THE PUMP WAS SUCCESSFULLY RUN. LCO 3.0.3 ACTION WAS THEN EXITED. AN |
| INVESTIGATION INTO THE CAUSE OF THIS EVENT WILL BE CONDUCTED." |
| |
| MAINTENANCE WORKERS WERE TAKING A SAMPLE OF THE BEARING OIL FOR ANALYSIS |
| WHICH IS USUALLY ACCOMPLISHED THROUGH DRAINING. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36625 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 01/26/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 07:42[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/26/2000|
+------------------------------------------------+EVENT TIME: 06:48[EST]|
| NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 01/26/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|ACCS 50.72(b)(1)(iv) ECCS INJECTION |FRANK CONGEL IRO |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER |
| LEVEL DUE TO A FEEDWATER (FW) CONTROL FAILURE |
| |
| AT APPROXIMATELY 0648 EST ON 1/26/2000 CONTROL ROOM OPERATORS RESPONDED TO A |
| FEEDWATER CONTROL FAILURE ALARM. WHILE INVESTIGATING, FEEDWATER PUMP SPEED |
| DECREASED CAUSING REACTOR VESSEL WATER LEVEL (RVWL)TO DROP FROM ITS NORMAL |
| OPERATING LEVEL OF 37.5" TO APPROXIMATELY -45". AT 0" AN AUTOMATIC REACTOR |
| SCRAM AND GROUP 2 ENGINEERED SAFEGUARDS FEATURES (ESF) ACTUATION OCCURRED, |
| AS EXPECTED. ALL CONTROL RODS FULLY INSERTED. AT -38" BOTH THE HIGH |
| PRESSURE COOLANT INJECTION (HPCI) AND REACTOR CORE ISOLATION COOLING (RCIC) |
| SYSTEM RECEIVED A START SIGNAL. HPCI INJECTED UNTIL THE HPCI PUMP TRIPPED |
| AT ITS RVWL SETPOINT OF 51.5". THE FW PUMPS TRIPPED AT 58" WITH RVWL SWELL |
| CAUSING LEVEL TO REACH 100". FOLLOWING THE LEVEL TRANSIENT OPERATORS HAD |
| DIFFICULTY IN ESTABLISHING THE LO-LO SET RANGE FOR PRESSURE CONTROL. |
| NORMALLY, ONE OF THE FOUR SAFETY RELIEF VALVES USED FOR PRESSURE CONTROL, |
| i.e., "H", "A", "G", OR "C" SRV, IS OPENED ELECTRICALLY FROM THE CONTROL |
| ROOM WHICH THEN ESTABLISHES THE LOWER PRESSURE CONTROL. TEN OF THE ELEVEN |
| SRVs FAILED TO OPEN IN RESPONSE TO CONTROL ROOM SWITCH POSITIONING. THE |
| LAST SRV ATTEMPTED, THE "B" SRV, OPENED. UNIT 1 IS CURRENTLY STABLE IN HOT |
| SHUTDOWN REJECTING DECAY HEAT TO THE TORUS WITH BOTH TRAINS OF SUPPRESSION |
| POOL COOLING IN SERVICE. EFFORTS ARE UNDERWAY TO RESTORE THE MAIN CONDENSER |
| AS A HEAT SINK. UNIT 1 INTENDS TO COOLDOWN TO INVESTIGATE AND RESOLVE THE |
| PROBLEM WITH THE SRVs. THERE IS NO INDICATION THAT THE SRV MECHANICAL |
| SAFETY OR ADS FUNCTION IS IMPAIRED AT THIS TIME. DURING THE TRANSIENT, |
| REACTOR COOLANT SYSTEM (RCS) TEMP AND PRESSURE DECREASED FROM THEIR NORMAL |
| AT POWER VALUES OF 532 DEGREES F AND 1035 PSIG TO AN OBSERVED MINIMUM OF 480 |
| DEGREES F AND 871 PSIG. BOTH ARE CURRENTLY AT 510 DEGREES F AND 977 PSIG. |
| THERE IS NO INDICATION THAT THE 100 DEGREES F/ HR COOLDOWN RATE WAS |
| EXCEEDED. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36626 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/26/2000|
| UNIT: [1] [2] [3] STATE: CT |NOTIFICATION TIME: 11:06[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/26/2000|
+------------------------------------------------+EVENT TIME: 09:47[EST]|
| NRC NOTIFIED BY: STEVE LAWHEAD |LAST UPDATE DATE: 01/26/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |FRANK CONGEL IRO |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE/LOCAL AGENCIES INVOLVING ERRONEOUS EMERGENCY |
| |
| "At 0947 on January 26, 2000 a notification to offsite emergency response |
| agencies was made in error. The notification indicated that a General |
| Emergency had been declared at Millstone. No emergency conditions currently |
