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Event Notification Report for December 15, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/14/2000 - 12/15/2000

                              ** EVENT NUMBERS **

37552  37594  37595  37596  37597  37598  37599  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37552       |
+------------------------------------------------------------------------------+
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| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 11/26/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 06:13[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/26/2000|
+------------------------------------------------+EVENT TIME:        01:54[CST]|
| NRC NOTIFIED BY:  WILLIAM GREEN                |LAST UPDATE DATE:  12/14/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF LOOSE SERVICE WATER PUMP FOUNDATION BOLTS                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0154 [CST] on 11/26/00, a station operator noticed that 2 foundation     |
| bolts on service water pump (SWP) C were loose and 3 foundation bolts on     |
| [SWP] D were loose.  Both service water loops were declared inoperable, and  |
| [limiting condition for operation (LCO)] 3.7.2, condition A, was entered     |
| twice and condition B once.  This required placing the plant in Mode 3       |
| within 12 hours and Mode 4 within 36 hours.  Personnel were called to the    |
| site, and all foundation bolts on all 4 [SWPs] were torqued.  No loose bolts |
| were found on SWP A, 4 loose bolts were found on SWP B, and 5 loose bolts    |
| were found on SWPs C [and] D.  An operability determination was written to   |
| justify operability of the service water system, and all LCOs were exited at |
| 0428 [CST].  Engineering [personnel are] evaluation the condition."          |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTED AT 1244 EST ON 12/14/00 BY STEVEN JOBE TO FANGIE JONES * *   |
| *                                                                            |
|                                                                              |
| "Subsequent evaluation has determined that all Service Water Pumps were      |
| operable at all times and this event is not reportable under either 10 CFR   |
| 50.72(b)(2)(iii)(B) or 10 CFR 50.72(b)(2)(iii)(D).                           |
|                                                                              |
| "Engineering evaluation has determined that a Service Water Pump is operable |
| with one or more pedestal nuts (foundation bolts) having less than           |
| installation torque provided a minimum finger tight torque exists. That      |
| justification is based on evaluation of loading stress and the impact of not |
| having a preload stress applied to the nut. The determination is that the    |
| finger tight nut is an acceptable condition for pump operability. This       |
| evaluation has considered the effects of various loading conditions          |
| including seismic, barge impact and normal operational loads."               |
|                                                                              |
| The licensee has notified the NRC Resident Inspector.  The R4DO (Chuck Cain) |
| has been notified.                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37594       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 12/14/2000|
|    UNIT:  [] [2] []                 STATE:  WI |NOTIFICATION TIME: 08:40[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        06:30[CST]|
| NRC NOTIFIED BY:  R. HASTINGS                  |LAST UPDATE DATE:  12/14/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       0        Startup          |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO A BLOWN CONTROL POWER FUSE ON AN INTERMEDIATE  |
| RANGE NEUTRON DETECTOR                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The Unit 2] reactor automatically tripped at 0630 [CST] due to a blown     |
| control power fuse on intermediate range neutron detector 2N35.  Reactor     |
| power at the time of the trip was in the source range [10E+4] cps, well      |
| below the actual intermediate range trip setpoint.  [Unit 2] is exiting a    |
| refueling outage, the reactor was made critical at 0543 [CST].               |
| Troubleshooting is in progress.  The heat removal mechanism is steam dump    |
| discharge from the steam generator atmospheric relief valves.  There are no  |
| known steam generator tube leaks."                                           |
|                                                                              |
| The licensee stated that auxiliary feedwater was supplying water to the      |
| steam generators both before and after the trip.  The unit is currently      |
| stable in Mode 3.  Pressurizer heaters and sprays, normal charging and       |
| letdown, and the reactor coolant pumps are being utilized for primary system |
| pressure, inventory, and transport control.  Containment parameters are      |
| normal, and offsite power is available.  There were no engineered safety     |
| actuations or emergency core cooling system actuations, and none were        |
| required.  The licensee stated that all systems functioned as required and   |
| that there was nothing unusual or misunderstood.  There were no related      |
| maintenance activities ongoing at the time if the trip.                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37595       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 12/14/2000|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 14:15[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        11:50[CST]|
| NRC NOTIFIED BY:  LARRY McLERRAN               |LAST UPDATE DATE:  12/14/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHUCK CAIN           R4      |
|10 CFR SECTION:                                 |FEMA,DOE,DOA         FAX     |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |HHS,EPA,DOT          FAX     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       60       Power Operation  |60       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO THE U.S. COAST GUARD ABOUT A FUEL OIL SPILL          |
|                                                                              |
| The licensee notified the U.S. Coast Guard of a spill of less than 5 gallons |
| of diesel fuel oil released to the discharge canal.  Absorbent booms are     |
| deployed across the discharge canal and in the storm drain discharge to the  |
| canal.                                                                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector and will notify the state   |
| of Arkansas.                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37596       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 12/14/2000|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 18:02[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        17:15[EST]|
| NRC NOTIFIED BY:  DAVID DVORAK                 |LAST UPDATE DATE:  12/14/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LOCATION OF 2 FUEL PINS IN THE SPENT FUEL POOL IS UNKNOWN                |
|                                                                              |
| "As part of the ongoing decommissioning of Millstone Unit 1, a detailed      |
| documentation of the fuel currently in the Unit 1 spent fuel pool is         |
