Event Notification Report for June 21, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/18/1999 - 06/21/1999
** EVENT NUMBERS **
35790 35801 35832 35834 35841 35842 35843 35844 35845 35846 35847 35848
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35790 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/03/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/02/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/18/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |DAVID HILLS R3 |
| DOCKET: 0707001 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: THOMAS WHITE | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour |
| report) |
| |
| The following text is a portion of a facsimile received from Paducah: |
| |
| "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified |
| that numerous sprinkler heads were corroded, affecting 16 sprinkler systems |
| in C-337 and one system in C-333, such that the ability of the sprinklers to |
| flow sufficient water was called into question. Subsequently, these |
| sprinkler systems were declared inoperable, and TSR-required actions |
| establishing roving fire patrols were initiated. This deficiency was |
| detected during scheduled system inspections conducted by Fire Protection |
| personnel. Currently, functionality of the sprinkler heads has not been |
| fully evaluated by Fire Protection personnel, and the remaining cascade |
| buildings are currently being inspected, and if necessary, this report will |
| be updated to identify any additional areas. |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| The NRC resident inspector has been notified of this event. |
| |
| ******************** UPDATE RECEIVED AT 1022 EDT ON 06/04/99 FROM CAGE TO |
| TROCINE ******************* |
| |
| The following text is a portion of a facsimile received from Paducah: |
| |
| "Two sprinkle heads on system D-1 in C-337 and two sprinkler heads on system |
| 27 in C-335 were identified to also be corroded. These were identified to |
| the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively, and determined |
| to require an update to this report by the PSS. |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| Paducah personnel notified the NRC resident inspector of this update. The |
| NRC operations officer notified the R3DO (Hills) and NMSS EO (Combs). |
| |
| *********** UPDATE RECEIVED AT 2152 EDT ON 06/17/99 FROM WALKER TO POERTNER |
| *********** |
| |
| The following text is a portion of a facsimile received from Paducah: |
| |
| "Three sprinkler heads on system C-15 and five sprinkler heads on system B-8 |
| in C-333 were identified to also be corroded. The PSS was notified of this |
| condition at 1300 CDT on 06/17/99 and determined that an update to this |
| report was required." |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| Paducah personnel notified the NRC resident inspector of this update. The |
| NRC operations officer notified the R3DO (Madera). |
| |
| * * * UPDATE AT 1440 ON 06/18/99 FROM UNDERWOOD TAKEN BY STRANSKY * * * |
| |
| "Two sprinkler heads on system C-15 and one sprinkler head on system B-8 in |
| C-333 were identified to have corrosion. The PSS was notified of this |
| condition at 1350 CDT on 06/18/99. The area of the fire patrol for system |
| C-15 was expanded to include the two heads identified as corroded. The one |
| head on system B-8 was in the area already being patrolled. The PSS |
| determined that an update to this report was required." |
| |
| The NRC resident inspector has been informed of this update. The NRC |
| operations officer notified R3DO (Madera). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35801 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 06/06/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 18:07[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 06/06/1999|
+------------------------------------------------+EVENT TIME: 14:40[CDT]|
| NRC NOTIFIED BY: MIKE MacLENNON |LAST UPDATE DATE: 06/18/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|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 |55 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LIGHTNING STRIKE CAUSED SOME MINOR ALARMS AND PARTIAL GROUP ONE ISOLATIONS |
| |
| "On 06/06/99 at approximately 1440, a lightning strike caused valves |
| 1-0220-44 and 1-0220-45, Reactor Recirculation sample valves, to close on an |
| invalid signal. These valves close automatically on a Group 1 isolation, |
| and therefore this is considered to be an ESF actuation. |
| |
| "The power change indicated above was also a result of the lightning strike. |
| An emergency load reduction was made in response to a partial loss of |
| feedwater heaters. Reactor recirculation flow was manually reduced and |
| control rods were inserted to reduce the flow control line below 100%. |
| Miscellaneous other minor alarms were received on both units due to the |
| lightning strike. |
| |
| "The above sample valves have been reopened, and a load increase to full |
| power has been initiated at 1635." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1115 ON 06/18/99 BY VENCI RECEIVED BY WEAVER * * * |
| |
| On 06/06/99, an ENS notification was made in accordance with |
| 10CFR50.72(b)(2)(ii) as an ESF actuation. A lightning strike caused the |
| reactor recirculation sample valves, 1-0220-44 and 1-0220-45 to close on an |
| invalid signal. These valves close on a Group 1 isolation signal. |
| |
| The subsequent evaluation determined that there were no conditions present |
| to actuate these valves from a Group 1 signal and the PCI logic circuitry |
