U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/28/96 - 02/29/96 ** EVENT NUMBERS ** 30031 30038 30039 30040 30041 30042 30043 30044 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30031 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 02/27/96 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 01:59 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 02/27/96 | +------------------------------------------------+EVENT TIME: 01:00[EST]| |NRC NOTIFIED BY: GREENE |LAST UPDATE DATE: 02/28/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LESSER 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VOLTAGE REGULATOR SETTING AT KEOWEE HYDROELECTRIC STATION FOUND TO BE TOO | | LOW | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "FIELD STUDIES HAVE REVEALED THAT IF CERTAIN DESIGN BASIS EVENTS HAD | | OCCURRED IN THE PAST, THE OUTPUT OF THE KEOWEE HYDRO UNITS MAY NOT HAVE | | BEEN SUFFICIENT TO ENSURE PROPER OPERATION OF CERTAIN SAFETY-RELATED LOADS. | | THE ACTUAL SETTING OF THE VOLTAGE REGULATOR ON THE KEOWEE HYDRO UNIT TIED | | TO THE UNDERGROUND POWER PATH WAS MEASURED AT 11.9 kV. THIS REGULATOR WAS | | SUBSEQUENTLY RECALIBRATED TO 13.5 kV TO ELIMINATE THIS PROBLEM. FURTHER | | STUDIES WILL BE CONDUCTED TO VERIFY THE RESULTS OF THIS LOWER VOLTAGE ON | | SAFETY-RELATED COMPONENTS. THIS NOTIFICATION MAY BE RETRACTED IN THE | | FUTURE DEPENDING ON THE RESULTS OF THESE STUDIES. THIS NOTIFICATION | | CONCERNS PAST OPERABILITY ONLY." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT. | | | | * * * UPDATE AT 1632 ON 02/28/96 BY MIKE BAILEY ENTERED BY JOLLIFFE * * * | | | | THE FOLLOWING IS A CLARIFICATION OF THE ABOVE REPORT: | | | | THE VOLTAGE REGULATOR LOWER LIMIT SETTING AT THE KEOWEE HYDROELECTRIC | | STATION WAS FOUND TO BE TOO LOW. THE ACTUAL LOWER LIMIT SETTING OF THE | | VOLTAGE REGULATOR ON THE KEOWEE HYDRO UNIT TIED TO THE UNDERGROUND POWER | | PATH WAS MEASURED AT 11.9 kV. THE LOWER LIMIT SETTING OF THIS VOLTAGE | | REGULATOR WAS SUBSEQUENTLY RECALIBRATED TO 13.5 kV TO ELIMINATE THIS | | PROBLEM. | | | | THE FOLLOWING IS AN ELABORATION OF THIS REPORT: | | | | WHILE PERFORMING A VOLTAGE REGULATOR FAILURE ANALYSIS (#KC-2028), LICENSEE | | DETERMINED THAT A POSTULATED FAILURE IN THE KEOWEE VOLTAGE REGULATOR COULD | | CAUSE IT TO BE DRIVEN TO ITS LOWER LIMIT. THE LIMITS FOR THIS TYPE OF | | VOLTAGE REGULATOR ARE TYPICALLY SET FOR +/-15% OF NORMAL GENERATOR VOLTAGE | | (13.8 kV); THUS, VOLTAGE ON THE GENERATOR COULD DROP TO AS LOW AS 11.7 kV. | | SINCE THE ACTUAL SETTING FOR THE LOWER LIMIT WAS UNKNOWN, LICENSEE | | PERFORMED A TEST TO DETERMINE THE ACTUAL LOWER LIMIT SETTING ON THE VOLTAGE | | REGULATOR. THE TEST INDICATED THAT THE KEOWEE UNDERGROUND POWER PATH | | VOLTAGE REGULATOR HAD A LOWER LIMIT SETTING OF 11.9 kV. | | | | AT THE PRESENT TIME, THE KEOWEE UNDERGROUND POWER PATH IS OPERABLE DUE TO | | THE RECALIBRATION OF ITS VOLTAGE REGULATOR LOWER LIMIT SETTING OF 13.5 kV. | | | | LICENSEE IS STILL EVALUATING THE ACTUAL IMPACT OF THE POTENTIAL LOWER | | VOLTAGES ON THE ASSOCIATED LOADS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R2DO