Event Notification Report for September 23, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/20/2002 - 09/23/2002
** EVENT NUMBERS **
39194 39202 39205 39206 39207 39208
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|General Information or Other |Event Number: 39194 |
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| REP ORG: ILLINOIS DEPT OF NUCLEAR SAFETY |NOTIFICATION DATE: 09/17/2002|
|LICENSEE: ILLINOIS ROOF CONSULTING ASSOC. INC |NOTIFICATION TIME: 10:25[EDT]|
| CITY: CHICAGO REGION: 3 |EVENT DATE: 09/16/2002|
| COUNTY: STATE: IL |EVENT TIME: 14:35[CDT]|
|LICENSE#: IL-01713-01 AGREEMENT: Y |LAST UPDATE DATE: 09/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANNE MARIE STONE R3 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STEVE COLLINS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN TROXLER MODEL 3216 GAUGE |
| |
| During the afternoon of September 16, 2002, a roof moisture gauge in its |
| locked case was stolen from a locked van belonging to an Illinois |
| Radioactive Material Licensee--IL Roof Consulting Associates, Inc. with |
| license IL-01713-01. The Radiation Safety Officer (RSO) reported the |
| break-in and theft to the IDNS and the Chicago Police within an hour of the |
| theft. The gauge was a Troxler Model 3216, Serial Number 00173 with 40 |
| millicuries of americium-241and was used for roofing moisture measurements. |
| The van was parked in front of a Chicago public school while two workers |
| were on the roof of the school--Leif Ericson Scholastic Academy--at 3600 W. |
| 5th Avenue, Chicago. Near the end of the job the RSO had joined the two |
| workers and then discovered the theft that occurred approximately 1435 as he |
| was returning to the van with a second gauge that had been in use. The |
| windows of the van were tinted to reduce visibility except for the drivers |
| side window. |
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|Power Reactor |Event Number: 39202 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/20/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 04:12[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/20/2002|
+------------------------------------------------+EVENT TIME: 01:12[EDT]|
| NRC NOTIFIED BY: TIM JOHNSON |LAST UPDATE DATE: 09/20/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|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 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| INADVERTENT ACTUATION OF BLACKOUT SIGNAL ON UNIT 1 DURING SURVEILLANCE |
| TESTING |
| |
| "Inadvertent Actuation of B Train Blackout Signal on Unit 1. Actuation |
| occurred during testing of the 1B Diesel Generator sequence panel. The |
| actuation caused the B Train Nuclear Service Water System to realign to the |
| standby Nuclear Service Water Pond on both Unit 1 and Unit 2. Unit 2 was not |
| affected due to the realignment. The Unit 1 Boric Acid pump transfer pump |
| automatically secured and various containment and Auxiliary Building |
| Ventilation components were affected due to the actuation. The procedure |
| used for testing the sequencer simulated an undervoltage signal on the B |
| Train Emergency Bus. Plans are being evaluated to restore the sequencer from |
| the test alignment and realign all affected equipment." |
| |
| Neither reactor residual heat removal cooling or spent fuel pool cooling |
| were affected by this event. Electrical buses remained energized and no EDG |
| autostart occurred since the blackout signal was simulated and not based on |
| an actual undervoltage condition. The licensee is attributing the cause |
| preliminarily to an inadequate procedure. |
| |
| The licensee will notify the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39205 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/20/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 16:30[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/20/2002|
+------------------------------------------------+EVENT TIME: 10:02[EDT]|
| NRC NOTIFIED BY: BOB LANCE |LAST UPDATE DATE: 09/20/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN KINNEMAN R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| HPCI INOPERABLE DUE TO PRESSURE AND SPEED FLUCTUATIONS |
| |
| "On 9/20/02 at 10:02 AM EDT, the Unit 1 HPCI system was declared inoperable |
| due to observation of speed and pressure fluctuations while operating in the |
| manual mode. HPCI was being run for the quarterly surveillance test. Site |
| engineering is currently troubleshooting. This report is being made pursuant |
| to 10CFR50.72(b)(3)(v)(D) for failure of a single train accident mitigation |
| system." |
| |
| The NRC resident inspector was notified. |
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|Power Reactor |Event Number: 39206 |
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| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 09/21/2002|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 15:40[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/21/2002|
+------------------------------------------------+EVENT TIME: 11:00[EDT]|
| NRC NOTIFIED BY: JOHN RODEN |LAST UPDATE DATE: 09/21/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|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 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| PARTIAL LOSS OF OFFSITE POWER CAUSED EDG START AND AFW PUMP START |
| |
