Event Notification Report for January 25, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/24/2000 - 01/25/2000
** EVENT NUMBERS **
36610 36612 36618 36619 36620
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|Power Reactor |Event Number: 36610 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/21/2000|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 04:21[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/21/2000|
+------------------------------------------------+EVENT TIME: 02:39[CST]|
| NRC NOTIFIED BY: JOHN SELL |LAST UPDATE DATE: 01/24/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 40 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 MANUALLY TRIPPED FROM 40% POWER DUE TO A DECREASING FOREBAY LEVEL |
| |
| "UNIT 1 WAS MANUALLY TRIPPED FROM 40% POWER AFTER AN ANTICIPATORY POWER |
| REDUCTION AT 0239 CST DUE TO DECREASING LEVEL IN THE CIRC. WATER INLET |
| FOREBAY. DECREASING LEVEL WAS APPARENTLY DUE TO ICING OF THE INTAKE |
| STRUCTURE. UNIT 1 CIRC. WATER SYSTEM HAS BEEN SECURED AND FOREBAY LEVEL HAS |
| INCREASED. THE UNIT 1 CIRC. WATER SYSTEM WAS SECURED TO MAINTAIN |
| OPERABILITY OF THE SERVICE WATER SYSTEM. UNIT 2 REMAINS AT 100% POWER AND |
| IS STABLE." |
| |
| FOREBAY LEVEL HAD DECREASED TO -11 FT FROM THE NORMAL OPERATING -8 FT. THE |
| -11 FT CORRESPONDS TO THE MINIMUM DESIGN LIMIT FOR THE SERVICE WATER SYSTEM. |
| CURRENTLY, LEVEL IS -6 FT 4 INCHES. STEAM GENERATORS USING THE ATMOSPHERIC |
| DUMPS ARE PROVIDING THE HEAT SINK FOR DECAY HEAT REMOVAL SINCE THE CONDENSER |
| IS NOT IN SERVICE. ALL CONTROL RODS FULLY INSERTED FOLLOWING THE MANUAL |
| TRIP. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE ON 01/21/00 @ 1339 EST BY KRAUSE TO GOULD * * * |
| |
| THE LICENSEE UPDATED THIS EVENT BY ALSO CLASSIFYING IT AS A RPS ACTUATION |
| DUE TO THE MANUAL REACTOR TRIP. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| THE R3DO (HILLS) WAS NOTIFIED. |
| |
| * * * UPDATE ON 01/24/00 @ 1201 EST BY KRAUSE TO JONES * * * |
| |
| The licensee performed an engineering evaluation that demonstrated that at |
| no time was the design basis water level for service water exceeded. The |
| report of the Tech Spec required shutdown is retracted, but the report of |
| the RPS activation stands as previously updated. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The R3DO (Monte Phillips) has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36612 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 01/21/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 11:17[EST]|
| RXTYPE: [1] GE-2 |EVENT DATE: 01/21/2000|
+------------------------------------------------+EVENT TIME: 10:48[EST]|
| NRC NOTIFIED BY: GLENN HUTTON |LAST UPDATE DATE: 01/24/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |FELICIA HINSON R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 65 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM PER PROCEDURE FOLLOWING TRIP OF ALL RECIRCULATION |
| PUMPS |
| |
| During the performance of a surveillance test, with a half scram signal |
| inserted, a spurious trip signal from the other system initiated a trip of |
| all the reactor coolant system recirculation pumps. The operators manually |
| scrammed the reactor per procedure, all rods fully inserted. Heat removal |
| is via the main condenser with main feedwater feeding the reactor. All |
| systems functioned as designed and the plant is proceeding to cold shutdown. |
| A trip review will be performed by the licensee. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1943 EST ON 01/24/00 BY FRANK CIGANIK TO FANGIE JONES * * * |
| |
| |
| On 01/21/00, the licensee inserted a manual scram in accordance with station |
| procedures in response to a trip of all the reactor recirculation pumps. |
| The trip of all the pumps was due to an error in the performance of the |
| ongoing surveillance test. |
| |
| "During the performance of an instrument logic surveillance test on the |
| isolation condenser actuation logic which also inserts trip signals into the |
| recirculation pump trip logic, the reactor recirculation pumps tripped. |
| After testing the first instrument, the trip signal associated with the |
| isolation condensers were reset; however, the recirc pump trip logic was not |
| properly reset before proceeding to the second instrument. When a test |
| signal was introduced on this instrument, the reactor recirculation pumps |
| tripped as designed. In response to the pump trip, the operators manually |
| scrammed the reactor. The plant is currently in cold shutdown. A trip |
| review has been performed. Oyster Creek plans to take advantage of this |
| shutdown to perform some other maintenance activities." |
| |
| The original report should have read "half trip" rather than "half scram" |
| referring to the trip logic of the reactor recirculation pumps; this was |
| entered wrong the first time. |
| |
| The licensee notified the NRC Resident Inspector. The R1DO (John Rogge) has |
| been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36618 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 01/24/2000|
| UNIT: [] [4] [] STATE: FL |NOTIFICATION TIME: 12:50[EST]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 01/24/2000|
+------------------------------------------------+EVENT TIME: 11:42[EST]|
| NRC NOTIFIED BY: DAVE MORRIS |LAST UPDATE DATE: 01/24/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|4 M/R Y 95 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO FEEDWATER OSCILLATIONS |
| |
| The licensee had reduced power to 95% to examine the '4A' steam generator |
| feedwater regulating valve due to feedwater oscillations. A preliminary |
| determination of valve internal problems versus control problems was made. |
| The licensee was ready to continue the down power to shutdown to repair the |
| feedwater regulating valve, when a manual trip became necessary due to the |
| feedwater oscillations on '4A' steam generator. |
| |
| All systems functioned as designed, all rods fully inserted, no secondary |
| safety valves lifted, and the plant is stable in Mode 3. Heat removal is |
| via the atmospheric steam dumps, normal procedure with no tube leaks, and |
| feedwater is via the standby feedwater system. The plant will remain shut |
| down until repairs to the feedwater regulating valve are complete. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36619 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 01/24/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 17:59[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 01/24/2000|
+------------------------------------------------+EVENT TIME: 15:30[CST]|
| NRC NOTIFIED BY: STEVE GORTON |LAST UPDATE DATE: 01/24/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MONTE PHILLIPS R3 |
|10 CFR SECTION: |JAMES CREED IAT |
|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 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| COURTESY NOTIFICATION OF LOCAL AND STATE LAW ENFORCEMENT AGENCIES |
| |
| The licensee notified local and state law enforcement agencies as a courtesy |
| concerning an investigation. This prompted notification of the NRC under |
| 10CFR50.72(b)(2)(vi), "Offsite Notification." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| Refer to the HOO log for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36620 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 01/24/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 22:37[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 01/24/2000|
+------------------------------------------------+EVENT TIME: 22:15[EST]|
| NRC NOTIFIED BY: HENRY MANOS |LAST UPDATE DATE: 01/24/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|AENS 50.72(b)(1)(v) ENS INOPERABLE | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| MORE THAN 25% OF THE OFFSITE WARNING SIRENS LOST DUE TO ICE STORMS |
| |
| The licensee reported the loss of more than 25% of the offsite warning |
| sirens due to ice storms passing through the local area. The licensee will |
| be contacting the power suppliers of the sirens to take action to recover |
| them. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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