U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/21/95 - 07/24/95 ** EVENT NUMBERS ** 29049 29094 29095 29096 29097 29098 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29049 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/11/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/11/95 | +------------------------------------------------+EVENT TIME: 12:38[CDT]| |NRC NOTIFIED BY: MARK KAUL |LAST UPDATE DATE: 07/21/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | -CONTROL ROOM HVAC EMERGENCY BYPASS SYSTEM INOP DUE TO FAILED RAD MONITOR- | | | | AT 1154 (CDT), A CONTROL ROOM VENTILATION RADIATION MONITOR ALARMED AND | | ACTUATED THE CONTROL ROOM HVAC EMERGENCY BYPASS SYSTEM. | | | | AT 1238 (CDT), THE LICENSEE DETERMINED THAT THE RADIATION MONITOR WAS | | MALFUNCTIONING AND DECLARED THE CONTROL ROOM HVAC EMERGENCY BYPASS SYSTEM | | INOPERABLE. | | | | TECH SPEC LCO A/S 3.12.A.2, TABLE 3.2.D, REQUIRES THE LICENSEE TO RESTORE | | THE CONTROL ROOM HVAC EMERGENCY BYPASS SYSTEM TO OPERABLE STATUS WITHIN 7 | | DAYS OR TO SHUT THE PLANT DOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***RETRACTION @ 09:15 07/21/95 FROM BENNETT TAKEN BY SEBROSKY *** | | THE LICENSEE IS RETRACTING THE EVENT. THE FOLLOWING IS A TEXT OF A | | FACSIMILE FROM THE LICENSEE: | | | | "THE CONTROL EMERGENCY FILTER SYSTEM (CREFS) IS A SINGLE TRAIN SYSTEM THAT | | MITIGATES DOSE TO CONTROL ROOM PERSONNEL DURING A DESIGN BASIS ACCIDENT. | | THE KEY INPUT INTO INITIATING ACCIDENT MODE OF OPERATION IS THE CONTROL | | ROOM VENTILATION RADIATION MONITOR. SPIKING ON THE PARTICULATE ACTIVITY | | CHANNEL CAUSED THE CREFS TO AUTOMATICALLY SHIFT TO THE EMERGENCY BYPASS | | MODE. THE SPIKING WAS DETERMINED TO BE SPURIOUS, BUT THE INITIAL | | REPORTABILITY DETERMINATION CONSERVATIVELY ASSUMED THAT CREFS WAS | | INOPERABLE FOR SOME PERIOD PRIOR TO THE RECORDED SPIKING (AND EMERGENCY | | BYPASS ACTUATION), SINCE THE NATURE OF THE CONTROL ROOM VENTILATION MONITOR | | FAILURE WAS NOT KNOWN AND ITS PRIOR OPERABILITY COULD NOT FIRMLY BE | | ESTABLISHED. SUBSEQUENT MAINTENANCE AND TESTING HAS DETERMINED THAT THE | | PARTICULATE RECORDER WAS ACCURATELY READING THE OUTPUT OF THE CONTROL ROOM | | VENTILATION MONITOR. THEREFORE, THE FAILURE OCCURRED COINCIDENT WITH CREFS | | EMERGENCY BYPASS ACTUATION, AND THERE WAS NO PERIOD OF PRIOR INOPERABILITY | | THAT WOULD HAVE RENDERED CREFS INOPERABLE. SINCE, AS A RESULT OF THIS | | FAILURE, CREFS SHIFTED TO ITS ACCIDENT MODE OF OPERATION (AND WAS | | MAINTAINED THERE UNTIL THE CONTROL ROOM VENTILATION MONITOR WAS RESTORED TO | | OPERABILITY), THERE WAS NO LOSS OF ACCIDENT MITIGATION CAPABILITY AS | | ORIGINALLY SUPPOSED. ACCORDINGLY THIS OCCURRENCE IS NOT REPORTABLE." END | | OF TEXT. