Event Notification Report for April 30, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/27/2001 - 04/30/2001
** EVENT NUMBERS **
37948 37949 37950 37951 37952 37953
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|Power Reactor |Event Number: 37948 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/27/2001|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 17:13[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/27/2001|
+------------------------------------------------+EVENT TIME: 14:51[CDT]|
| NRC NOTIFIED BY: MIKE MCDONALD |LAST UPDATE DATE: 04/27/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 A/R Y 100 Power Operation |0 Hot Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM |
| |
| UNIT 3 scrammed on low reactor water level (+8") due to flow and power |
| oscillations from 3B reactor recirculation pump. The 3B recirculation |
| motor generator set could not be tripped from the main control room and was |
| tripped locally. All rods fully inserted during the scram. The unit is |
| currently stable in mode 3. There were no ECCS injections nor did any SRVs |
| lift. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37949 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MONTANA DEPT OF TRANSPORTATION |NOTIFICATION DATE: 04/27/2001|
|LICENSEE: MONTANA DEPT OF TRANSPORTATION |NOTIFICATION TIME: 22:50[EDT]|
| CITY: PLENTYWOOD REGION: 4 |EVENT DATE: 04/27/2001|
| COUNTY: STATE: MT |EVENT TIME: 12:00[MDT]|
|LICENSE#: 25-11498-01 AGREEMENT: N |LAST UPDATE DATE: 04/27/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BILL JONES R4 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: REX HOY | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| DAMAGED TROXLER GAUGE |
| |
| A Troxler moisture/density gauge model 3440 was run over on a construction |
| site. The gauge contains 8 mCi of Cs-137 and 40 mCi of Am-241. The serial |
| number of the gauge is 20993. The gauge was not seriously damaged. The |
| gauge was surveyed for contaminated and none was found. The gauge has been |
| removed from the job site and placed in storage pending further action. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37950 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/28/2001|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 21:10[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 04/28/2001|
+------------------------------------------------+EVENT TIME: 16:00[EDT]|
| NRC NOTIFIED BY: JAMES WEAST |LAST UPDATE DATE: 04/28/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION - BORON RESIDUE ON REACTOR VESSEL HEAD PENETRATIONS |
| |
| Preliminary reactor head visual inspection indicates a small amount of boron |
| residue surrounding four control rod drive mechanism head penetrations. |
| These indications are similar to those previously reported for unit one and |
| unit three. Additional inspection will be performed to determine the cause |
| of identified boron accumulation. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37951 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 04/29/2001|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 03:18[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/29/2001|
+------------------------------------------------+EVENT TIME: 00:50[EDT]|
| NRC NOTIFIED BY: ROBERT KIDDER |LAST UPDATE DATE: 04/29/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|*ESF 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 M/R Y 16 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL SCRAM DUE TO DEGRADING VACUUM CONDITIONS |
| |
| The licensee had reduced power to 16% and removed the main generator from |
| service due to a stator water leak on the generator exciter causing a |
| ground. After the main generator was off line vacuum started deteriorating |
| and the reactor was manually scrammed. All rods fully inserted and all |
| systems functioned normally. The plant is presently using the reactor core |
| isolation cooling (RCIC) system for makeup and the safety relief valves to |
| the suppression pool for decay heat removal. |
| |
| The cause of the deteriorating vacuum condition is under investigation. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 0526 EDT ON 4/29/01 BY TOM VEITCH TO FANGIE JONES * * * |
| |
| The plant is using RCIC for pressure control and the motor driven feedpump |
| for makeup to the reactor coolant system. Also, at 0116 EDT there was an |
| automatic main steam valve isolation due to the deteriorating vacuum |
| condition, an expected action. This is reportable under 10 CFR |
| 50.72(b)(3)(iv)(B) as an 8 hour report. |
| |
| The licensee notified the NRC Resident Inspector. The R3DO (Thomas Kozak) |
| was notified. |
| |
| * * * UPDATE AT 1641 ON 4/29/01 BY TODD HENDERSON TO DOUG WEAVER * * * |