| was not actuated. Apparently, the lightning strike caused a minor power |
| disturbance of the instrument bus that resulted in the solenoid valves, |
| associated with the reactor recirculation sample valves, to lose power. |
| This caused closure of the 1-0220-44 and 1-0220-45 valves. |
| |
| Quad Cities experienced an invalid signal with no actuation of ESF logic. |
| Therefore, this event is being retracted. |
| |
| The licensee informed the NRC Resident Inspector. The NRC Operations |
| Officer notified the R3DO (Madera). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35832 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/16/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 18:57[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/16/1999|
+------------------------------------------------+EVENT TIME: 18:15[EDT]|
| NRC NOTIFIED BY: CHARLIE KOCSIS |LAST UPDATE DATE: 06/18/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIMI YEROKUN R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH HEAD SAFETY INJECTION EXTERNAL LEAKAGE. |
| |
| On 06/16/99, operators identified packing leakage from a drain valve in the |
| high head safety injection system (valve SI-105). When the leakage was |
| added to the existing system leakage, the control room ventilation system |
| exceeded its system design basis calculation assumption for external |
| recirculation system leakage (0.68 gph). The control room ventilation |
| system continues to remain operable per an existing operability |
| determination (OD 98-16). Leakage was subsequently reduced, such that total |
| system leakage was within design base limits. |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| * * * UPDATE AT 1318 ON 06/18/99 FROM DECLEMENTE TAKEN BY STRANSKY * * * |
| |
| "On 06/16/99, while the plant was in operation, operators identified active |
| packing leakage from a drain valve in the high head safety injection system |
| (valve SI-105). When the leakage is added to the existing system leakage, |
| the control room ventilation system exceeded its system design basis |
| calculation assumption for external recirculation system leakage (0.68 gph). |
| The control room ventilation system continues to remain operable per an |
| existing operability determination (OD 98-16). Following discovery of the |
| active packing leak, adjustments were made that reduced leakage. However, |
| the subsequent calculated leak rate shows the leak rate still remained |
| greater than 0.68 gph, specifically 0.683 gph. |
| |
| "During another test procedure, PT-Q116, packing leakage from valve |
| SI-MOV-851B, 32 safety injection pump discharge isolation valve was found on |
| 06/18/99. Total leak rate of systems outside containment likely to contain |
| radioactive material is 0.689 gph." |
| |
| The licensee will inform the NRC Resident Inspector. The NRC Operations |
| Officer notified R1DO (Yerokun). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35834 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/16/1999|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 20:57[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/16/1999|
+------------------------------------------------+EVENT TIME: 20:00[EDT]|
| NRC NOTIFIED BY: BARRY COLEMAN |LAST UPDATE DATE: 06/18/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY REPORT |
| |
| Plant access granted inappropriately. Immediate compensatory measures taken |
| upon discovery. The licensee notified the NRC resident inspector. |
| |
| Refer to HOO Log for additional details. |
| |
| * * * RETRACTION AT 1312 ON 06/18/99 FROM BARNES TAKEN BY STRANSKY * * * |
| |
| The licensee has determined that this event is not reportable, and this |
| notification is being retracted. The licensee will inform the NRC Resident |
| Inspector. The NRC Operations Officer notified R2DO (Julian). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35841 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 06/18/1999|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 01:41[EDT]|
| RXTYPE: [1] CE |EVENT DATE: 06/17/1999|
+------------------------------------------------+EVENT TIME: 22:40[EDT]|
| NRC NOTIFIED BY: BRUCE HOWARD |LAST UPDATE DATE: 06/18/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INFORMATION CALL - A FIRE ON OWNER CONTROLLED PROPERTY |
| |
| A fire of undetermined origin was discovered by a janitor at 2240 on |
| 06/17/99 in a temporary office trailer, north of the Palisades Training |
| Building. The trailer complex is located one-half mile from the operating |
| plant. There was no impact to the Training Building or the plant's |
| operation, and the plant remained at full power. |
| |
| The control room was notified after discovery of the blaze. The control |
| room dispatched the plant's fire brigade and Covert Fire and Ambulance |
| department to the scene. The plant fire brigade began immediate setup of |
| hoses and began initial fire fighting until the Covert Fire department |
| arrived, some 15 minutes later. |
| |
| The cause of the fire has not been determined. An investigation will be |
| initiated. There were no injuries and no one was in the trailer office at |
| the time. |
| |
| A safety inspection of all plant offices and trailers for potential fire |
| hazards will be conducted on 06/18/99. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35842 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 06/18/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 05:48[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 06/18/1999|