DOUG COLLINS. | | | | NOTE: SEE EVENT #30030 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30038 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 02/28/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 11:02 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/28/96 | +------------------------------------------------+EVENT TIME: 08:05[EST]| |NRC NOTIFIED BY: ROBERT VINCENT |LAST UPDATE DATE: 02/28/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - RELEASE OF SULFURIC ACID TO LAKE MICHIGAN | | | | THE LICENSEE REPORTED A RELEASE OF SULFURIC ACID TO THE NATIONAL RESPONSE | | CENTER AND LOCAL COUNTY OFFICIALS. THEY HAVE RELEASED 15,000 GALLONS OF | | SULFURIC ACID WITH A PH OF 1.4. THE ACID IS DILUTED IN THE MIXING BASIN | | BEFORE BEING RELEASED TO THE LAKE, SO NO ENVIRONMENTAL EFFECTS ARE | | EXPECTED. THE ACID IS STILL BEING RELEASED AT A RATE OF 50 GALLONS PER | | HOUR. THE ACID IS LEAKING FROM THE WASTE NEUTRALIZATION TANK FROM AN | | UNKNOWN LOCATION. | | | | THE LICENSEE PLANS TO RAISE THE PH OF THE CONTENTS OF THE WASTE | | NEUTRALIZATION TANK TO THE BAND NECESSARY FOR A BATCH RELEASE (A PH OF | | BETWEEN 2 AND 12), AND THEN RELEASE THE CONTENTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. A PRESS RELEASE WILL BE | | MADE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30039 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 02/28/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/28/96 | +------------------------------------------------+EVENT TIME: 09:30[EST]| |NRC NOTIFIED BY: ART ZAREMBA |LAST UPDATE DATE: 02/28/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |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 +------------------------------------------------------------------------------+ | SAFETY RELIEF VALVE PILOT SOLENOID LINES CONTAIN DEBRIS | | | | DURING A WALKDOWN OF THE DRYWELL, AN OPERATOR NOTED AN "AIR" LEAK ON THE | | "G" SRV PILOT SOLENOID VALVE. TROUBLESHOOTING LED TO THE DISCOVERY OF | | MINUTE DEBRIS FROM THE EXHAUST PORT OF THE PILOT VALVE. FURTHER INSPECTION | | OF THE REMAINING 10 PILOT VALVES REVEALED DEBRIS IN THE SUPPLY LINES TO | | FOUR OTHER VALVES. THE DEBRIS WAS CHARACTERIZED AS DARK, METALLIC AND VERY | | SMALL. | | | | THE LICENSEE ALSO DISCOVERED THAT ONE PILOT VALVE WOULD NOT OPERATE FROM | | THE CONTROL ROOM AND TWO OTHERS WOULD NOT OPERATE FROM THE REMOTE PANEL. IN | | EACH OF THESE THREE CASES THE VALVES WERE OPERABLE FROM AT LEAST ONE | | LOCATION. THESE FAILURES WOULD NOT HAVE PREVENTED THE SAFETY FUNCTION OF | | THE SRVs. TWO OF THE THREE VALVES ARE PART OF THE AUTOMATIC | | DEPRESSURIZATION SYSTEM. IT IS NOT KNOWN WHETHER THE FAILURE OF THESE | | THREE PILOT VALVES TO OPERATE IS ASSOCIATED WITH THE DEBRIS PROBLEM | | MENTIONED ABOVE. | | | | THE LICENSEE'S CORRECTIVE ACTIONS ARE UNDER DEVELOPMENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30040 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 02/28/96 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 12:35 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 02/28/96 | +------------------------------------------------+EVENT TIME: 12:02[EST]| |NRC NOTIFIED BY: GORDEN CREMER |LAST UPDATE DATE: 02/28/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |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 | 95 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PARTIAL LOSS OF OFFSITE POWER TO UNITS 2 & 3 FOR UNKNOWN REASONS - | | | | AT 1202, UNITS 2 & 3 LOST 1 OF 2 OFFSITE STARTUP POWER CIRCUITS (#343) FOR | | UNKNOWN REASONS. THIS CAUSED THE LOSS OF 1 OF 3 REACTOR FEEDWATER HEATER | | STRINGS ON EACH UNIT. CONTROL ROOM OPERATORS COMPENSATED FOR THIS BY | | REDUCING POWER FROM 100% TO 95% ON UNIT 2 AND FROM 100% TO 92% ON UNIT 3. | | THE UNIT 2/3 COMMON CONTROL ROOM EMERGENCY VENTILATION SYSTEM AUTO ACTUATED | | ON LOW AIR FLOW AND THE PRIMARY CONTAINMENT ISOLATION SYSTEM ON BOTH UNITS | | HALF ISOLATED. | | | | THIS EVENT HAD NO EFFECT ON THE ELECTRICAL GRID AND NO PERSONNEL WERE | | INJURED. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE PARTIAL LOSS OF OFFSITE POWER. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30041 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/28/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/28/96 | +------------------------------------------------+EVENT TIME: 14:40[EST]| |NRC NOTIFIED BY: MIKE BIGIARELLI |LAST UPDATE DATE: 02/28/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNIT 1 REACTOR VESSEL HEATUP & COOLDOWN CYCLES EXCEEDED UFSAR LIMIT - | | | | UNIT 1 IS IN CONDITION 5 IN A REFUELING OUTAGE WITH THE CORE OFFLOADED TO | | THE SPENT FUEL POOL. | | | | THE MILLSTONE UNIT 1 UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) LIMITS | | THE UNIT 1 REACTOR VESSEL TO 120 HEATUP AND COOLDOWN CYCLES OVER THE LIFE | | OF THE VESSEL. LICENSEE DETERMINED THAT THIS NUMBER HAS BEEN EXCEEDED. | | THIS PLACES THE UNIT 1 REACTOR VESSEL IN AN UNANALYZED CONDITION. | | LICENSEE IS ANALYZING THIS CONDITION. | | | | UNIT 1 IS SCHEDULED TO RESTART IN JULY, 1996. | | | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30042 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DR PHILLIP J. W. LEE, MD |NOTIFICATION DATE: 02/28/96 | | CITY: HONOLULU REGION: 4 |NOTIFICATION TIME: 17:03 [ET]| | COUNTY: STATE: HI |EVENT DATE: 02/28/96 | |LICENSE#: 53-04935-01 AGREEMENT: N |EVENT TIME: 11:00[AH ]| | DOCKET: |LAST UPDATE DATE: 02/28/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DR PHILLIP J. W. LEE, MD | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MEDICAL MISADMINISTRATION: 20% BETA OVERDOSE TO 16 PATIENTS - | | | | BETWEEN MAY AND OCTOBER 1995, DR PHILLIP J. W. LEE MEDICALLY TREATED | | 16 PATIENTS WITH A SR-90 BETA APPLICATOR. THESE TREATMENTS WERE POST | | OPERATIVE PTERYGIUM BETA RADIATION TREATMENTS FOR A GROWTH ON THE EYE. | | | | ON 11/15/95, DURING A REGION 4 INSPECTION OF DR LEE'S MEDICAL ACTIVITIES, | | THE REGION 4 INSPECTOR CALCULATED THAT THE DOSES ADMINISTERED TO THE | | PATIENTS WERE HIGHER THAN INTENDED. | | | | ON 01/18/96, A CALIBRATION LAB CONFIRMED THAT DR LEE'S EQUIPMENT HAD BEEN | | ADMINISTERING A DOSE AVERAGING 20% HIGHER THAN INTENDED. | | | | DR LEE HAS BEEN IN CONTACT