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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37594 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37595 |
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| 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. |
+------------------------------------------------------------------------------+
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|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. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 37597 |
+------------------------------------------------------------------------------+
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| 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 |
+------------------------------------------------------------------------------+
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| 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. |
+------------------------------------------------------------------------------+
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|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. |
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