Event Notification Report for December 21, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/20/2000 - 12/21/2000
** EVENT NUMBERS **
37597 37621 37622 37623 37624 37625 37626 37627
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|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: 12/20/2000|
| 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�F 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. |
| |
| ***** UPDATE AT 1539 CST ON 12/20/00 FROM JIM ROYSTON TO LEIGH TROCINE |
| ***** |
| |
| The licensee is retracting this event notification. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "The initial report to the NRC (Event #37597) was based upon an observation |
| of a 3�F increase in the indicated Feedwater temperature (a primary input to |
| the Calorimetric calculation) following a Computer room temperature change |
| initiated by a swap of the ventilation system. An increase of 3�F in |
| Feedwater temperature results in a 0.55% reduction in Calorimetric power. A |
| declining Calorimetric indication results in Operator action to increase and |
| maintain that indication at 100%. Because of this, the initial indication |
| was that the Unit was inadvertently increased to 100.55%." |
| |
| "Upon execution of troubleshooting it was discovered that the temperature |
| measurement problem was caused by miss-wired RTD temperature elements, which |
| are used to compensate thermocouples for their cold reference junction |
| temperature. From this data, a correction to the temperature measurements |
| was performed such that the true Feedwater temperatures were determined |
| during the event. After applying this correction, it was determined that |
| prior to the event the unit was operating at 99.488%. Following the event, |
| at the highest power level period, the unit was operating at 99.935%. This |
| data also confirms the conclusion that Unit 2 did not exceed 100% power. As |
| an additional check, Calorimetric calculations were performed independently |
| of those executed on the Plant Process Computer which indicate that no |
| problems exist." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Kozak). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37621 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 12/20/2000|
| UNIT: [] [2] [] STATE: WI |NOTIFICATION TIME: 06:31[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/20/2000|
+------------------------------------------------+EVENT TIME: 04:17[CST]|
| NRC NOTIFIED BY: RANDY HASTINGS |LAST UPDATE DATE: 12/20/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK 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 63 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP CAUSED BY TRANSFORMER GROUND |
| |
| The apparent cause of the reactor trip was a turbine trip caused by a ground |
| overcurrent relay actuation on the 2X01 transformer (main power out |
| transformer). Heat removal is via the steam dumps to the main condenser |
| with main feedwater supplying the steam generators. All systems operated as |
| required. The licensee is investigating the cause of the ground |
| indication. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37622 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 12/20/2000|
| UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 11:37[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/20/2000|
+------------------------------------------------+EVENT TIME: 10:35[EST]|
| NRC NOTIFIED BY: CHARLES REID |LAST UPDATE DATE: 12/20/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANTHONY DIMITRIADIS R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE DEP DUE TO OIL SPILL ON SITE |
| |
| The licensee notified the Connecticut Department of Environmental Protection |
| (DEP) about an oil spill due to operator error. The waste oil separator was |
| in operation filling a 55-gallon drum when the operator overflowed the drum. |
| The spill was contained on the concrete pad, there was no release offsite or |
| to the water. Cleanup is now in progress. |
| |
| The licensee notified NRC Region 1 (John Wray). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37623 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SOUTHEAST MO STATE UNIVERSITY |NOTIFICATION DATE: 12/20/2000|
|LICENSEE: SOUTHEAST MO STATE UNIVERSITY |NOTIFICATION TIME: 13:52[EST]|
| CITY: CAPE GIRARDEAU REGION: 3 |EVENT DATE: 12/19/2000|
| COUNTY: CAPE GIRARDEAU STATE: MO |EVENT TIME: 13:30[CST]|
|LICENSE#: 24-09296-02 AGREEMENT: N |LAST UPDATE DATE: 12/20/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |THOMAS KOZAK R3 |
| |CHERYL TROTTIER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHRIS McGOWLAN | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST STRONTIUM-90 SOURCE |
| |
| The school has lost a 20 mCi Sr-90 sealed source. It is unknown how long it |
| has been missing. A search of physical areas and records have been |
| unsuccessful in locating the source. As long as the source remains sealed |
| it presents little of no threat to the public. |
| |
| The source was used as part of an ionization cell for an ion capture |
| detector. The equipment was sold sometime back at auction. The paperwork |
| for the equipment does not indicate that the source was included in the |
| sale. |
| |
| The school has been in contact with NRC Region 3 (Kevin Null). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37624 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 12/20/2000|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 18:01[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/20/2000|
+------------------------------------------------+EVENT TIME: 08:55[EST]|
| NRC NOTIFIED BY: DEAN BRUCK |LAST UPDATE DATE: 12/20/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 0 Startup |2 Startup |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT REGARDING A NON-LICENSED SUPERVISOR'S RANDOM |
| POSITIVE TEST FOR ALCOHOL |
| |
| A non-licensed supervisor tested positive for alcohol during a random test. |
| This was a first time positive test for this individual. The individual was |
| removed from site, and the individual's badge was placed on administrative |
| hold. |
| |
| The licensee made this 24-hour event notification in accordance with 10 CFR |
