U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/27/95 - 09/28/95 ** EVENT NUMBERS ** 28841 29378 29379 29380 29381 29382 29383 29384 29385 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28841 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/22/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 16:51 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/25/95 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: COOK |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BJ HOLT RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | |VERN HODGE RVIB | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 INTERIM REPORT NO. 21-95-010: ELGAR INVERTER PULSE WIDTH | | MODULATOR (PWM) DRIVE LOGIC CARD (J4) FAILURE. | | | | ON MARCH 24, 1995, THE LICENSEE INSTALLED A NEW PWM DRIVE LOGIC CARD IN THE | | DIVISION 2 NUCLEAR SYSTEMS PROTECTION SYSTEM (NSPS) INVERTER, AND IT FAILED | | AFTER 4 TO 6 HOURS OF OPERATION DURING CALIBRATION OF THE INVERTER. THE | | INVERTER WAS OUT OF SERVICE AT THE TIME OF THE FAILURE IN ORDER TO | | FACILITATE THE REPLACEMENT OF THE LOGIC CARD WITH A REVISED CARD IN | | ACCORDANCE WITH A SCHEDULED MAINTENANCE ACTIVITY. THE LICENSEE DOES NOT | | KNOW THE CAUSE OF THE FAILURE, BUT HAS RETURNED THE LOGIC CARD TO THE | | SUPPLIER FOR FAILURE ANALYSIS. THE LICENSEE DETERMINED THAT THE FAILURE | | WAS A CONDITION POTENTIALLY REPORTABLE UNDER THE PROVISIONS OF 10 CFR PART | | 21 ON MARCH 25, 1995, AND EXPECTS TO COMPLETE THE EVALUATION OF THIS ISSUE | | BY JUNE 30, 1995. | | | | THE BASIC COMPONENT INVOLVED WAS A PWM DRIVE LOGIC CARD (PART NUMBER NO. | | 642-108-40, REVISION F) WHICH WAS MANUFACTURED BY ELGAR CORPORATION AND | | SUPPLIED TO THE LICENSEE BY ELGAR CORPORATION/GENERAL ELECTRIC. THIS LOGIC | | CARD WAS INSTALLED IN THE DIVISION 2 NSPS INVERTER WHICH PROVIDES 120-VOLT | | AC UNINTERRUPTIBLE POWER TO LOADS SUCH AS NSPS LOGIC POWER, NEUTRON | | MONITORING, PROCESS RADIATION MONITORING, PORTIONS OF THE LEAK DETECTION | | SYSTEM, NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM VALVES, AND LOSS OF COOLANT | | ACCIDENT BYPASS RELAYS DURING ALL MODES OF OPERATION, INCLUDING ABNORMAL | | AND ACCIDENT CONDITIONS. THE LOGIC CARD ALSO PROVIDES CONTROL SIGNALS TO | | THE SILICON CONTROLLED RECTIFIER DRIVES. THE SAME LOGIC CARD CAN BE | | UTILIZED IN THE DIVISION 1, 2, 3, AND 4 NSPS INVERTERS, BUT THE REVISED | | CARD WAS NEVER INSTALLED IN THE DIVISION 3 OR 4 NSPS INVERTERS. ANOTHER | | NO. 642-108-40, REVISION F, LOGIC CARD WAS IDENTIFIED AS DEFICIENT WHEN IT | | WAS INITIALLY INSTALLED IN THE DIVISION 1 NSPS INVERTER DURING A SIMILAR | | MAINTENANCE ACTIVITY. THE SILICON CONTROLLED RECTIFIER DRIVE SECTION | | OPERATION WOULD NOT FUNCTION, AND THE DIVISION 1 NSPS INVERTER WOULD NOT | | OPERATE. BOTH OF THE FAILED LOGIC CARDS WERE RETURNED TO ELGAR CORPORATION | | FOR FAILURE ANALYSIS. | | | | THE FAILURE OF THIS LOGIC CARD CAUSES THE INVERTER TO SHUT DOWN. WHEN THIS | | OCCURS, THE INVERTER LOADS ARE TRANSFERRED TO THE ALTERNATE AC SOURCE OF | | POWER. IF THE LOGIC CARD HAD FAILED