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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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39205       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39206       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39207       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
|  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.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39208       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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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