Event Notification Report for August 3, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/02/2001 - 08/03/2001
** EVENT NUMBERS **
38179 38180 38181 38182 38183
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|Power Reactor |Event Number: 38179 |
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/01/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 09:05[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/01/2001|
+------------------------------------------------+EVENT TIME: 07:01[CDT]|
| NRC NOTIFIED BY: BRUCE ANDERSON |LAST UPDATE DATE: 08/02/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PATRICK HILAND R3 |
|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 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO NEGATIVE FLUX RATE |
| |
| The unit automatically tripped from 100%; the first out annunciator was Flux |
| Rate Reactor Trip. Immediately following the trip, the rod position |
| indicator showed that five control rods did not insert completely. The stuck |
| control rods indicated 15-20 steps out from bottom. Operators entered their |
| reactor trip/safety injection emergency procedure (1E0), but were able to |
| transition to the trip recovery procedure (1ES0.1). One of the stuck control |
| rods subsequently indicated full insertion. The unit is currently stable in |
| Mode 3. Operators are emergency borating the reactor per 1ES0.1 a total of |
| 1000 gallons (250 gallons per stuck rod). The licensee is continuing their |
| trip recovery. Preliminary investigation indicates a problem with the rod |
| control system may have led to one or more dropped control rods. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE 1025 EDT 8/1/01 FROM DAMMANN TAKEN BY JONES * * * |
| |
| The licensee reported that the auxiliary feedwater (AFW) system (pumps 11 |
| and 12) automatically actuated on steam generator low-low level following |
| the trip, as expected. In addition, two of the stuck rods are now |
| indicating full insertion. The NRC resident inspector has been informed of |
| this update. |
| |
| * * * UPDATE 1624 EDT 08/01/01 FROM GOSMAN TAKEN BY MACKINNON * * * |
| |
| After interviewing the Reactor Operators it was determined that 6 rod bottom |
| lights did not immediately come on after the reactor trip. Also a media |
| press release will be made concerning this event. R3DO (John Madera) |
| notified. |
| |
| The NRC resident inspector was notified of this update by the licensee. |
| |
| * * * UPDATE 0431 EDT 8/2/01 FROM IRVIN TAKEN BY STRANSKY * * * |
| |
| "Investigation into the cause of the reactor trip has determined that |
| control rods associated with Rod Control Power Cabinet 2AC began to insert |
| into the core. As designed, the reactor protection system actuated to insert |
| the remaining control rods. |
| |
| "In accordance with procedures, operators verified the reactor had safely |
| shutdown. However, indicator lights for six of twenty-nine individual |
| control rods did not indicate that the rods had fully inserted. This |
| situation is addressed in the reactor trip procedure and the operators |
| responded appropriately by borating to compensate. |
| |
| "Control rod drop testing has been performed and has verified that all |
| control rods fully inserted. Individual rod position indication calibration |
| check is in progress." |
| |
| The NRC resident inspector will be informed of this update by the licensee. |
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|Other Nuclear Material |Event Number: 38180 |
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| REP ORG: NTH CONSULTANTS |NOTIFICATION DATE: 08/02/2001|
|LICENSEE: NTH CONSULTANTS |NOTIFICATION TIME: 08:49[EDT]|
| CITY: FARMINGTON HILLS REGION: 3 |EVENT DATE: 08/02/2001|
| COUNTY: STATE: MI |EVENT TIME: 07:50[EDT]|
|LICENSE#: 21-14894-01 AGREEMENT: N |LAST UPDATE DATE: 08/02/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN MADERA R3 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM CARSONS | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN TROXLER MOISTURE DENSITY GAUGE |
| |
| The licensee reported a missing (presumed stolen) Troxler moisture density |
| gauge, model #3401 serial #14236. The gauge was discovered missing from the |
| bed of a pickup where it had been locked in its case and the case cabled to |
| the truck. The gauge contains 2 sources, one of approximately 8 mCi Cs-137 |
| and the other 40 mCi Am-241:Be. The licensee intends to make a police |
| report and is retracing the trucks route from the work site back to the |
| driver's home located in Farmington Hills, MI. |
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|Power Reactor |Event Number: 38181 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 08/02/2001|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 10:07[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 08/02/2001|
+------------------------------------------------+EVENT TIME: 08:23[CDT]|
| NRC NOTIFIED BY: TOM OSELAND |LAST UPDATE DATE: 08/02/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |JOHN MADERA R3 |
|10 CFR SECTION: |PAT MADDEN NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH HOLONICH IRO |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|MARK RING R3 |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT|JAMES DYER R3 |
| |STEINDURF FEMA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER FOLLOWING LIGHTNING |
| STRIKE |
| |
| At 0823 CDT, the licensee declared an Unusual Event due to a lightning |
| strike on or near the Unit 2 main transformer which caused a fire in the |
| transformer and a loss of offsite power to the unit. Both emergency diesel |
| generators (the Unit 2 and swing EDGs) started and loaded. An automatic |
| reactor scram occurred and all control rods inserted following the scram. |