| 26.73(a)(2)(iv). |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37625 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/20/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:04[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/20/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:05[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/20/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |THOMAS KOZAK R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC G. WALKER | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR REPORT) - LOSS OF ONE CONTROL IN THE |
| DOUBLE CONTINGENCY |
| |
| The following text is a portion of a facsimile received from the Paducah |
| personnel: |
| |
| "The C-331 E and F surge drum room temperature was found to be at 103 |
| degrees F in violation of NCSA.CAS-005. Requirement 3.2.6 of this NCSA |
| states that when the surge drums contain UF6, they shall be operated at a |
| minimum temperature of 105 degrees F. This temperature requirement prevents |
| hydrogen fluoride (HF) from condensing at the maximum pressure rating of the |
| drums. Should HF condense it could moderate any UF6 that might be |
| present." |
| |
| "SAFETY SIGNIFICANCE OF EVENTS:" |
| |
| "HF cannot condense at 103 degrees F and 20 psia. The drum pressures were |
| all less than 1 psia; therefore, it was not possible to condense HF." |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR:" |
| |
| "In order for a criticality to be possible, HF would have to condense. |
| Therefore, the temperature of the drums would have to be less than 80 |
| degrees F, and the drum pressures would have to exceed 20 psia." |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):" |
| |
| "[Since the double] contingency is based on two controls on moderation and |
| [since] the temperature control was lost, double contingency was not |
| maintained." |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS):" |
| |
| "The surge drums contain an estimated 1425 pounds of UF6 at less than 1 |
| weight % U235 assay." |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES:" |
| |
| "The first leg of double contingency is an administrative control, which |
| limits the surge drum room temperature to a minimum of 105 degrees F. The |
| control was violated, and the first leg of double contingency was lost." |
| |
| "The second leg of double contingency is an administrative control to |
| maintain the drum pressures below 20 psia, which is the maximum rated |
| pressure for the drums. This control was not violated, and this leg of |
| double contingency was maintained." |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS |
| IMPLEMENTED:" |
| |
| "Temperature loss was due to low outside ambient temperature. Building |
| temperature was raised and surge drum room temperature rose above minimum |
| required temperature. Additional heating for the area is being |
| considered." |
| |
| Paducah personnel notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37626 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 12/20/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 22:25[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 12/20/2000|
+------------------------------------------------+EVENT TIME: 20:14[EST]|
| NRC NOTIFIED BY: ROBERT McCOY |LAST UPDATE DATE: 12/20/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANTHONY DIMITRIADIS R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC CONTROL ROOM VENTILATION SYSTEM SHIFT FROM NORMAL TO EMERGENCY |
| RECIRCULATION MODE WHILE A PLANNED GAS DECAY TANK RELEASE WAS IN PROGRESS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 2014, with a gas decay tank release in progress (total activity 0.215 |
| Ci, (Kr-85 = 0.214 Ci, Xe-133 = 0.001 Ci)), control room ventilation gas |
| monitor R-36 went into alarm causing ventilation to shift to mode F. During |
| the [2-second] spike, R-36 counts went from 30 cpm to 856 cpm and back to 30 |
| cpm. Local air samples taken by the RP Tech both in the control room and in |
| the area of the control room ventilation intake revealed no activity." |
| |
| The licensee stated that the gas decay tank release was planned and that the |
| counts going through the plant stack were considered normal. (These counts |
| peaked at 120 cpm.) The licensee stated that the planned gas decay tank |
| release was within both the expected and required release limits. The wind |
| was blowing in a favorable direction, and the stability class for |
| meteorological conditions was stable. Although counts have returned to |
| normal, the licensee plans to leave control room ventilation in the |
| emergency recirculation mode until tomorrow morning. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37627 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 12/20/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 22:58[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/20/2000|
+------------------------------------------------+EVENT TIME: 20:08[EST]|
| NRC NOTIFIED BY: REINSBURROW |LAST UPDATE DATE: 12/20/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE ERNSTES R2 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| FAILURE OF A REACTOR CORE ISOLATION COOLING (RCIC) BYPASS TO CONDENSATE |
| STORAGE TANK VALVE TO FULLY STROKE DURING STROKE TIME TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "EVENT: At 2008 on 12/20/00 during performance of OPT-10.1.8 (RCIC System |
| Valve Operability Test), the 2-E51-F022 (RCIC bypass to condensate storage |
| tank) failed to fully stroke during stroke timing of the valve. A valve |
| thermal overload annunciator was received. This rendered the Brunswick Unit |
| 2 RCIC system inoperable. RCIC was not in operation at the time of this |
| failure." |
| |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION: Minimal safety significance. |
| Remaining ECCS systems are operable." |
| |
| "CORRECTIVE ACTION(S): Determine the cause of the 2-E51-F022 valve failure. |
| Return the Unit 2 RCIC system to operable following repair of 2-E51-F022." |
| |
| The licensee stated that this event did not result in any radiological |
| release or reactor coolant leaks. The licensee also stated that all systems |
| functioned as required and that there was nothing unusual or misunderstood. |
| This event placed the unit in a 14-day technical specification limiting |
| condition for operation. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
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