| "While operating at 100% power on September 21, 2002, Watts Bar Unit 1 |
| experienced a momentary loss of the 161kV offsite power feed to Common |
| Station Service Transformer (CSST) D. WBN's two offsite power supplies are |
| fed from a remote switchyard located at the Watts Bar hydro electric plant. |
| The one affected offsite power source and the CSST D are the primary power |
| sources for 6900V Shutdown Boards 1B-B and 2B-B, The partial loss of offsite |
| power was caused by the inadvertent manual operation of a breaker at the |
| hydro electric plant switchyard. The opening of the breaker occurred at |
| 11:00:20 (EDT) and the breaker was reset to provide offsite power at |
| 11:00:34 (EDT). Due to this event, and the loss of the primary feed to the |
| shutdown boards, a valid engineered safety function (ESF) actuation occurred |
| which started all four of the standby diesel generators (DGs), along with, |
| as designed, the 1B-B Motor Driven Auxiliary Feedwater (AFW) Pump and the |
| Turbine Driven AFW Pump. The DGs provided power to the affected Shutdown |
| Boards and other required blackout loads during the event. All components at |
| the hydro plant were restored to their normal configuration at 11:44 (EDT). |
| Affected Plant components are currently being restored to normal |
| configurations." |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 39207 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/22/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 03:19[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/22/2002|
+------------------------------------------------+EVENT TIME: 01:46[EDT]|
| NRC NOTIFIED BY: ALAN RABENOLD |LAST UPDATE DATE: 09/22/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK RING R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 90 Power Operation |0 Hot Shutdown |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DURING MAIN TURBINE TRIP TESTING |
| |
| "At 0146, Reactor Scram occurred when the Main Turbine Tripped during the |
| weekly testing of the Main Turbine Protection Devices Trip Test Instruction. |
| The tripping of the Main Turbine caused a Turbine Control Valve Fast Closure |
| Scram. All rods inserted. Reactor Level dropped below Level 3 due to the |
| Scram. The Main Feed System restored level above Level 3, following the |
| Scram. No Safety Related Injection Systems were required to maintain |
| Reactor Level. Currently the Reactor is being maintained in Hot Stby Mode 3 |
| with RPV Pressure at 900 PSIG and RPV level at 196 [inches] with the Feed |
| System. |
| |
| "The Main Turbine Protection Device Trip Test did not function properly and |
| caused the Main Turbine to trip. A team is being formed to determine why |
| the trip lockout test failed to prevent a Main Turbine Trip." |
| |
| Decay heat is being rejected to the Main Condenser. Plant electrical loads |
| transferred to the Startup Transformer as required. |
| |
| The licensee will inform the NRC Resident Inspector. |
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|Fuel Cycle Facility |Event Number: 39208 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/23/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:08[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/22/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:42[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/23/2002|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MARK RING R3 |
| DOCKET: 0707001 |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: K.A. BEASLEY | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
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EVENT TEXT
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| 24 HOUR REPORT INVOLVING A VALID ACTUATION OF A "Q" SAFETY SYSTEM DUE TO A |
| UF6 RELEASE |
| |
| "At 1642, on 9-22-02 the Plant Shift Superintendent (PSS) was notified of an |
| activation of a Q safety system in the C-333 process building. Operations |
| personnel reported receiving a Process Gas Leak Detection (PGLD) alarm at |
| Unit 5 Cell 9. The operators responded to the area according to their |
| emergency response procedure and reported that a haze was visible in the |
| area. Building personnel then reported that multiple PGLD alarms were |
| received from other cells in the area. The location of the PGLD detectors |
| that were alarming indicated that the UF6 release was located at the Unit 5 |
| cell bypass housing. All cells in Unit 5 were shutdown to reduce the process |
| pressure to below atmosphere. Following shutdown of the equipment, air |
| sampling in multiple locations through out the building were obtained by the |
| plant emergency squad. After it was determined that all air samples showed |
| no indication of an ongoing release, an all clear on the emergency was given |
| by the PSS. Trouble shooting by building personnel is in progress to |
| determine the location of the system breach. |
| |
| "The PSS determined that this event is a 24 Hour Event Report due to the |
| valid activation of a TSR required Q safety system. |
| |
| "The NRC Resident inspector has been notified of this event." |
| |
| The duration of the release was estimated as approximately 10 minutes. |
| Urine samples for four (4) maintenance personnel and ten (10) operators |
| working in the area will be processed as a precautionary measure. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021