Event Notification Report for March 5, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/04/2002 - 03/05/2002
** EVENT NUMBERS **
38477 38704 38748 38749
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38477 |
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| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/07/2001|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 19:47[EST]|
| RXTYPE: [1] CE |EVENT DATE: 11/07/2001|
+------------------------------------------------+EVENT TIME: 14:14[EST]|
| NRC NOTIFIED BY: DANIEL G. MALONE |LAST UPDATE DATE: 03/04/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R3 IRC TEAM MANAGER R3 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| HEAD LOSS CHARACTERISTICS OF CHECK VALVES GREATER THAN PREVIOUSLY
ASSUMED. |
| |
| On November 7, 2001, at approximately 1414 hours, with the plant in mode 5 |
| (cold shutdown), evaluation of preliminary results from mock-up testing of |
| containment sump check valves determined that the head loss characteristics |
| of the check valves are greater than previously assumed by calculations that |
| support the safety analyses. The result of increased head loss through the |
| containment sump check valves is reduced available net positive suction head |
| (NPSH) for the safety injection and containment spray pumps during |
| recirculation mode following a loss of coolant accident (LOCA). The reduced |
| available NPSH may have effected the ability of the pumps to satisfy their |
| required design safety function during previous periods of plant operation. |
| Recirculation mode operation of these pumps is required by Technical |
| Specifications in Mode 3 (hot standby) and above. Therefore, this condition |
| has no adverse implications for the present plant condition at Mode 5. |
| Evaluation of test results is continuing. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1450 EST ON 03/04/02 BY DAN MALONE TO GERRY WAIG* * * |
| |
| "Subsequent evaluation of the past operability of the pumps with the reduced |
| NPSH condition was concluded that the pumps were nonconforming but operable. |
| This conclusion was reached by crediting containment overpressure and actual |
| plant parameters, which increase available NPSH above that required for all |
| pumps considering the most limiting postulated conditions. |
| |
| "Since a determination of nonconforming but operable was reached for past |
| operating conditions, there was no loss of a required safety function and no |
| significant impact on plant safety this condition was originally discovered |
| and reported with the plant in Mode 5; and was corrected prior to plant |
| restart by modifying plant equipment and procedures without further reliance |
| on crediting containment overpressure." |
| |
| Licensee notified the NRC Resident Inspector. Notified R3DO (John Madera). |
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|Fuel Cycle Facility |Event Number: 38704 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/16/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:11[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/15/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:00[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/04/2002|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |ANTON VEGEL R3 |
| DOCKET: 0707001 |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KEVIN BEASLEY | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2) SAFETY EQUIPMENT FAILUR| |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| SAFETY EQUIPMENT FAILURE - PROCESS GAS LEAK DETECTION FAILURE |
| |
| "At 2200 CST, on 02-15-02 the Plant Shift Superintendent (PSS) was notified |
| of a failure of the Process Gas Leak Detector (PGLD) system in the C-333 |
| building. During above atmospheric operation a PGLD alarm was received in |
| the Area Control Room [ACR] on C-333 Unit 4 Cell 4. An operator responded |
| to the local cell panel to investigate according to the alarm response |
| procedure. Upon arriving at the cell panel the operator discovered that the |
| Ready light was not Illuminated on the PGLD panel. At this time the |
| operator attempted to test fire the PGLD system, however the system would |
| not respond. The Front Line Mgr. and the PSS were immediately notified of |
| the system failure. At this time, required TSR 2.4.4.1 LCO continuous smoke |
| watches were put in place in the affected areas until repair of the system |
| was completed. Following replacement of the power supply by Instrument |
| Maintenance and testing by Operations, ten Unit 4 Cell 4 PGLD system was |
| declared operable by the PSS at 2340 CST. At this time the TSR required |
| smoke watches were discontinued. |
| |