DURING A LOSS OF OFFSITE POWER | | CONDITION, THE NUCLEAR SYSTEMS PROTECTION SYSTEM LOADS WOULD BE TRANSFERRED | | TO AN ALTERNATE AC POWER SOURCE WHICH MAY NOT BE AVAILABLE DUE TO THE LOSS | | OF OFFSITE POWER CONDITION, AND THE NUCLEAR SYSTEMS PROTECTION SYSTEM COULD | | LOSE POWER. | | | | THE LICENSEE HAS NO INFORMATION ABOUT LOGIC CARDS THAT MAY HAVE BEEN | | SUPPLIED TO OTHER PURCHASERS. | | | | * * * UPDATE AT 1033 ON 9/27/95 FAXED NOTIFICATION RECEIVED BY WEAVER * * * | | | | ILLINOIS POWER ISSUED A FINAL REPORT ON THIS SUBJECT. ADDITIONAL TESTING | | YIELDED INCONCLUSIVE RESULTS. FUTURE SUCCESS PATHS ON THE SUBJECT ARE | | DISCUSSED. THE HOO NOTIFIED VERN HODGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29378 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/27/95 | |UNIT: [ ] [ ] [3] STATE: AZ |NOTIFICATION TIME: 02:03 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/26/95 | +------------------------------------------------+EVENT TIME: 18:00[MST]| |NRC NOTIFIED BY: JEAN-MARC L'EPLATTENIER |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR POWER EXCEEDED 100% BECAUSE OF A VALVE LINEUP PROBLEM | | | | A PROCEDURAL ERROR RESULTED IN A VALVE MISALIGNMENT WHICH ISOLATED THE | | ABNORMAL BLOWDOWN VALVES INTO THE BLOWDOWN FLASH TANK. THIS CONDITION | | AFFECTS THE INPUTS INTO THE COLSS COMPUTER PROGRAM AND CAUSES INDICATED | | POWER TO BE LESS THAN ACTUAL POWER. THIS IS CAUSED BY ACTUAL BLOWDOWN FLOW | | BEING LESS THAN INDICATED FLOW AND ACTUAL FEEDWATER FLOW BEING GREATER THAN | | INDICATED FEEDWATER FLOW. | | | | UPON DISCOVERY OF THIS CONDITION, REACTOR POWER WAS REDUCED TO ENSURE THAT | | THE 12-HOUR JSCALOR-H ROLLING AVERAGE CALCULATION REMAINED BELOW 100%. A | | TEST AND CALCULATION WAS MADE TO DETERMINE THE MAGNITUDE OF THE OVERPOWER | | CONDITION. THE TEST DEMONSTRATED THAT THE 100% POWER LIMIT WAS EXCEEDED BY | | A SMALL FRACTION OF A PERCENT (0.11%). THIS CONDITION EXISTED FROM 23:00 | | ON 9/23 TO 08:00 ON 9/24. THE TIME DELAY IN REPORTING WAS USED TO | | DETERMINE THE SIGNIFICANCE OF THIS EVENT. | | | | AS A RESULT OF THIS EVENT, THE BLOWDOWN PROCEDURE WAS CHANGED, AND A NIGHT | | ORDER WAS ISSUED IN ALL THREE UNITS. THE INVESTIGATION INTO THIS EVENT IS | | ONGOING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29379 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 09/27/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 08:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/27/95 | +------------------------------------------------+EVENT TIME: 08:24[EDT]| |NRC NOTIFIED BY: ANDREW WISNIEWSKI |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFF ANDERSON RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EMERGENCY OFFSITE SIRENS INOPERABLE. | | | | AT 08:24 EDT LICENSEE WAS NOTIFIED BY THEIR CONTRACTOR (JPS) THAT THEIR | | NOAA (NATIONAL OCEANOGRAPHIC ATMOSPHERIC ADMINISTRATION) TRANSMITTER WAS | | INOPERABLE. THIS TRANSMITTER IS USED TO INITIATE THEIR EMERGENCY OFFSITE | | SIRENS. LICENSEE DID NOT KNOW WHAT WAS WRONG WITH THE TRANSMITTER. | | CONTRACTOR (JPS) IS