Event Notification Report for February 7, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/04/2000 - 02/07/2000
** EVENT NUMBERS **
36659 36660 36661 36662 36663 36664 36665 36666 36667
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36659 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 02/04/2000|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 12:18[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/04/2000|
+------------------------------------------------+EVENT TIME: 12:00[EST]|
| NRC NOTIFIED BY: W. SUSLICK |LAST UPDATE DATE: 02/04/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS 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 |
|2 N Y 65 Power Operation |65 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOW HEAD SAFETY INJECTION PUMPS SUCTION MAY SWAP FROM FWST CONTAINMENT SUMP |
| BEFORE LOW FWST LEVEL IS REACHED. |
| |
| "On February 4. 2000 during a review of engineering staff comments on a |
| proposed technical specification change, a condition was discovered that may |
| have resulted in operation outside the design basis of the plant. The |
| specific condition is a deficiency in the current ACTION statement for |
| McGuire Technical Specifications when invoked for one inoperable level |
| channel of the refueling water storage tank (FWST). Currently this Technical |
| Specification allows for the option of placing the affected channel in the |
| trip condition, operation is permitted in this condition for an indefinite |
| period of time. |
| |
| "Because Technical Specifications allow operation in this condition for an |
| indefinite period of time, this condition can not be considered a design |
| basis single failure during a design basis accident. A single failure of an |
| FWST level channel coincident with a design basis LOCA, with another channel |
| in trip as allowed by technical specifications would result in premature |
| swapover of the low head safety injection pumps to the containment sump. As |
| a result of this premature swapover both trains of low head safety injection |
| pumps could fail, which could result in a complete loss in recirculation |
| phase post accident cooling. |
| |
| "Currently all 3 channels of FWST level instrumentation of both McGuire |
| Units are operable. Therefore, the plant is not operating with this single |
| failure vulnerability. Administrative controls have been put into place to |
| limit the time which the plant could operate in this condition until such |
| time as Technical Specifications can be revised to limit this single failure |
| vulnerability" |
| |
| The NRC Resident Inspector was notified of this event by the licensee.. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36660 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/04/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 17:14[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/04/2000|
+------------------------------------------------+EVENT TIME: 16:39[EST]|
| NRC NOTIFIED BY: M VASELY |LAST UPDATE DATE: 02/04/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY DIMITRIADIS R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALIDITY OF ASSUMPTIONS FOR THE 30 MINUTE NITROGEN BACKUP SUPPLY IN QUESTION |
| |
| |
| During the review of Consolidated Edison calculation FIX0030-00, Nitrogen |
| Backup Supply for control of Auxiliary Feedwater Flow Control Valves, |
| Turbine Driven Auxiliary Feedwater Pump, and Atmospheric Steam Dump |
| Controls, questions arose as to the validity of the assumption statements |
| that resulted in the design basis for 30 minutes of Nitrogen could not be |
| sustained. The assumptions are in the process of being validated. A third |
| nitrogen bottle has been placed in backup alignment to maintain the 30 |
| minute requirement. |
| |
| 3 of the 6 Nitrogen Backup Bottles are now valved in instead of 2. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36661 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/04/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 19:36[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/04/2000|
+------------------------------------------------+EVENT TIME: 18:00[CST]|
| NRC NOTIFIED BY: ROBERT POWERS |LAST UPDATE DATE: 02/04/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY VEGEL R3 |
|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 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) DECLARED INOPERABLE |
| |
| AT 1042 CST SPDS WAS DECLARED INOPERABLE BECAUSE OF A HARDWARE PROBLEM WITH |
| THEIR PLANT PROCESS COMPUTER WHICH FEEDS DATA INTO THE SPDS. THE LICENSEE |
| HAS INCREASED MONITORING PLANT PARAMETERS. CARDS ARE BEING REPLACED IN THE |
| PROCESS PLANT COMPUTER AT THIS TIME. |
| |
| THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. |
| |
| * * * UPDATE AT 2143ET ON 02/04/00 BY HALVERSON TAKEN BY MACKINNON * * * |
| |