| exists at the site. The notification occurred during testing of the primary |
| notification system. The cause of the condition is being investigated at |
| this time. Backup means of notification is available in the event that a |
| bonafide emergency condition arises prior to the restoration of the primary |
| notification system. |
| |
| "Retractions of the event notification were issued to appropriate State and |
| local agencies. Millstone emergency management personnel have also been in |
| contact with representatives of these agencies." |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36627 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SOLIDSTATE CONTROLS, INC. |NOTIFICATION DATE: 01/26/2000|
|LICENSEE: SOLIDSTATE CONTROLS, INC. |NOTIFICATION TIME: 16:11[EST]|
| CITY: COLUMBUS REGION: 3 |EVENT DATE: 01/21/2000|
| COUNTY: STATE: OH |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 01/26/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MONTE PHILLIPS R3 |
| |JOHN ROGGE R1 |
+------------------------------------------------+CAUDLE JULIAN R2 |
| NRC NOTIFIED BY: W. G. HAMPTON |GAIL GOOD R4 |
| HQ OPS OFFICER: FANGIE JONES |VERN HODGE (fax) NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR 21 - POTENTIAL DEFECT INVOLVING STATIC SWITCH CONTROL ASSEMBLY AND |
| REGULATED RECTIFIER CONTROL ASSEMBLY USED IN AN UNINTERRUPTIBLE POWER |
| SYSTEM |
| |
| This reports a potential for a defect in Static Switch Control assemblies |
| and Regulated Rectifier Control assemblies used in Uninterruptible Power |
| Systems manufactured under the Solidstate Controls, Inc., 10CFR50 Appendix B |
| Program. |
| |
| Each of the plants has been notified of this report and requested to return |
| the affected assemblies for replacement. The following plants have affected |
| components: Indian Point 2, Catawba, Oconee, Arkansas Nuclear One, |
| Waterford 3, Crystal River, Diablo Canyon, Sequoyah, and Surry. |
| |
| The problem is associated with a component part - Unijunction Transistor, |
| part number 03-650007-00, that has been found to sometimes cause random, |
| sporadic transfers of the static switch due to a higher level of sensitivity |
| to noise spikes on the input line or cause the regulated rectifier to output |
| a higher DC voltage. This increase in sensitivity will not cause the system |
| to drop power to the load, if the alternate source is not available the |
| static switch will not transfer, continuing to protect the load. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36628 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: METROPOLITAN DISTRICT |NOTIFICATION DATE: 01/26/2000|
|LICENSEE: METROPOLITAN DISTRICT |NOTIFICATION TIME: 18:23[EST]|
| CITY: HARTFORD REGION: 1 |EVENT DATE: 01/26/2000|
| COUNTY: STATE: CT |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/26/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN ROGGE R1 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EARL DELANO | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REQUIRED REPORT - EXPLOSION IN SHREDDER, NO DAMAGE TO SOURCE IN LEVEL |
| DETECTOR |
| |
| The operating procedures require notification of the NRC of any explosion in |
| the trash shredders, even if no damage occurs to the source in the level |
| measuring device. It has been determined that small gas welding bottle that |
| contained acetylene caused an explosion in the shredder at Metropolitan |
| District. The source was not damaged. Local authorities were informed and |
| the fire department made the determination of the probable cause. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021