CURRENTLY WORKING ON REPAIRING THE TRANSMITTER. | | LICENSEE HAS TO NOTIFY LOCAL OFFICIALS AND THE STATES OF VERMONT, NEW | | HAMPSHIRE, AND MASSACHUSETTS OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29380 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/27/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 10:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/27/95 | +------------------------------------------------+EVENT TIME: 09:23[EDT]| |NRC NOTIFIED BY: MIKE CASHION |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP IN RESPONSE TO THE CLOSURE OF THE "A" MSIV | | | | WITH UNIT 1 @ 100% POWER, THE "A" STEAM GENERATOR MSIV CLOSED. OPERATORS | | MANUALLY TRIPPED THE PLANT IN ANTICIPATION OF THE AUTOMATIC TRIP ON LOW | | STEAM GENERATOR LEVEL. ALL RODS FULLY INSERTED. AUXILIARY FEEDWATER | | STARTED AND RESTORED STEAM GENERATOR LEVELS. THE "B" MOTOR-DRIVEN AFW PUMP | | DID NOT START BECAUSE THE "B" CHANNEL OF THE SOLID STATE PROTECTION SYSTEM | | (SSPS) WAS IN TEST AT THE TIME OF THE TRIP. ALL OTHER EQUIPMENT RESPONDED | | AS EXPECTED. | | | | THE PLANT IS STABLE IN HOT STANDBY. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER AS NECESSARY TO REMOVE DECAY HEAT. THE CAUSE OF THE MSIV CLOSURE | | IS UNDER INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29381 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/27/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:25 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/27/95 | +------------------------------------------------+EVENT TIME: 09:50[CDT]| |NRC NOTIFIED BY: TERRY RATZLAFF |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |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 89 POWER OPERATION | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE STATE OF NEBRASKA DEPARTMENT OF ENVIRONMENTAL | | QUALITY OF A GLYCOL SPILL IN THE FACILITY'S ADMINISTRATIVE BUILDING. | | | | A GLYCOL SPILL (SPILL NUMBER 092795-GY-0950) OCCURRED AT 10:20 CDT ON | | SEPTEMBER 26, 1995, DURING THE REPLACEMENT OF GLYCOL IN THE ADMINISTRATIVE | | BUILDING CHILLED WATER SYSTEM. APPROXIMATELY TWO GALLONS OF GLYCOL WAS | | RELEASED TO THE PLANT'S SEWER SYSTEM WITH THE REMAINDER (APPROXIMATELY | | THIRTY GALLONS) CONTAINED IN THE ADMINISTRATIVE BUILDING. THERE WERE NO | | PERSONNEL CONTAMINATIONS AS A RESULT OF THIS INCIDENT. | | | | THE LICENSEE REPORTED THIS SPILL TO THE STATE OF NEBRASKA DEPARTMENT OF | | ENVIRONMENTAL QUALITY AT 09:50 CDT ON SEPTEMBER 27, 1995, AND THE LICENSEE | | PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29382 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/27/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/26/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: TOM SILKO |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT REACTOR BUILDING NEGATIVE PRESSURE WAS | | TEMPORARILY LOST WHICH RESULTED IN AN ADVERSE CONDITION CONTRARY TO THE | | FSAR. | | | | CONTRARY TO THE FSAR, REACTOR BUILDING NEGATIVE PRESSURE WAS TEMPORARILY | | LOST DUE TO A NORMAL REACTOR BUILDING VENTILATION DAMPER PROBLEM. (THE | | CAUSE OF THE DAMPER PROBLEM IS STILL UNDER INVESTIGATION.) REACTOR | | BUILDING PRESSURE IS NOT A MONITORED PARAMETER, AND THE SLIGHTLY POSITIVE | | REACTOR BUILDING PRESSURE WAS DISCOVERED AT APPROXIMATELY 14:00 ON | | SEPTEMBER 26, 1995. AS A RESULT, STANDBY GAS TREATMENT WAS PLACED IN | | SERVICE IN ORDER TO IMMEDIATELY RESTORE THE NEGATIVE REACTOR BUILDING | | PRESSURE. NORMAL REACTOR BUILDING VENTILATION (WHICH IS NON-SAFETY | | RELATED) WAS SUBSEQUENTLY RE-BALANCED AND RESTORED AT APPROXIMATELY 19:00. | | SECONDARY CONTAINMENT INTEGRITY AND STANDBY GAS TREATMENT (WHICH ARE BOTH | | SAFETY RELATED) REMAINED FULLY OPERABLE THROUGHOUT THIS EVENT, AND NO | | TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION WERE ENTERED. IN | | ORDER TO ENSURE OPERABILITY OF THE SAFETY-RELATED SYSTEMS THAT WERE | | CREDITED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT, THE LICENSEE | | SATISFACTORILY PERFORMED A SECONDARY CONTAINMENT TIGHTNESS TEST. IN THE | | EVENT OF AN ACCIDENT, THE LICENSEE BELIEVES THAT STANDBY GAS TREATMENT | | WOULD HAVE INITIATED AND THAT REACTOR BUILDING NEGATIVE PRESSURE WOULD HAVE | | BEEN MAINTAINED IN ACCORDANCE WITH THE DESIGN AND ACCIDENT ANALYSIS. THE | | EVENT CLASSIFICATION WAS DETERMINED AT 16:45 ON SEPTEMBER 27, 1995, WHEN | | THE LICENSEE DETERMINED THAT THIS SITUATION WAS CONTRARY TO THE FSAR WHICH | | STATES THAT THE NORMAL REACTOR BUILDING VENTILATION SYSTEM WOULD MAINTAIN A | | SLIGHTLY NEGATIVE REACTOR BUILDING DIFFERENTIAL PRESSURE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE OF | | CONNECTICUT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29383 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 09/27/95 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 17:53 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/11/95 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: PHIL CRONE |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |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 | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED, FOLLOWING THE PERFORMANCE OF A CONTROL ROOM | | VENTILATION SYSTEM SELF ASSESSMENT, THAT THE PLANT COULD EXCEED THE GENERAL | | DESIGN CRITERIA LIMIT FOR POST-ACCIDENT THYROID DOSE TO CONTROL ROOM | | OPERATORS. | | | | THE LICENSEE DETERMINED THAT THE CALIBRATION OF THE HUMIDISTATS (WHICH | | FUNCTION TO ACTUATE CONTROL ROOM PRESSURIZATION UNIT HEATERS IN THE EVENT | | THAT THE HUMIDITY OF THE OUTSIDE AIR DRAWN BY THE UNIT RISES ABOVE 70%) HAS | | NOT BEEN MAINTAINED. THE EFFECT OF HUMIDITY GREATER THAN 70% IS THE | | REDUCTION OF THE IODINE REMOVAL EFFICIENCY OF THE CHARCOAL FILTER AND A | | RESULTING INCREASE IN THYROID DOSE. WITH THE HUMIDISTATS INOPERABLE, THE | | LICENSEE WAS UNABLE TO DEMONSTRATE THAT THE POSTULATED ACCIDENT DOSE TO THE | | CONTROL ROOM OPERATORS WOULD BE LESS THAN 30 REM TO THE THYROID. WHEN THE | | NEED TO CALIBRATE THE HUMIDISTATS WAS QUESTIONED DURING THE SELF ASSESSMENT | | ON AUGUST 11, 1995, THE HAND SWITCHES FOR THE HEATERS WERE PLACED IN THE | | TEST POSITION IN ORDER TO