| SPDS RETURNED TO SERVICE AT 1847CST. R3DO (VEGEL) NOTIFIED. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36662 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/05/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:42[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/04/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:00[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/05/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |TONY VEGEL R3 |
| DOCKET: 0707001 |JOE HOLONICH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM HORN FAILED SURVEILLANCE |
| |
| At 1600 on 02-04-2000 the PSS was informed of the failure of a criticality |
| accident alarm system (CAAS) air horn to sound during the performance of |
| surveillance testing. The cause of the failure was determined to be debris |
| in the air line fouling the flow path for the horn. Subsequently, after |
| this horn was repaired and the air horn line blown out, another air horn on |
| the same branch line became clogged and would not sound sufficiently. This |
| horn was also repaired and its line blown out. The system was retested |
| satisfactorily and declared operable at 2245 on 02-04-00. It is possible |
| that the system would not have performed its intended safety function if it |
| had been required to before it was declared inoperable. |
| |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which |
| equipment required by the TSR is disabled or fails to function as designed. |
| |
| The NRC Senior Resident Inspector has been notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36663 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 02/05/2000|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 13:54[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/04/2000|
+------------------------------------------------+EVENT TIME: 20:59[CST]|
| NRC NOTIFIED BY: GREG JANAK |LAST UPDATE DATE: 02/05/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLAUDE JOHNSON R4 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| 2 TRAINS OF ESSENTIAL CHILLED WATER INOPERABLE |
| |
| On 02/04/00 at 2059 CST, Essential Chiller 12C was declared inoperable due |
| to tripping after being started at 2056 CST on 02/04/00. This resulted in |
| an entry into Technical Specification 3.7.14. Investigation revealed that |
| Essential Chiller 12C tripped on high condenser pressure which was caused by |
| not having cooling water flow properly aligned. Found Essential Cooling |
| Water valve EVV-3025 to be closed, when it's required position is throttled |
| to maintain Essential Cooling Water flow. The valve alignment was restored |
| to normal and Essential Chiller 12C was declared operable at 2358 CST on |
| 02/04/00. |
| |
| The investigation revealed that EVV-3025 was closed at approximately 1121 |
| CST on 02/02/00 as indicated on integrated computer system trends. At that |
| time Essential Chilled Water Train "B" was inoperable for planned |
| maintenance and remained inoperable until 1527 CST on 02/02/00. This |
| resulted in 2 trains of Essential Chilled Water being inoperable for 4 hours |
| and 6 minutes which placed the plant in Technical Specification 3.0.3 (did |
| not require plant shutdown). |
| |
| A Licensee Event Report will be submitted within 30 days. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36664 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 02/05/2000|
| UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 15:06[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 02/05/2000|
+------------------------------------------------+EVENT TIME: 13:06[CST]|
| NRC NOTIFIED BY: TOM MOSBY |LAST UPDATE DATE: 02/06/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLAUDE JOHNSON R4 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOSEPH GIITTER IRO |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION 3.0.3 ENTERED AT 1306 CST DUE TO BOTH TRAINS OF LOW |
| PRESSURE INJECTION/RESIDUAL HEAT REMOVAL (LPI/RHR) DECLARED INOPERABLE. |
| |
| "At 1306 on 02/05/00, both Low Pressure Injection/Decay Heat Removal Pumps |
| (P-34A and B) were declared inoperable and Technical Specification 3.0.3 |
| was entered. The pumps were declared inoperable after the inboard pump |
| bearing temperatures exceeded their alarm setpoint after being placed in |
| service for decay heat removal for normal cooldown. |
| |
| "Unit 1 was taken offline at 0010 on 02/05/00 for scheduled maintenance. |
| The unit was in the process of cooling down at the time Tech Spec 3.0.3 was |
| entered. Decay heat removal is being maintained with the use of the |
| operable "B" Reactor Coolant System Loop." |
| |
| Low Pressure Injection pump "A" was placed in service at 1206 CST and a high |
| temperature alarm for the inboard pump bearing was received. Later Low |
| Pressure Injection pump "B" was placed in service and a high temperature |
| alarm for the pump inboard bearing was also received at which time Tech Spec |
| 3.0.3 was entered. The outboard bearing temperatures for both Low Pressure |
| Injection pumps were below their high temperature alarm setpoint. The Low |
| Pressure Injection pumps inboard and outboard bearing are cooled by the |
| Service Water system. Reactor Coolant System pressure is currently 262 psig |