| "The PGLD system is designed to detect the leakage of process gas from the |
| process system and is required to be operable while operating in Cascade |
| Mode 2 (Above Atmospheric Pressure). Due to the failure of this TSR |
| required system; the PSS has determined that this is reportable as a 24 hour |
| Event Report. |
| |
| "The NRC Resident inspector has been notified of this event." |
| |
| * * * RETRACTED AT 0346 EST ON 02/22/02 BY ERIC WALKER TO FANGIE JONES * * * |
| |
| |
| "This event has been retracted. Even though the power loss causes the system |
| to be incapable of annunciating additional alarms from this system in the |
| ACR, the same is true when a PGLD head actuates in response to smoke. The |
| system Is designed to alert operators of a release or loss of system power. |
| Operator response and the initiation of a smoke watch provide the safety |
| function after the initial alarm is annunciated. The NRC resident inspector |
| has been notified of this update." |
| |
| The R3DO (Bruce Jorgensen) and NMSS EO (E. William Brach) have been |
| notified. |
| |
| * * * UPDATED AT 1750 EST ON 3/4/02 BY TOM WHITE TO FANGIE JONES * * * |
| |
| "Following discussions with NRC Region III and the PGDP NRC Senior Resident |
| Inspector. USEC has determined that a rescission of the retraction made on |
| 2/21/02 will be necessary in response to NRC concerns related to this |
| matter. Therefore, USEC hereby rescinds the subject retraction and will be |
| submitting the written report required by 10CFR76.120(d)(2). The NRC Senior |
| Resident Inspector has been notified of the rescission." |
| |
| Notified the R3DO (John Madera) and NMSS EO (C. W. Reamer). |
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|Power Reactor |Event Number: 38748 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/04/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 10:13[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/04/2002|
+------------------------------------------------+EVENT TIME: 08:41[EST]|
| NRC NOTIFIED BY: PHILLIP THOMPSON |LAST UPDATE DATE: 03/04/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER |
| |
| "Manual reactor trip due to falling level in 1A Steam Generator (S/G), (RPS |
| Activation). Level decrease occurred after the Feedwater Regulating Valve |
| (FRV) for the 1A S/G failed closed upon loss of the normal and backup |
| electrical power to the valve solenoid. After the reactor trip, the 1A S/G |
| experienced a LO-LO Level Alarm which auto started both motor driven |
| Auxiliary Feedwater pumps, (ESF Actuation). All S/G levels are now at |
| normal levels and Unit 1 is stable. An investigation is in progress to |
| determine the loss of electrical power to the FRV solenoid for the 1A S/G." |
| |
| The plant is dumping steam to the Main Condenser with no known |
| Primary/Secondary leakage. There was no actuation of primary safety valves. |
| All safety systems are operable and normal electrical distribution is |
| available. |
| |
| The NRC Resident Inspector has been notified. |
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|Power Reactor |Event Number: 38749 |
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| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/04/2002|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 11:37[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/04/2002|
+------------------------------------------------+EVENT TIME: [CST]|
| NRC NOTIFIED BY: RICK ROBBINS |LAST UPDATE DATE: 03/04/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |JOHN MADERA R3 |
|10 CFR SECTION: |CHRIS GRIMES EO |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |RICHARD WESSMAN IRO |
| |JEFF GRANT R3 |
| |REGION V OSC EPA |
| |BELCHER FEMA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| UNUSUAL EVENT DUE TO UNCONTROLLED FLAMMABLE GAS LEAK ONSITE |
| |
| At 0946 CST, 3/4/02, an Unusual Event was declared due to a non isolable |
| leak on a propane tank. The tank is approximately 500 to 750 gals, and is |
| 55 % full. The tank is leaking at the rate of 5% decrease every 20 minutes. |
| The tank is 25 to 30 yards out in the Owner Controlled Area and a local |
| area evacuation has been performed. The Two Creek Fire Department is on the |
| scene. |
| |
| NRC Resident Inspector has been notified. |
| |
| At 1147 EST, NRC entered Monitoring for Normal Phase Mode. |
| |
| ***EVENT UPDATED AT 1309 EST ON 3/4/02 BY MARK HANSON TO FANGIE JONES*** |
| |
| At 1154 CST, Licensee terminated Unusual Event due to leak isolated. |
| |
| At 1310 EST, NRC exited monitoring for the Unusual Event. |
| |
| Notified IRO (Holonich), R3DO (Madera), NRR (Grimes), PAO (Dricks), FEMA |
| (Snyder). |
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