Event Notification Report for July 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/16/1999 - 07/19/1999
** EVENT NUMBERS **
35922 35923 35924 35925 35926 35927 35928 35929 35930 35931
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35922 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 07/15/1999|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 16:45[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/15/1999|
+------------------------------------------------+EVENT TIME: 14:44[EDT]|
| NRC NOTIFIED BY: KATHLEEN BRESLIN |LAST UPDATE DATE: 07/16/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF 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
+------------------------------------------------------------------------------+
| UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP FROM 100% POWER DURING RPS |
| TESTING. |
| |
| THE McGUIRE UNIT 2 REACTOR TRIPPED FROM 100% POWER. THE TRIP INVOLVED AN |
| AUTOMATIC ACTUATION OF THE REACTOR PROTECTION SYSTEM (RPS). INVESTIGATION |
| OF THE CAUSE OF THE REACTOR TRIP IS IN PROGRESS AND IS BELIEVED TO BE FROM |
| 'A' TRAIN SOLID STATE PROTECTION SYSTEM (SSPS) TESTING. THE '2A' AUXILIARY |
| FEEDWATER PUMP DID NOT START AUTOMATICALLY AND WAS MANUALLY STARTED. |
| |
| UNIT 2 IS CURRENTLY STABLE IN MODE 3. NO PRIMARY OR SECONDARY POWER |
| OPERATED RELIEF VALVES OR SAFETY VALVES LIFTED DURING THE TRANSIENT. ALL |
| CONTROL RODS FULLY INSERTED. THE MAIN FEEDWATER SYSTEM HAS BEEN RESTORED |
| WITH DECAY HEAT BEING REJECTED TO THE MAIN CONDENSER. THE EMERGENCY DIESEL |
| GENERATORS ARE AVAILABLE, IF NEEDED. THE LICENSEE INFORMED THE NRC RESIDENT |
| INSPECTOR. |
| |
| * * * UPDATE AT 0730 EDT ON 7/16/99 BY THAD REAMES TO FANGIE JONES * * * |
| |
| The cause of the reactor trip was determined to be a turbine trip while |
| reactor power was greater than 48%. The turbine trip was due to testing |
| that was being performed on the '2A' reactor trip breaker after it had been |
| replaced. The test caused the turbine trip signal because the new reactor |
| trip breaker had a bad set of contacts in it. The '2A' reactor trip breaker |
| has been replaced and verified operable. |
| |
| The licensee notified the NRC Resident Inspector. The Headquarters |
| Operations Officer notified the R2DO (Ann Boland). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35923 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MD RADIOLOGICAL HEALTH PROGRAM |NOTIFICATION DATE: 07/16/1999|
|LICENSEE: KCI TECHNOLOGIES |NOTIFICATION TIME: 10:44[EDT]|
| CITY: LAYTONSVILLE REGION: 1 |EVENT DATE: 07/15/1999|
| COUNTY: MONTGOMERY STATE: MD |EVENT TIME: 15:30[EDT]|
|LICENSE#: MD-05-150-01 AGREEMENT: Y |LAST UPDATE DATE: 07/16/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN WHITE R1 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONNA GAINES | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DAMAGED TROXLER MOISTURE/DENSITY GAUGE |
| |
| The state of Maryland reported that a Troxler moisture/density gauge, model |
| number 3411B and serial number 11038, was damaged (run over) at the Oaks |
| Sanitary Landfill in Laytonsville, MD on 7/15/99. The state responded to |
| the scene along with the licensee's Radiation Safety Office (KCI |
| Technologies of Baltimore, MD). The gauge was damaged. The source was in |
| the shielded position. The gauge was surveyed and it was determined that the |
| shielding had not been compromised. The gauge was returned to the |
| licensee's facility in Baltimore and will be shipped to Troxler for |
| disposal. |
| |
| There were no personnel overexposures or contaminations, and the source was |
| still intact. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35924 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 07/16/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 13:24[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 07/16/1999|
+------------------------------------------------+EVENT TIME: 12:45[EDT]|
| NRC NOTIFIED BY: VINCENT FALLACARA |LAST UPDATE DATE: 07/16/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LICENSEE IDENTIFIED DURING OPERATOR REQUALIFICATION A CONDITION WHICH PLACES |
| THE UNIT OUTSIDE THE DESIGN BASES. |
| |
| "PDC99.05 (EDG breaker logic modification) could prevent B6 [swing bus] from |
| automatically re-energizing during a LOCA coincident with degraded voltage. |
| |
| "A LOCA with degraded voltage will delay the de-energization of the 480V |
| load centers BI and B2. The EDG's will start immediately on the LOCA signal |
| and the new design will have the EDG 10 second timer working in parallel |
| with the degraded voltage 10 second timer. Once the degraded voltage relay |
| times out the 4KV buses A5 and A6 will be isolated and the EDGs will load |
| within a couple of seconds. This time will not allow the B6 transfer |
| breaker time to precharge and thus leave bus B6 de-energized. |
| |
| "The problem was identified during review of [Problem Report] PR99.9417. |
| |