| underway. A detailed verification of spent fuel pool content records was     |
| part of this effort. During this process, workers identified a discrepancy   |
| in the paperwork relating to the location of two spent fuel pins that were   |
| removed from a fuel assembly in October 1972. A search is underway; however, |
| these fuel pins have not yet been located among the 2,884 fuel assemblies    |
| containing more than 140,000 fuel pins currently in the spent fuel pool. In  |
| addition, workers are also searching pertinent records.                      |
|                                                                              |
| "Due to the radiation levels of the fuel pins, if they were removed from the |
| spent fuel pool, the use of a shielded cask would have been required and the |
| shipment could have only been made to a licensed facility. Any other         |
| movement of these pins from the site would have been immediately detected by |
| the site radiation monitoring system. Therefore, there is a high degree of   |
| confidence that these pins are not in an unrestricted area and are under the |
| control of a licensed facility; either here in the spent fuel pool or        |
| possibly at a licensed radioactive waste disposal site. As a result, we are  |
| also confident that no overexposure of workers or members of the public has  |
| resulted. An independent team with relevant expertise is on-site to assist   |
| in an ongoing investigation to determine the location of the 2 fuel pins."   |
|                                                                              |
| The licensee notified NRC Region 1 (Todd Jackson) and the state of           |
| Connecticut.  The licensee intends notifying the NRC Resident Inspector.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37597       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 12/14/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 18:33[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        06:00[CST]|
| NRC NOTIFIED BY:  DAVID BRAGLIA                |LAST UPDATE DATE:  12/14/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OVERPOWER CONDITION DUE TO FEED TEMPERATURE CALCULATION ERROR                |
|                                                                              |
| "Braidwood Station Operating License condition 2.C.1 restricts licensed      |
| thermal power level to 3411 MW thermal. From December 13, 2000 at 0410 to    |
| December 14, 2000 at 0600, Braidwood Unit 2 was operated at a power level of |
| 100.55 percent in violation of this license condition.                       |
|                                                                              |
| "On December 14, 2000 at 0600 the station Thermal Performance Engineer       |
| discovered that Feedwater inlet temperature was not being calculated         |
| correctly by the plant process computer. Following a transfer of computer    |
| room ventilation trains on December 12, 2000 at 1800 feedwater calculated    |
| temperatures were 3 degF higher than actual feedwater temperatures. This     |
| resulted in the process computer calorimetric reading 0.6% low. Reactor      |
| power was adjusted using this incorrect calculation resulting in the         |
| overpower condition.                                                         |
|                                                                              |
| "Following identification of the error, Unit load was reduced to ensure that |
| reactor power was less than 100%. Nuclear instrumentation was verified to be |
| indicating less than 100%. No adjustment to the nuclear instrumentation was  |
| performed using the incorrect calculation.                                   |
|                                                                              |
| "This is being reported pursuant to License Condition 2.g, which requires    |
| notification within 24 hours of the violation of any condition in section    |
| 2.c of the Operating License."                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37598       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  DRIESENGA & ASSOCIATES, INC.         |NOTIFICATION DATE: 12/14/2000|
|LICENSEE:  DRIESENGA & ASSOCIATES, INC.         |NOTIFICATION TIME: 21:28[EST]|
|    CITY:  WYOMING                  REGION:  3  |EVENT DATE:        12/14/2000|
|  COUNTY:                            STATE:  MI |EVENT TIME:        08:00[EST]|
|LICENSE#:  21-26634-01           AGREEMENT:  N  |LAST UPDATE DATE:  12/14/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRUCE BURGESS        R3      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DANIEL DRIESENGA             |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER GAUGE STOLEN AND RECOVERED                                           |
|                                                                              |
| A model 3440 Troxler moisture/density gauge was stolen from a company truck  |
| by cutting the chain restraining it.  The theft occurred about 0800 on       |
| 12/14/00 in Wyoming , MI.  The gauge contains <10 mCi Cs-137 and <50 mCi     |
| Am-241.  A report was filed with the Wyoming Police Department, who also     |
| recovered the gauge.                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37599       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 12/15/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 03:53[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        21:30[PST]|
| NRC NOTIFIED BY:  ARTHUR J. MOORE              |LAST UPDATE DATE:  12/15/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHUCK CAIN           R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ISOLATION OF A CONTAINMENT INSTRUMENT AIR HEADER FROM ITS NORMAL SUPPLY AND  |
| ACTUATION OF THE ASSOCIATED BACKUP NITROGEN BOTTLE BANK PROGRAMMER           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 2130 PST, the plant experienced an isolation of the 'B' Containment      |
| Instrument Air (CIA) header from its normal supply and actuation of the      |
| associated backup nitrogen bottle bank programmer.  The isolation and        |
| actuation were due to an actual system low pressure caused by performance of |
| a maintenance procedure in conjunction with a failed heater in the           |
| non-safety related normal Containment Nitrogen (CN) system."                 |
|                                                                              |
| "The CIA system supplies nitrogen to provide motive force for safety-related |
| valves inside the primary containment.  The valves are reactor pressure      |
| vessel Safety Relief Valves (SRVs) and inboard Main Steam Isolation Valves   |
| (MSIVs)."                                                                    |
|                                                                              |
| "Evaluation of computer information indicates that pressure on the 'A' CIA   |
| header may have been below the administrative allowable value for the        |
| associated pressure switch.  Investigation continues as to why the isolation |
| and [actuation] involved only the 'B' train."                                |
|                                                                              |
| "The plant is stable, and there were no other abnormal occurrences in        |
| conjunction with this event."                                                |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+