| |
| At approximately 0215 on 04/29/2001, the Main Steam Isolation Valves closed |
| automatically as a result of the continued loss of vacuum. In a 0530 update |
| to the original notification, this isolation was reported as a specified |
| system actuation in accordance with 10 CFR 50.72 (b)(3)(iv)(A). In that |
| update, the time of the actuation was originally reported as 0116 on |
| 04/29/2001. At approximately the same time, Reactor Core Isolation Cooling |
| (RCIC) was started to assist with pressure control. At 0227, main condenser |
| vacuum was broken. At 0247, a Safety Relief Valve (SRV) was opened and |
| closed to control pressure, with the motor driven feed pump supplying |
| feedwater. |
| |
| Approximately 2 minutes after the first SRV was cycled, a High Pressure Core |
| Spray (HPCS) RPV Level 2 (130" above the top of active fuel) initiation |
| signal was received which started the HPCS pump and Division 3 emergency |
| diesel generator. No injection to the RPV occurred (or should have |
| occurred) because reactor level was above the level where injection was |
| required (Level 8 219" above the top of active fuel). A Division 2 Balance |
| of Plant isolation signal and Redundant Reactivity Control System Level 2 |
| also occurred at this time (with expected plant response including the |
| tripping of both Recirculation pumps). The source of this signal has not |
| yet been determined. |
| |
| At approximately 0430, a Reactor Pressure High/Drain Temperature Low alarm |
| was received, indicating thermal stratification in the reactor pressure |
| vessel due to the loss of reactor recirculation. This originally delayed |
| placing shutdown cooling in operation, but the condition has been cleared |
| allowing progress toward initiating shutdown cooling. |
| |
| The plant is currently in mode 3, with reactor level and pressure being |
| maintained with periodic cycling of Safety Relief Valves and operation of |
| RCIC. Residual heat removal (RHR) train 'B' is being used for suppression |
| pool cooling. Actions are in progress to place RHR train 'A' in shutdown |
| cooling, and bring the plant to Mode 4. |
| |
| The Senior Resident Inspector has been informed of the event. The |
| operations center notified the R3DO (Kozak). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37952 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/29/2001|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 12:19[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/29/2001|
+------------------------------------------------+EVENT TIME: 11:28[EDT]|
| NRC NOTIFIED BY: JOSEPH FRANKS |LAST UPDATE DATE: 04/29/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK R1 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|*ESF 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 97 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE TRIP - REACTOR TRIP |
| |
| The loss of a circulating water pumped led to a turbine trip and reactor |
| trip. All rods inserted after the trip and the plant is stable in mode 3. |
| Reactor coolant pumps are running and the steam generators are being fed |
| with the mainfeed system. The main condenser is available for decay heat |
| removal. One steam generator safety valve may have lifted during the |
| transient, but is closed now. |
| |
| The cause of the circulating water pump trip is unknown. |
| |
| The licensee informed the NRC resident inspector as well as State and local |
| governments. |
| |
| |
| * * * UPDATE AT 1715 ON 4/29/01 BY FRANKS RECEIVED BY WEAVER * * * |
| |
| This update corrects the time of the event from 1151 to 1128. There was |
| also a specified system actuation after the trip. Two auxiliary feedwater |
| pumps started after the trip on low steam generator level. Once level was |
| restored the pumps were secured. The licensee notified the NRC resident |
| inspector. The operations center notified R1DO (Silk). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37953 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/30/2001|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 02:24[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/29/2001|
+------------------------------------------------+EVENT TIME: 22:50[CDT]|
| NRC NOTIFIED BY: DAVE HANKS |LAST UPDATE DATE: 04/30/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EXPECTED LOSS OF SPDS FOR GREATER THAN 8 HOURS |
| |
| Planned maintenance removed safety parameters display system (SPDS) from |
| service for greater than 8 hours. This requires a notification per 10 CFR |
| 50.72(b)(3)(xiii) for loss of assessment capabilities. |
| |
| The licensee notified the NRC Resident Inspector. |
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