| "[The cause of the problem was that ] the design did not consider the |
| pre-charging time of the B6 feeder breakers. |
| |
| "[Corrective actions taken included a determination that ] the EDG, |
| emergency distribution system and ECCS systems are operable. The basis for |
| operability identified in Engineering Evaluation EE98-54 (operability |
| evaluation OP98-34) still apply." |
| |
| The corrective action includes verifying grid stability and, if a degraded |
| voltage condition exists, starting the stations EDGs and realigning the |
| power supplies for the safeguards buses. The licensee informed the NRC |
| Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35925 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TVA |NOTIFICATION DATE: 07/16/1999|
|LICENSEE: TVA |NOTIFICATION TIME: 15:41[EDT]|
| CITY: CHATTANOOGA REGION: 2 |EVENT DATE: 07/11/1999|
| COUNTY: HAMILTON STATE: TN |EVENT TIME: 18:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 07/16/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANN BOLAND R2 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MARCIA COOPER | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TVA TESTING AND MAINTENANCE DIVISION LOCATED IN CHATTANOOGA, TN, REPORTED |
| THAT A HANDHELD X-MET ANALYZER CONTAINING 40 MILLICURIES OF IRON-55 AND 10 |
| MILLICURIES OF CADMIUM-109 WAS INADVERTENTLY LEFT UNATTENDED ON A LOADING |
| DOCK BETWEEN APPROXIMATELY 1000-1100 EDT ON 7/10/99 THROUGH 1800-2000 EDT ON |
| 7/11/99. THERE WAS NO INDICATION OF TAMPERING, CONTAMINATION OR PERSONNEL |
| OVEREXPOSURE INVOLVED. THIS DEVICE IS USED FOR METAL IDENTIFICATION AND |
| FALLS UNDER A GENERAL LICENSE. THIS REPORT WAS CONSERVATIVELY MADE UNDER |
| 10CFR20.2201(a). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35926 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/16/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/16/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/16/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |RONALD GARDNER R3 |
| DOCKET: 0707002 |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RON CRABTREE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 4-HOUR REPORT INVOLVING COURTESY NOTIFICATION TO OSHA FOLLOWING AN EMPLOYEE |
| WORK INJURY. |
| |
| "On 7/16/99 at 1028 hours, it was reported to Emergency Responders that an |
| employee had been injured by an electrical flash while performing |
| Preventative Maintenance on a 480volt system. Emergency Medical |
| Technicians/Paramedics responded to the scene and treated/stabilized |
| employee and transported the employee to an area hospital for further |
| treatment. At approximately 1600 hours, The PORTS ES&H Manager made a |
| courtesy notification to OSHA regarding this injury/accident. This |
| notification to another government agency is reportable to NRC as a |
| four-hour notification report." |
| |
| The NRC Resident Inspector and DOE Site Representative were informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35927 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/16/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 19:25[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/16/1999|
+------------------------------------------------+EVENT TIME: 19:12[EDT]|
| NRC NOTIFIED BY: CHARLES TRIPLETT |LAST UPDATE DATE: 07/16/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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 94 Power Operation |94 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN DUE TO THE LOSS OF BOTH A |
| BATTERY CHARGER AND ITS ASSOCIATED RECTIFIER. |
| |
| "WHILE TESTING #2 EMERGENCY DIESEL GENERATOR, THE SUPPLY BREAKER FROM THE |
| NORMAL 4KV BUS TRIPPED OPEN ON AN OVERCURRENT SIGNAL. THE #2 EMERGENCY |
| DIESEL GENERATOR WAS TRIPPED DUE TO INDICATED LOW EXCITATION VOLTAGE. THIS |
| LED TO A LOSS OF POWER TO THE DF EMERGENCY BUS. NUMBER 2 AND 4 BATTERY |
| CHARGERS BECAME INOPERABLE AND ENTRY INTO TECH SPEC 3.0.3 ACTION STATEMENT |
| OCCURRED. TECH SPEC REQUIRED SHUTDOWN WAS INITIATED AT 1912[EDT]. |
| INVESTIGATION IS CONTINUING TO DETERMINE CAUSE OF BREAKER TRIP." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE 2108EDT ON 7/16/99 FROM CHARLES TRIPLETT TO S. SANDIN * * * |
| |
| THE LICENSEE IS UPDATING THIS REPORT TO INCLUDE AN ESF ACTUATION OF THE #2 |
| EMERGENCY DIESEL GENERATOR. |
| |
| "AFTER BEING MANUALLY TRIPPED AT 1729[EDT] DUE TO INDICATED LOW EXCITATION |
| VOLTAGE, THE #2 EMERGENCY DIESEL GENERATOR SUBSEQUENTLY RESTARTED |
| AUTOMATICALLY AT 1812[EDT] WHEN DIESEL GENERATOR AUTO/LOCAL CONTROL SWITCH |
| WAS TAKEN TO THE LOCAL POSITION. THE DIESEL OUTPUT BREAKER CONTROL SWITCH |
| WAS IN PULL-TO-LOCK AND DID NOT RECLOSE. INVESTIGATION INTO THE CAUSE OF |
| THE AUTO START IS CONTINUING. |
| |
| "UPDATING [THIS REPORT], THE DE-ENERGIZED DF EMERGENCY BUS HAS BEEN |
| RE-ENERGIZED AND BOTH BATTERY CHARGERS ARE CHARGING [THEIR] RESPECTIVE |
| BATTERIES. THE BATTERIES ARE INOPERABLE DUE TO LOW PILOT CELL VOLTAGE AND |