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. THE HOO NOTIFIED THE R4DO | | (STETKA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29094 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 07/21/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 03:21 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/21/95 | +------------------------------------------------+EVENT TIME: 01:40[EDT]| |NRC NOTIFIED BY: MARK HOLBEIN |LAST UPDATE DATE: 07/21/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SAFETY INJECTION SIGNAL ACTUATED DUE TO PROCEDURE INADEQUACY DURING A TEST | | | | WHILE PERFORMING A TECH SPEC SURVEILLANCE CONTAINMENT HIGH PRESSURE AND | | SPRAY SYSTEM TEST, ONE OF TWO SAFETY INJECTION CHANNELS WAS INADVERTENTLY | | ACTUATED. NO SAFETY INJECTION OCCURRED. | | | | THE SAFETY INJECTION SIGNAL ACTUATION WAS NOT EXPECTED AND APPEARS NOT TO | | HAVE BEEN PROPERLY ISOLATED DUE TO AN INADEQUACY IN THE TEST PROCEDURE. | | | | THE LICENSEE RESET THE SAFETY INJECTION SIGNAL TO NORMAL AT 0200. | | | | THE LICENSEE PLANS TO EVALUATE THE TEST PROCEDURE AND REVISE IT AS | | NECESSARY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0501 ON 7/21/95 BY MARK HOLBEIN TAKEN BY HOO JOLLIFFE * * * | | | | AT 0404, WHILE RESTORING THE SYSTEM TO ITS PRE-TEST CONDITION, AN | | ELECTRICIAN CREATED AN ELECTRICAL SHORT CIRCUIT WHICH CAUSED ONE OF TWO | | SAFETY INJECTION CHANNELS TO AGAIN ACTUATE. NO SAFETY INJECTION OCCURRED. | | | | THE LICENSEE RESET THE SAFETY INJECTION SIGNAL TO NORMAL AT 0422. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED THE R3DO (MARK RING). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29095 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/21/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/21/95 | +------------------------------------------------+EVENT TIME: 12:26[EDT]| |NRC NOTIFIED BY: LONG |LAST UPDATE DATE: 07/21/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS RDO | |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 +------------------------------------------------------------------------------+ | DIVISION II HALF SCRAM AND SEVERAL GROUP ISOLATIONS DUE TO A VOLTAGE DIP ON | | THE 'B' RPS BUS. (REFER TO SIMILAR EVENT NUMBER 29097.) | | | | AT 1226 EDT ON 7/21/95, UNIT 1 RECEIVED A DIVISION II HALF SCRAM SIGNAL. | | IN ADDITION, A DIVISION II GROUP 1, 2, 3, AND 6 ISOLATION SIGNAL; A | | REACTOR BUILDING AND SECONDARY CONTAINMENT ISOLATION SIGNAL; AND A | | STANDBY GAS TREATMENT SYSTEM INITIATION SIGNAL OCCURRED, AS EXPECTED. ALL | | REQUIRED AUTOMATIC ACTIONS AND ISOLATIONS WERE VERIFIED TO HAVE OCCURRED. | | THE FOLLOWING VALVES WERE VERIFIED TO HAVE CLOSED: | | 1-G31-F004 RWCU OUTBOARD ISOLATION VALVE GROUP 3 | | 1-G16-F004 DW FLOOR DRAIN OUTBOARD ISOLATION VALVE GROUP 2 | | 1-G16-F020 DW EQUIPMENT DRAIN OUTBOARD ISOLATION VALVE GROUP 2 | | 1-B32-F020 SAMPLE OUTBOARD ISOLATION VALVE GROUP 1 | | 1-CAC-V23 DRYWELL PURGE EXHAUST VALVE GROUP 6 | | 1-CAC-V22 TORUS PURGE EXHAUST VALVE GROUP 6 | | ALONG WITH GROUP 6 DRYWELL MONITOR ISOLATION VALVES. (MOST OF THE GROUP 6 | | VALVES WERE ALREADY CLOSED.) | | | | PLOTS OF THE 'B' BUS RPS VOLTAGE SHOWED A DIP IN VOLTAGE WHICH RESULTED IN | | TRIPPING OF THE ELECTRONIC PROTECTION DEVICE FOR THE RPS BUS 'B' ON LOW | | VOLTAGE AS DESIGNED. | | | | THE ISOLATED SYSTEMS WERE RETURNED TO SERVICE BY 1406 EDT. THE 'B' RPS BUS | | WAS TRANSFERRED TO ITS ALTERNATE SUPPLY SOURCE FROM EMERGENCY BUS 'E6'. THE | | ONE HALF GROUP 1 AND ONE HALF RPS TRIP HAVE BEEN RESET. THE CAUSE OF THE | | ELECTRONIC PROTECTION DEVICE TRIP IS BEING INVESTIGATED. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29096 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 07/21/95 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 20:45 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 07/21/95 | +------------------------------------------------+EVENT TIME: 00:00[PDT]| |NRC NOTIFIED BY: RILEY |LAST UPDATE DATE: 07/21/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 83 POWER OPERATION | 83 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAN ONOFRE PROVIDED A PART 21 REPORT REGARDING POTTER & BRUMFIELD (P&B) | | MODEL-5095 MOTOR-DRIVEN RELAYS (MDR). SAN ONOFRE WAS NOTIFIED BY P&B OF | | POSSIBLE IMPROPER RE-ASSEMBLY OF SEVERAL DIFFERENT MODELS OF P&B RELAYS. | | THE IMPROPER RE-ASSEMBLY INVOLVES INTERNALLY DAMAGED (BENT) CONTACT ARMS | | THAT COULD ADVERSELY EFFECT RELAY INTERRUPT CAPABILITY, DIELECTRIC | | CAPABILITY, RELIABILITY, AND LIFE EXPECTANCY. THE PROBLEM IS POTENTIALLY | | APPLICABLE TO ANY MDR RELAY RETURNED TO P&B FOR REWORK OR DISASSEMBLY | | BETWEEN MARCH 1993 AND MARCH 1995. | | | | POTTER & BRUMFIELD INC. (A SEIMENS CO.) IS LOCATED IN MARION, KY. SEVEN OF | | EIGHTEEN RELAYS RETURNED FROM P&B TO SONGS WERE SUBSEQUENTLY INSTALLED IN | | SAFETY-RELATED SYSTEMS OF THE SONGS PLANTS. THE MOST LIMITING APPLICATION | | OF THESE SEVEN MDR RELAYS IS IN THE CONTROL CIRCUITS OF VALCOR SOLENOID | | VALVES WHICH ISOLATE CONTAINMENT PRESSURE TRANSMITTER SENSING LINES AT | | UNITS 2 AND 3. THE SOLENOID VALVES ARE NORMALLY OPEN AND REMAIN OPEN | | DURING ACCIDENT CONDITIONS INSIDE THE CONTAINMENT. THESE VALVES ARE ONLY | | REQUIRED TO CLOSE IN ORDER TO ISOLATE A SENSING LINE FAILURE OR LOSS OF | | PRESSURE BOUNDARY IN THE TRANSMITTER. THE SEVEN INSTALLED RELAYS WILL BE | | REPLACED AT THE EARLIEST OPPORTUNITY FOLLOWING PROCUREMENT OF REPLACEMENTS. | | THE SEVEN INSTALLED P&B MDR RELAYS AT SONGS REMAIN OPERABLE AT THIS TIME | | BASED ON POSITIVE DEDICATION TESTING RESPONSE, SYSTEM DESIGN USE, | | SUCCESSFUL INSTALLATION POST-MAINTENANCE TESTING, AND PAST OPERATING | | EXPERIENCE WITH OTHER RELAYS USED IN THIS TYPE APPLICATION. | | | | THE HOO FORWARDED THE PART 21 NOTIFICATION TO VERN HODGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29097 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/21/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 23:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/21/95 | +------------------------------------------------+EVENT TIME: 19:33[EDT]| |NRC NOTIFIED BY: SCHALL |LAST UPDATE DATE: 07/21/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS RDO | |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 +------------------------------------------------------------------------------+ | A SECOND HALF SCRAM WAS RECEIVED AFTER RETURNING THE 'B' RPS BUS BACK TO | | THE NORMAL POWER SUPPLY. (REFER TO SIMILAR EVENT NUMBER 29095.) | | | | AT 1933 EDT ON 7/21/95, UNIT 1 RECEIVED A SECOND DIVISION II RPS TRIP. | | THIS RESULTED IN A DIVISION II HALF SCRAM AND HALF GROUP 1 SIGNAL AS WELL | | AS DIVISION II GROUP 2, 3, AND 6 ISOLATION SIGNALS. ADDITIONALLY, A | | SECONDARY CONTAINMENT ISOLATION AND STANDBY GAS TREATMENT SYSTEM START | | OCCURRED AS EXPECTED. ALL REQUIRED AUTOMATIC ACTIONS AND ISOLATIONS WERE | | VERIFIED TO HAVE OCCURRED. THIS EVENT IS SIMILAR TO THE EVENT REPORTED | | PREVIOUSLY TODAY (REFER TO EVENT NUMBER 29095), AND THE SAME VALVES CLOSED | | THAT WERE REPORTED EARLIER. | | | | THE 'B' RPS BUS WAS TRANSFERRED BACK TO ITS NORMAL SUPPLY AT 1653 | | FOLLOWING THE ORIGINAL TRIP AS IT WAS DEEMED THE MORE STABLE POWER SUPPLY. | | THE LICENSEE HAS AGAIN TRANSFERRED RPS BUS 'B' TO ITS ALTERNATE SUPPLY | | (FROM EMERGENCY BUS E6). THE HALF GROUP ONE AND HALF REACTOR SCRAM HAVE | | BEEN RESET. TROUBLESHOOTING IS CONTINUING TO DETERMINE THE CAUSE WITH THE | | LICENSEE INVESTIGATING A POSSIBLE PROBLEM WITH AN ELECTRICAL PROTECTION | | ASSEMBLY BREAKER (EPA-4). | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29098 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 07/23/95 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 21:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/23/95 | +------------------------------------------------+EVENT TIME: 18:04[EDT]| |NRC NOTIFIED BY: CHESNUT |LAST UPDATE DATE: 07/23/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |EDWARD BUTCHER EO | |ANLI 50.72(b)(1)(iii) LIGHTNING | | | |BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DUAL UNIT TRIPS ON MAIN GENERATOR TRIPS DUE TO A LIGHTNING STRIKE IN THE | | VICINITY OF THE TURBINE BUILDING. | | | | AT 1804 EDT ON 7/23/95, VOGTLE UNITS 1 AND 2 AUTOMATICALLY TRIPPED. THE | | REACTOR TRIPS WERE DUE TO GENERATOR/TURBINE TRIPS WHICH OCCURRED DURING A | | THUNDERSTORM. LIGHTNING WAS OBSERVED TO STRIKE NEAR THE TURBINE BUILDING | | AT THE TIME OF THE TRIPS. NO DAMAGE TO PLANT EQUIPMENT HAS BEEN OBSERVED | | AS A RESULT OF THE LIGHTNING STRIKES. | | | | THE POST-TRIP RESPONSE OF BOTH UNITS WAS NORMAL. MAIN STEAM SAFETY VALVES | | DID NOT LIFT. AUXILIARY FEEDWATER SYSTEMS ACTUATED AS EXPECTED. ALL RODS | | FULLY INSERTED AT BOTH UNITS. OFFSITE POWER WAS NOT LOST, AND ALL DIESEL | | GENERATORS ARE OPERABLE. THERE WERE NO ELECTRICAL BUSES LOST AS A RESULT | | OF THE TRANSIENT. ALL ECCSs ARE OPERABLE IN STANDBY. GRID STABILITY IS | | GOOD, AND THE THUNDERSTORMS HAVE PASSED THROUGH THE AREA. | | | | AN INVESTIGATION CONTINUES TO DETERMINE THE CAUSE OF THE GENERATOR TRIPS. | | REACTOR RESTARTS ARE PENDING RESULTS OF THE INVESTIGATION AND EVENT | | CRITIQUES. THE LICENSEE IS TENTATIVELY PLANNING TO RESTART UNIT 2 AROUND | | MIDNIGHT, AND UNIT 1 TOMORROW. UNIT 1 WILL BE REPLACING AN INTERMEDIATE | | RANGE DETECTOR (NI-36). | | | | THE RESIDENT INSPECTORS HAVE BEEN INFORMED AND ARE ON SITE. | +------------------------------------------------------------------------------+