+------------------------------------------------+EVENT TIME: 02:50[CDT]|
| NRC NOTIFIED BY: JIM SPIELER |LAST UPDATE DATE: 06/18/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|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
+------------------------------------------------------------------------------+
| ESF ACTUATION - VACUUM BREAKER |
| |
| At 0250 CDT, #2PC001D, the 2D Primary Containment Vacuum Breaker went from |
| the (normal) closed position to an indicated dual position. Locally, it was |
| determined that the valve was just cracked open. The valve is designed to |
| open when suppression chamber pressure is approximately 0.5 psig greater |
| than drywell pressure. When the vacuum breaker opened the aforementioned |
| differential pressure was approximately 0.2 psid. The vacuum breaker was |
| closed by an equipment attendant and then cycled per LOS-PC-M2 "Unit 2 |
| Drywell-Suppression Pool Vacuum Breaker Operability Test for Condition 1, 2 |
| and 3" to verify proper operation. The valve cycled satisfactorily. |
| |
| The licensee notified the NRC resident inspector. |
| |
| NOTE: THIS EVENT IS SIMILAR TO EVENT #35840. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35843 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NC DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 06/18/1999|
|LICENSEE: BARNHILL CONSTRUCTION |NOTIFICATION TIME: 08:45[EDT]|
| CITY: ROBERSON REGION: 2 |EVENT DATE: 06/14/1999|
| COUNTY: MARTIN STATE: NC |EVENT TIME: 12:00[EDT]|
|LICENSE#: NC-092-0958-1 AGREEMENT: Y |LAST UPDATE DATE: 06/18/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CAUDLE JULIAN R2 |
| |FRED COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MR. JEFFRIES | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|NDAM DAMAGED GAUGE/DEVICE | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DAMAGED MOISTURE DENSITY GAUGE |
| |
| A TROXLER MOISTURE DENSITY GAUGE WAS DAMAGED BY A MOTORIST AT A CONSTRUCTION |
| WORKSITE ALONG HIGHWAY 64 IN MARTIN COUNTY, NC. THE GAUGE WAS SEVERELY |
| DAMAGED AS WAS THE SOURCE TUBE, BUT NO CONTAMINATION WAS SPREAD BY THIS |
| INCIDENT. THE GAUGE HAS BEEN RETURNED TO TROXLER. THE GAUGE IS A MODEL |
| 4640B CONTAINING A 8 mCi Cs-137 SOURCE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35844 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ROSEMOUNT NUCLEAR INSTRUMENTS, INC. |NOTIFICATION DATE: 06/18/1999|
|LICENSEE: ROSEMOUNT NUCLEAR INSTRUMENTS, INC |NOTIFICATION TIME: 12:28[EDT]|
| CITY: EDEN PRAIRIE REGION: 3 |EVENT DATE: 06/18/1999|
| COUNTY: STATE: MN |EVENT TIME: 10:00[CDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/18/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |VERN HODGE (via fax) NRR |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GERRY HANSON | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT REGARDING POTENTIAL NEED FOR CAPACITOR REPLACEMENT IN |
| SPECIFIC TRIP/CALIBRATION SYSTEMS |
| |
| The following is text of a letter submitted to the NRC Operations Center via |
| facsimile: |
| |
| "The purpose of this letter is to inform you that a specific capacitor C25 |
| used in Rosemount Trip/Calibration Systems may require replacement. This |
| affects all Rosemount Model 510DU Trip Units (obsolete since 1987) and |
| certain Rosemount Model 710DU Trip Units. |
| |
| "Prior to 1987, there were 10 confirmed random failures of C25 capacitors |
| used in slave and master trip unit circuit boards. In 1987, a number of |
| tests were run on sample capacitors in an attempt to duplicate the failure |
| modes. It was found that unless the capacitors were exposed to temperatures |
| and voltages in excess of normal operating conditions, no failures were |
| induced. However, introduction of a contaminant such as moisture could |
| possibly cause this type of failure. As a precautionary measure, a |
| component change was instituted on the C25 capacitor beginning with |
| manufacturer date code 8630. This change featured an enhanced moisture |
| seal. No confirmed failures of the post 8630 date code C25 capacitor have |
| been identified. However, Rosemount Nuclear Instruments. Inc is sending |
| this letter to affected utilities to remind users that the model 710 and 510 |
| trip units with pre-8630 date code C25 capacitors could be susceptible to |
| this condition. Failure of the C25 capacitor can cause a low resistance |
| condition between the power supply input and chassis ground. This low |
| resistance can allow over-current conditions to cause failure of the |
| affected unit. |
| |
| "A letter [enclosed in facsimile] was issued by Rosemount Nuclear |
| Instruments Inc to the Scram Frequency Reduction Committee of the BWR |
| Owners' Group in response to a BWROG request for information [enclosed in |
| facsimile], documenting the change which had been made in 1987. Since that |
| time, there have been five additional confirmed C25 failures and fourteen |
| additional failures possibly related to the C25 capacitor. Again, all of |
| these failures occurred in units with C25 capacitors that had date codes of |
| pre-8630. The total number of model 510 and 710 trip units shipped with the |
| pre-8630 date code capacitors was 18,164. We believe that recent failures |
| may warrant further examination of your 510DU/710DU systems to determine |
| whether replacement of the pre-8630 date code capacitors is warranted." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35845 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 06/19/1999|
| UNIT: [] [2] [] STATE: AZ |NOTIFICATION TIME: 04:16[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 06/18/1999|