| [THE] PLANT SHUTDOWN CONTINUES." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R1DO(WHITE). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35928 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 07/17/1999|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 06:16[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/17/1999|
+------------------------------------------------+EVENT TIME: 04:49[CDT]|
| NRC NOTIFIED BY: DOUG SMITH |LAST UPDATE DATE: 07/17/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER 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 |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC START OF AUX BUILDING SPECIAL VENT SYSTEM |
| |
| The auxiliary building special vent system received an automatic start |
| signal from a spike on radiation monitor 1R30 (aux building vent gas |
| radiation monitor). Redundant radiation monitor 1R37 did not show any change |
| in radiation levels. The licensee will investigate the cause of the spike on |
| monitor 1R30. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35929 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 07/17/1999|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 11:30[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 07/17/1999|
+------------------------------------------------+EVENT TIME: 08:45[EDT]|
| NRC NOTIFIED BY: ALAN HALL |LAST UPDATE DATE: 07/17/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|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 Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE AGENCY CONCERNING DEAD LOGGERHEAD TURTLE FOUND |
| IN THE INTAKE CANAL. |
| |
| THE STATE OF FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) WAS |
| NOTIFIED OF A LOGGERHEAD TURTLE MORTALITY AT ST. LUCIE PLANT INTAKE CANAL. |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35930 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/17/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 20:26[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/17/1999|
+------------------------------------------------+EVENT TIME: 20:21[EDT]|
| NRC NOTIFIED BY: JIM TURNER |LAST UPDATE DATE: 07/17/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 64 Power Operation |63 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN DUE TO INADEQUATE ALLOWABLE |
| TIME TO COMPLETE REPAIRS. |
| |
| "UNIT 2 IS SHUTTING DOWN PER TECHNICAL SPECIFICATION 3.8.1.1. THE 2-2 |
| EMERGENCY DIESEL GENERATOR WAS DECLARED INOPERABLE AT 2157 HOURS, 7/14/99, |
| DUE TO HEAT EXCHANGER FOULING. WHILE PERFORMING POST MAINTENANCE TESTING AT |
| 1729 [HOURS], 7/16/99, THE 2DF BUS WAS LOST APPARENTLY CAUSED BY A 2-2 |
| DIESEL GENERATOR MALFUNCTION. THERE IS NOT ADEQUATE ALLOWABLE OUTAGE TIME |
| REMAINING TO REPAIR AND TEST THE DIESEL GENERATOR, SO THE TECHNICAL |
| SPECIFICATION REQUIRED SHUTDOWN IS STARTING." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| HOO NOTE: SEE EVENT #35927 FOR ADDITIONAL INFORMATION. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35931 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 07/18/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 20:41[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 07/18/1999|
+------------------------------------------------+EVENT TIME: 18:07[EDT]|
| NRC NOTIFIED BY: BOB BOYER |LAST UPDATE DATE: 07/18/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE 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
+------------------------------------------------------------------------------+
| TWO OF THREE OPERATING REACTOR CONTAINMENT BUILDING (RCB) FANS UNEXPECTEDLY |
| TRIPPED DURING TROUBLESHOOTING OF ENGINEERED SAFEGUARDS ACTUATION SIGNAL |
| (ESAS) RELAYS BY A CONTROL ROOM OPERATOR (CRO). |
| |
| "A CRO was checking the ESAS relays for noise, humming or signs of |
| overheating after the relays had been exercised as a result of de-energizing |
| VBB for 1B Inverter restoration. While trying to identify a humming relay |
| the CRO touched what he thought was the frame of relay 1X1A RCB, but what he |
| touched actuated the relay contacts. This caused AH-E-1B and AH-E-1C to |
| trip. |
| |
| "The crew restarted AH-E-1B and AH-E-1C and followed Alarm response B-1-5 |
| '480V ES Motor Trip.' Electrical prints (209-570 and 209-592) were referred |
| to and showed that the relay is a normally de-energized relay. It sends a |
| signal to the 1S and 1T 480V under voltage circuit, DH-V-4B to open and |
| AH-E-1B/C to trip. The UV relays were verified to have not actuated and |
| they were manually reset as a precautionary measure. DH-V-4B was verified |
| still closed. |
| |
| "It is believed since the CRO only slightly moved the relay and AH-E-1B/C |
| contacts are normally closed when the relay is de-energized and the other |
| three relays are normally open, that the movement was enough to break the |
| closed contacts but not enough to make up the open contacts." |
| |
| The licensee will inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021