| and plant temperature is 263 degrees F. The licensee said that as far as he |
| knew the Service Water system was properly aligned for cooling both the |
| inboard and outboard bearings of the Low Pressure Injection pumps. Reactor |
| Coolant System Loop "A" is also fully operable if needed. All other |
| Emergency Core Cooling Systems are operable. The licensee is investigating |
| the cause of the high inboard bearing temperatures. |
| |
| The NRC Resident Inspector will notified of this event by the licensee. |
| |
| * * * UPDATE AT 1730 HOURS ON 02/05/00 BY MOSBY TAKEN BY MACKINNON * * * |
| |
| LICENSEE UPDATED EVENT AS A 4 HOUR CALL UNDER 10 CFR 50.72 (b)(2)(I) - |
| DEGRADED WHILE SHUTDOWN. |
| |
| "When P-34A was initially placed in service, the inboard bearing temperature |
| reached the alarm setpoint of 160 degrees F at which time the pump was |
| secured. Currently, P-34A is aligned to recirculate the Borated Water |
| Storage Tank (BWST) and is in operation with the temperature of the pump |
| inboard bearing steady at 84.5 degrees F. Engineering, Operation and |
| Predictive Maintenance are currently involved with the continued testing of |
| the pump. The testing and subsequent operability assessment will be |
| concluded prior to placing the pump in service for decay heat removal." |
| R4DO (C. Johnson) notified. |
| |
| The NRC Resident Inspector was notified of this event update by the |
| licensee. |
| |
| * * * UPDATE AT 1040 ON 02/06/00 BY SCHEIDE TAKEN BY WEAVER * * * |
| |
| The licensee has retracted this event notification based on the following |
| discussion. Technical Specifications require LPI to be operable when three |
| conditions are exist. 1. Fuel in the reactor vessel. 2. Reactor coolant |
| temperature above 200 degrees F and 3. Primary system pressure > 300 psig. |
| A subsequent review of the event verified that RCS pressure was at 240 psig |
| at the time of the event. Therefore, LPI was not required to be operable |
| and 3.0.3 was not applicable. Conditions for decay heat removal were |
| satisfied since both reactor coolant loops and associated OTSGs remained |
| operable. |
| |
| The licensee will notify the NRC resident inspector. The operations center |
| notified the RDO (Johnson). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36665 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 02/06/2000|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 18:37[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/06/2000|
+------------------------------------------------+EVENT TIME: 17:55[EST]|
| NRC NOTIFIED BY: BRUCE BUTLER |LAST UPDATE DATE: 02/06/2000|
| 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 93 Power Operation |93 Power Operation |
|2 N Y 98 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PUBLIC PROMPT NOTIFICATION SYSTEM INOPERABLE FOR 2 MINUTES |
| |
| Due to technical difficulties in Jacksonville, Florida, the Public Prompt |
| Notification System (NOAA weather radio) was lost at 1755 ET and was |
| restored to service at 1757 ET. Primary and backup system were inoperable |
| during this period of time. |
| |
| The NRC Resident will be notified of this event notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36666 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 02/07/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 03:11[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 02/07/2000|
+------------------------------------------------+EVENT TIME: 00:55[CST]|
| NRC NOTIFIED BY: KEVIN PEDERSON |LAST UPDATE DATE: 02/07/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY VEGEL R3 |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ESF ACTUATION - RECIRC SAMPLE ISOLATION VALVES |
| |
| During the performance of standby liquid control refueling tests, a signal |
| is sent to the reactor water cleanup isolation valves and the recirc sample |
| valves. The procedure addresses the RWCU valves, but not the recirc sample |
| valves. Since the outboard sample valve was secured (tagged) open, it |
| unexpectedly closed upon initiation of the standby liquid control system. |
| |
| The valves were returned to their pre-test positions. |
| |
| The licensee will notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36667 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/07/2000|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 04:28[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/07/2000|
+------------------------------------------------+EVENT TIME: 02:40[CST]|
| NRC NOTIFIED BY: DAVE KLIMECK |LAST UPDATE DATE: 02/07/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY VEGEL R3 |
|10 CFR SECTION: | |
|DDDD 73.71 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Minimum security personnel staffing requirements not met. Immediate |
| compensatory actions taken upon discovery. The licensee will notify the |
| NRC resident inspector. Additional details of this event may be obtained by |
| contacting the NRC operations officer. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021