MAINTAIN THE HEATERS ENERGIZED UNTIL THE | | OPERABILITY OF THE HUMIDISTATS COULD BE DETERMINED. ON SEPTEMBER 9 AND 26, | | 1995, RESPECTIVELY, THE LICENSEE DETERMINED THAT NEITHER THE 'A' OR 'B' | | TRAIN HUMIDISTATS WERE OPERABLE. AS A RESULT, THE LICENSEE PLANS TO KEEP | | THE HEATERS ENERGIZED (WHEN THE REQUIRED EQUIPMENT IS OPERABLE) UNTIL THE | | HUMIDISTATS ARE RETURNED TO SERVICE. AT 16:50 CDT ON SEPTEMBER 27, 1995, | | THE LICENSEE DETERMINED THAT THIS THIS EVENT WAS REPORTABLE BUT WILL | | RESCIND THE NOTIFICATION IF IT IS LATER DETERMINED NOT TO BE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29384 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 09/27/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:46 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 09/27/95 | +------------------------------------------------+EVENT TIME: 18:30[EDT]| |NRC NOTIFIED BY: WALT NEUMAN |LAST UPDATE DATE: 09/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |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 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF INCONSISTENT PROCEDURAL GUIDANCE TO PREVENT CROSS-TYING BOTH | | ONCE-THROUGH STEAM GENERATORS THROUGH THE BLOWDOWN LINE WHICH COULD DEFEAT | | MAIN STEAM LINE ISOLATION | | | | ON SEPTEMBER 27, 1995, PROCEDURAL GUIDANCE TO PREVENT CROSS-TYING BOTH | | ONCE-THROUGH STEAM GENERATORS THROUGH THE BLOWDOWN LINE WAS DISCOVERED TO | | BE INCONSISTENT IN SEVERAL OPERATING PROCEDURES. THIS LED TO A SITUATION | | WHERE BLOWDOWN CROSS-TIE COULD DEFEAT MAIN STEAM LINE ISOLATION. THE | | BLOWDOWN ISOLATION VALVES ARE NORMALLY CLOSED, BUT THEY ARE NOT ON THE MAIN | | STEAM LINE ISOLATION AUTOMATIC CLOSURE MATRIX. THIS CONDITION WAS | | DISCOVERED AS PART OF AN ONGOING ENGINEERING REVIEW. THE LICENSEE HAS | | INSTITUTED TEMPORARY GUIDANCE TO PRECLUDE THIS EVENT FROM OCCURRING. SINCE | | THE VALVES ARE CURRENTLY CLOSED, THERE IS NO SAFETY SIGNIFICANCE TO THIS | | EVENT AT THIS TIME. AT THE TIME OF THE NOTIFICATION, THE LICENSEE DID NOT | | KNOW HOW LONG THESE PROCEDURAL INCONSISTENCIES HAD BEEN IN PLACE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29385 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 09/28/95 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 01:39 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/28/95 | +------------------------------------------------+EVENT TIME: 00:06[CDT]| |NRC NOTIFIED BY: BILL ARENS |LAST UPDATE DATE: 09/28/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POWER TEMPORARILY LOST TO THE ONSITE EOF | | | | POWER WAS LOST TO THE ONSITE EOF WHILE TRANSFERRING THE POWER SUPPLY FOR | | THE EOF. THE SOURCE OF POWER TO THE EOF WAS BEING TRANSFERRED FROM THE | | UNIT AUX TRANSFORMER TO THE STARTUP TRANSFORMER WHEN POWER WAS LOST AT | | 0006. POWER WAS RESTORED AT 0030 WHEN THE SUPPLY WAS SHIFTED BACK TO THE | | UNIT AUX TRANSFORMER. | | | | THE ALTERNATE EOF, LOCATED OFFSITE, WAS NOT AFFECTED. THE REASON FOR THE | | LOSS OF POWER IS STILL UNDER INVESTIGATION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+