+------------------------------------------------+EVENT TIME: 22:29[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 06/19/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|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 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - Auto reactor trip from 100% power due to low DNBR trips due to a failed |
| control element assembly calculator - |
| |
| On 06/18/99, at approximately 2229 MST, Palo Verde Unit 2 experienced a |
| reactor trip (RPS actuation) from 100% rated thermal power due to low |
| departure from nucleate boiling ratio (DNBR) trips on all four channels of |
| the core protection calculators (CPCs). Unit 2 was at normal temperature |
| and pressure prior to the trip. |
| |
| Prior to the reactor trip, at approximately 2204 MST, a CPC channel 'C' |
| sensor fail alarm and control element assembly (CEA) withdrawal prohibit |
| (CWP) alarm were received and cleared about one second later. While |
| investigating the alarms, at 2229 MST, all four CPC channel sensor fail |
| alarms and the CWP alarm were received. The reactor automatically tripped |
| six seconds later. A CEA calculator (CEAC) fail alarm was received on CEAC |
| #2. The apparent cause is presently suspected to be the failure of CEAC #2. |
| An investigation has commenced to determine the root cause of the reactor |
| trip. |
| |
| All control rods fully inserted into the core. Four of eight steam bypass |
| control valves quick opened, per design, directing steam flow to the main |
| condenser. No main steam or primary relief valves lifted and none were |
| required. There was no loss of heat removal capability or loss of safety |
| functions associated with this event. Electrical buses transferred to |
| offsite power, as designed. The Shift Manager determined that this event |
| was an uncomplicated reactor trip. No significant LCOs have been entered as |
| a result of this event. No major equipment was inoperable prior to the |
| event nor contributed to the event, other than the CPCs discussed above. |
| |
| Unit 2 is stable in Mode 3 (hot standby) at normal operating temperature and |
| pressure. No ESF actuations occurred and none were required. The event did |
| not result in any challenges to the fission product barrier or result in any |
| releases of radioactive materials. There were no adverse safety |
| consequences or implications as a result of this event. The event did not |
| adversely affect the safe operation of the plant or health and safety of the |
| public. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35846 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/19/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 10:34[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/19/1999|
+------------------------------------------------+EVENT TIME: 10:01[EDT]|
| NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 06/19/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIMI YEROKUN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| -AFW PUMP STARTED DUE TO LOW S/G LEVEL SIGNALS WHILE VENTING A S/G LEVEL |
| TRANSMITTER- |
| |
| WITH UNIT 3 IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE AND THE #2A |
| VITAL INSTRUMENT AC BUS INOPERABLE, PLANT TECHNICIANS WERE VENTING AN 'A' |
| STEAM GENERATOR (S/G) LEVEL TRANSMITTER. THE 'A' AUXILIARY FEEDWATER (AFW) |
| PUMP STARTED DUE TO A LOW S/G LEVEL ACTUATION SIGNAL ALONG WITH A LOW S/G |
| LEVEL SIGNAL DUE TO THE #2A VITAL INSTRUMENT AC BUS BEING INOPERABLE (2 OUT |
| OF 4 LOGIC ACTUATION SIGNAL). PLANT OPERATORS STOPPED THE 'A' AFW PUMP AND |
| RESET IT TO NORMAL WITHIN ONE MINUTE. |
| |
| THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT |
| INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35847 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 06/19/1999|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 11:58[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 06/19/1999|
+------------------------------------------------+EVENT TIME: 10:15[EDT]|
| NRC NOTIFIED BY: PRESTON GILLESPIE |LAST UPDATE DATE: 06/19/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 66 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE TRIP |
| |
| The unit experienced an automatic turbine trip/reactor trip due to an |
| indicated high moisture separator level. Following the trip, all control |
| rods inserted and all systems functioned as required. The reactor is |
| currently stable in Mode 3, with steam generator levels being maintained by |
| the feedwater system and decay heat being removed via the main condenser. |
| |
| The licensee is investigating the cause of the trip, but reported that |
| numerous 125VDC ground alarms were received prior to the trip. The unit had |
| been operating at reduced power because one of the reactor coolant pumps had |
| been secured due to an oil leak. The NRC resident inspector has been |
| informed of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35848 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/19/1999|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 22:25[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/19/1999|
+------------------------------------------------+EVENT TIME: 21:00[CDT]|
| NRC NOTIFIED BY: ROBERT BRINKLEY |LAST UPDATE DATE: 06/19/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO VITAL AREA BOUNDARY. COMPENSATORY |
| MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL INFORM THE NRC RESIDENT |
| INSPECTOR. CONTACT THE OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021