WITH THE REGION 4 INSPECTOR, EMILIO GARCIA, | | REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30043 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 02/28/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 22:44 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 02/28/96 | +------------------------------------------------+EVENT TIME: 21:03[EST]| |NRC NOTIFIED BY: DAN GREEN |LAST UPDATE DATE: 02/28/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO REACTOR TRIP FROM 100% POWER DUE TO LOSS OF MAIN FEEDWATER - | | | | UNIT 1 EXPERIENCED ERRATIC SIGNALS FEEDING THE REACTOR Tave CONTROL SYSTEM | | FOR UNKNOWN REASONS. CONTROL ROOM OPERATORS TOOK MANUAL CONTROL OF THE | | INTEGRATED CONTROL CIRCUITS IN AN EFFORT TO STABILIZE THE SYSTEM. THIS | | EFFORT WAS UNSUCCESSFUL. | | | | UNIT 1 AUTO TRIPPED FROM 100% POWER DUE TO A LOSS OF MAIN FEEDWATER SIGNAL. | | ALL CONTROL RODS INSERTED COMPLETELY. 16 OF 16 MAIN STEAM RELIEF VALVES | | LIFTED AND RESEATED PROPERLY, AS EXPECTED. STEAM IS BEING DUMPED TO THE | | MAIN CONDENSER. THE EMERGENCY FEEDWATER SYSTEM AUTO STARTED, AS EXPECTED. | | UNIT 1 IS STABLE IN MODE 3 (HOT STANDBY). | | | | NO TESTING OR MAINTENANCE ACTIVITIES WERE BEING CONDUCTED AT THE TIME OF | | THE TRIP AND WEATHER CONDITIONS WERE NORMAL. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE ERRATIC SIGNALS. | | | | UNITS 2 AND 3 WHICH ARE EACH AT 100% POWER WERE UNAFFECTED BY THIS EVENT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 02/29/96 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 05:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 02/29/96 | +------------------------------------------------+EVENT TIME: 01:58[CST]| |NRC NOTIFIED BY: ROGERS |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McALPINE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAMMED ON HIGH APRM FLUX. LICENSEE INVESTIGATING MALFUNCTION OF | | THEIR ELECTRO-HYDRAULIC CONTROL (EHC) SYSTEM. | | | | REACTOR SCRAMMED ON APRM HIGH FLUX DUE TO A MALFUNCTION OF THE EHC SYSTEM. | | ALL RODS FULLY INSERTED INTO THE CORE. LICENSEE DOES NOT KNOW WHAT CAUSED | | THE APRM HIGH FLUX SCRAM SIGNAL BUT THEY BELIEVE THEY HAD SOME TYPE OF | | MALFUNCTION OF THEIR EHC SYSTEM. LICENSEE DID NOT KNOW IF A MAIN TURBINE | | CONTROL VALVE PARTIALLY CLOSED WHICH COULD HAVE CAUSED REACTOR VESSEL | | PRESSURE TO INCREASE TO CAUSE THE APRM HIGH FLUX SCRAM. NO SAFETY RELIEF | | VALVES OPENED. LICENSEE MANUALLY TRIPPED THEIR MAIN TURBINE PER PROCEDURE | | AT 50 MWe TO PREVENT A REVERSE POWER TRIP. THE LICENSEE RECEIVED THE | | FOLLOWING AUTOMATIC ISOLATIONS: GROUP 2 (DRYWELL FLOOR AND EQUIPMENT | | DRAIN), GROUP 3 (REACTOR WATER CLEANUP), GROUP 6 (PRIMARY & SECONDARY | | CONTAINMENT VENTILATION), AND GROUP 8 (TIPs WHICH WAS ALREADY ISOLATED). | | REACTOR VESSEL WATER LEVEL DID NOT GET LOW ENOUGH TO CAUSE HPCI AND RCIC TO | | AUTOMATICALLY START. ALL SYSTEMS OPERATED AS EXPECTED. NO TESTING OR | | MAINTENANCE WAS IN PROGRESS WHEN THE REACTOR SCRAMMED. LICENSEE IS | | INVESTIGATING WHAT CAUSED THE REACTOR SCRAM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+