Event Notification Report for June 18, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/17/1999 - 06/18/1999
** EVENT NUMBERS **
35790 35833 35835 35836 35837 35838 35839 35840 35841 35842
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|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: 06/17/1999|
| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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 1 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). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35833 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 06/16/1999|
| UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 19:01[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/16/1999|
+------------------------------------------------+EVENT TIME: 15:40[PDT]|
| NRC NOTIFIED BY: BARBARA HANSEN-HARRIS |LAST UPDATE DATE: 06/17/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY REPORT |
| |
| Unescorted access granted inappropriately, immediate compensatory measures |
| taken upon discovery. The licensee notified the NRC Resident Inspector. |
| |
| Refer to HOO Log for additional details. |
| |
| * * * RETRACTION 1215 6/17/99 FROM BARBARA HANSEN-HARRIS TAKEN BY STRANSKY * |
| * * |
| |
| After discussion with the Region IV security inspector, the licensee has |
| determined that this event is loggable, and not reportable. The NRC |
| resident inspector will be informed by the licensee. Notified R4DO |
| (Pellet). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35835 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 06/17/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 09:06[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 06/17/1999|
+------------------------------------------------+EVENT TIME: 08:26[EDT]|
| NRC NOTIFIED BY: DOUGLAS PETERSON |LAST UPDATE DATE: 06/17/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIMI YEROKUN R1 |
|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
+------------------------------------------------------------------------------+
| A CONTRACTOR HAD HIS SITE ACCESS REVOKED DUE TO A DISCOVERY MADE RELATING |
| TO HIS PREVIOUS WORK HISTORY. THE LICENSEE WILL NOTIFY THE NRC RESIDENT |
| INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35836 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/17/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 12:01[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/17/1999|
+------------------------------------------------+EVENT TIME: 10:15[EDT]|
| NRC NOTIFIED BY: PETER GARDNER |LAST UPDATE DATE: 06/17/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT ESF ACTUATION. |
| |
| During preparations for overspeed surveillance testing of the D23 diesel |
| generator an inadvertent 'C' emergency service water pump start signal was |
| received causing the pump to start. The cause of the event was personnel |
| error by an I&C technician during installation of a speed signal generator. |
| The speed tachometer was being calibrated and was set at 900 rpm when the |
| speed signal generator used for overspeed testing was hooked up. Normally |
| the calibration would be complete and the signal generator set at zero rpm |
| prior to hookup. All systems responded as expected. |
| |
| The NRC resident inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35837 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/17/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:15[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/16/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:31[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/17/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 |
| DOCKET: 0707002 |FREDRICK COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ACTUATION OF A "Q" SAFETY SYSTEM. |
| |
| At 1631 hours on 6/16/99, operations personnel responded to a high voltage |
| outleakage smokehead alarm at the X-333 Low Assay Withdrawal (LAW) condenser |
| accumulator area. Operators responded per alarm response procedures and |
| checked for outleakage and observed smoke at Instrument Control Panel (ICP) |
| Number 13. Operators immediately evacuated the area, called 911, and |
| initiated a building recall. |
| |
| The Emergency Response Organization (ERO) responded and monitored air |
| quality for hydrogen fluoride, airborne radioactivity, and surveyed for |
| surface contamination. All sample results were less than minimum detectable |
| activity. Investigation determined that a Dalton fitting in ICP#13 was |
| cross threaded and was considered a possible source of the outleakage. |
| |
| This is reportable as a valid actuation of a "Q" safety system in accordance |
| with Safety Analysis Report, Section 6.9 (24-Hour Report). |
| |
| The NRC resident inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35838 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/17/1999|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 17:27[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/17/1999|
+------------------------------------------------+EVENT TIME: 13:37[CDT]|
| NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 06/17/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INADVERTENT ESF ACTUATION. |
| |
| During the performance of a scheduled surveillance 2-SR-3.3.5.1.2(ATU |
| C)/Core and Containment Cooling Systems Analog Trip Unit Functional Test, |
| Relay 2-RLY-073-23A-K36 was required to have inhibits (boots) installed to |
| prevent HPCI valves (PCIS GP-4 isolation) from actuating due to a simulated |
| high steam flow condition. At 1337 CDT on June 17, 1999, Unit 2 received a |
| group 4 HPCI isolation during the performance of step 7.15.15 of the |
| surveillance procedure. The licensee determined that the wrong contacts had |
| been inhibited allowing the actuation to occur. The inhibits were removed |
| and the PCIS GP-4 isolation was reset at 1402 CDT returning HPCI to an |
| operable condition. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35839 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/17/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 18:16[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 06/17/1999|
+------------------------------------------------+EVENT TIME: 16:30[EDT]|
| NRC NOTIFIED BY: G FIEDLER |LAST UPDATE DATE: 06/17/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIMI YEROKUN R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THREE OF FOUR MAIN STEAM RELIEF VALVES (MSRV) CONEX CONNECTORS INSTALLED |
| BACKWARDS. |
| |
| While shutdown the licensee determined that 3 of 4 MSRV's had the conex |
| connectors installed backwards. The connectors provide the environmental |
| qualification seal to the pilot solenoid valve. ADS may not have functioned |
| under elevated drywell temperature conditions. |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35840 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 06/17/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 21:01[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 06/17/1999|
+------------------------------------------------+EVENT TIME: 17:22[CDT]|
| NRC NOTIFIED BY: S MARIK |LAST UPDATE DATE: 06/17/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+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. |
| |
| At 1722 CDT the 2D primary containment vacuum breaker 2PC001D went from the |
| closed (normal) position to an indicated dual position. The valve is |
| actuated by a differential pressure between the suppression chamber and the |
| drywell air space and is designed to open at 0.5 psid or less. Differential |
| pressure at 1722 CDT was 0.23 psid. An operator was dispatched and the |
| containment vacuum breaker was manually cycled. After being manually cycled |
| the containment vacuum breaker returned to the closed position. The |
| licensee subsequently satisfactorily performed an operability test on the |
| containment vacuum breaker. |
| |
| The licensee has notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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 yet undetermined origin was discovered by a janitor at |
| approximately 2240 hours, Thursday, June 17, 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. |
| |
| 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 will be conducted today of all plant offices and |
| trailers for potential fire hazards. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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 CDST 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 IS SIMILAR TO EVENT 35840. |
+------------------------------------------------------------------------------+
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