| The unit is currently in Hot Shutdown with decay heat being removed via the |
| safety/relief valves and reactor vessel water level control being maintained |
| using the safe shutdown makeup pump and the reactor core isolation cooling |
| (RCIC) system. |
| |
| Offsite firefighting assistance was requested to combat the fire, which has |
| since been extinguished. The licensee is currently in the process of |
| restoring offsite power to the unit. The electrical transient did not |
| significantly affect the operation of Unit 1. |
| |
| The NRC resident inspector has been informed by the licensee. |
| |
| HOO NOTE: The NRC senior resident inspector notified the NRC Operations |
| Center of this event at 0933 EDT. The agency entered the monitoring phase of |
| normal mode at 1003 EDT. |
| |
| * * * UPDATE 1220EDT ON 8/2/01 FROM FOSTER (REGION 3 IRC) TO S. SANDIN * * |
| * |
| |
| Region 3 has secured from Monitoring at 1120CDT based on current plant |
| conditions and the licensee's on-going restoration of offsite power. |
| Notified IRO(Holonich). |
| |
| * * * UPDATE 1253EDT ON 8/2/01 FROM CHRISSOTIMOS TO S. SANDIN * * * |
| |
| Unit 2 exited the Unusual Event at 1147CDT. The following information was |
| provided via fax: |
| |
| "The Unit 2 and 1/2 [Swing] Emergency Diesel Generators Auto Started on the |
| ESF signal. Group II and III isolations were received as expected. Local |
| Fire Department assisted in fire activities and extinguished transformer |
| fire. RCIC and the Safe Shutdown Makeup Pump were manually initiated to |
| provide level control. Relief valves were manually operated to control |
| pressure. At 1048 CDT Transformer 22 power was restored and is providing |
| loads to Unit 2. Both EDG's have been shutdown. The Illinois Emergency |
| Management Agency has been notified of the Hazmat spill from the transformer |
| fire. |
| |
| "A courtesy call was also made to the National Response Center for a |
| potential of a Hazmat spill into the Mississippi River [NRC Incident Report |
| # 575186]. |
| |
| "The Unusual Event was terminated at 1147 CDT." |
| |
| The licensee is in the process of informing state/local agencies and has |
| informed the NRC resident inspector. Notified R3DO(Madera), EO(Madden), |
| IRO(Holonich), EDO(Bergman) and FEMA(Caldwell). |
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|Fuel Cycle Facility |Event Number: 38182 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/02/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:10[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/02/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:38[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/02/2001|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA R3 |
| DOCKET: 0707001 |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: M. C. PITTMAN | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 24-HOUR REPORT INVOLVING A SAFETY SYSTEM ACTUATION DUE TO A VALID SIGNAL |
| |
| "At 1250 on 08/02/01, the PSS office was notified that a High Autoclave |
| Steam Pressure alarm was received on the C-337A autoclave position 2 west |
| Autoclave Steam Pressure Control System (SPCS). The SPCS system is required |
| to be operable while feeding in mode 5 according to TSR 2.2.3.3. The |
| autoclave was in Mode 5 at the time of the actuation. The indications were |
| checked according to the alarm response procedure and the alarm was |
| determined to be a valid signal. The autoclave was removed from service and |
| the Steam Pressure Control System was declared inoperable by the Plant Shift |
| Superintendent. |
| |
| "This safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report, section 6.9, table 1, criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification. |
| |
| "The NRC Senior Resident Inspector has been notified of this event." |
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|Power Reactor |Event Number: 38183 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/02/2001|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 19:17[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/02/2001|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: TIM RIEGER |LAST UPDATE DATE: 08/02/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 |
|10 CFR SECTION: |HERB BERKOW NRR |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| UNANALYZED CONDITION INVOLVING SEISMIC EVENT DISCOVERED DURING ENGINEERING |
| REVIEW |
| |
| "On August 2, 2001, at approximately 1500 hours, Engineering notified |
| operations that the Service Water (SW) System may not meet analyzed flow |
| requirements after a seismic event as a result of a system re-alignment |
| change implemented June 4, 2001. The SWS re-alignment change placed an 8 |
| inch non-seismic SW line on the essential SW header. The SWS was originally |
| analyzed for a seismic event with the break of a 10 inch non-seismic SW |
| line. The change evaluation concluded that this configuration was bounding |
| for the alignment. The assessment of the alignment change did not adequately |
| consider the effects of the seismic event. After a review of the change, |
| Engineering judged that the SWS would not meet system design flow |
| requirement after a seismic event with two out of three pumps due to the |
| failure of both non-seismic lines that were aligned as a result of the |
| change. Operations initiated realignment of the 8 inch SW line back to the |
| non-essential header which was completed at 1640 hours. Engineering is |
| performing evaluations but judged that the SWS would have met flow |
| requirements for plant shutdown with three SW pumps operable after a seismic |
| event with no random single failure (three pumps operable)." |
| |
| The licensee will inform the NRC resident inspector. |
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