U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/13/95 - 04/14/95 ** EVENT NUMBERS ** 28595 28674 28675 28676 28677 28678 28679 28680 28681 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28595 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 03/27/95 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 19:08 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/27/95 | +------------------------------------------------+EVENT TIME: 17:52[CST]| |NRC NOTIFIED BY: WILLIAM ARENS |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IT WAS DISCOVERED THAT A NON-LICENSED CONTRACT EMPLOYEE HAD A PRIOR | | CRIMINAL RECORD. | | | | THE INDIVIDUAL WAS GIVEN TEMPORARY ACCESS TO THE VITAL AND PROTECTED AREA | | ON 2/28/95. TODAY THE LICENSEE RECEIVED INFORMATION FROM THE FBI CRIMINAL | | HISTORY CHECK THAT THIS INDIVIDUAL HAD A PRIOR CRIMINAL RECORD AND HAD | | SPENT 1 YEAR AND 1 DAY IN JAIL. THE INDIVIDUAL HAD INDICATED TO THE | | LICENSEE THAT HE HAD NO PRIOR CRIMINAL RECORD. THE INDIVIDUAL'S ACCESS HAS | | BEEN REVOKED. SEE HOO LOG FOR ADDITIONAL DETAILS. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | ***UPDATE ON 4/13/95 @ 14:47 BY CROWNE TO GOULD*** THIS EVENT WAS DISCUSSED | | WITH SECURITY PERSONNEL IN THE REGION AND SAFEGUARDS BRANCH IN NRR, AND IT | | WAS DETERMINED THAT THE EVENT IS ONLY A LOGGABLE EVENT AND SHOULD NOT HAVE | | BEEN REPORTED AS A 1HR 73.71 EVENT. THE LICENSEE IS THEREFORE RETRACTING | | THIS EVENT. THE RI HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28674 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 04/13/95 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 03:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/12/95 | +------------------------------------------------+EVENT TIME: 23:46[CDT]| |NRC NOTIFIED BY: JOHN CRAIN |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - AUTO START OF THE "C" TRAIN COMPONENT COOLING WATER PUMP | | | | THE "C" TRAIN CCW PUMP AUTOMATICALLY STARTED WHILE SECURING THE "A" | | ESSENTIAL COOLING WATER (ECW) PUMP. THE INITIAL PUMP LINE UP WAS AS | | FOLLOWS. THE "B" CCW PUMP AND ALL THREE ECW PUMPS WERE RUNNING. THE PLANT | | SECURED THE "A" ECW PUMP TO REDUCE THE NUMBER OF RUNNING ECW PUMPS TO THE | | TYPICAL NUMBER OF TWO. FIFTEEN SECONDS AFTER THE "A" ECW PUMP WAS SECURED, | | THE "C" CCW PUMP STARTED. | | | | CCW PUMPS HAVE TWO AUTOMATIC START SIGNALS. CCW COMMON HEADER PRESSURE | | LESS THAN 76 PSIG OR PRESSURE LESS THAN 35 PSIG IN THE TWO OPPOSITE ECW | | TRAINS. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE PUMP START. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28675 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/13/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 13:37 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/13/95 | +------------------------------------------------+EVENT TIME: 09:00[CDT]| |NRC NOTIFIED BY: HARRINGTON |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THROUGH EDDY CURRENT TESTING RESULTS THAT MORE | | THAN 1% OF THE STEAM GENERATOR TUBES INSPECTED ARE DEFECTIVE. | | | | THIS PLACES BOTH "A" & "B" STEAM GENERATORS IN THE "C-3" CLASSIFICATION PER | | THEIR TS. A DEFECTIVE TUBE IS ANY TUBE WITH AN INDICATION BELIEVED TO BE | | MORE THAN 50% THROUGH WALL. IN THE "B" STEAM GENERATOR 220 OF 2084 TUBES | | INSPECTED IN THE AREA OF THE UPPER EXPANSION JOINT OF THE SLEEVES WERE | | DETERMINED TO BE DEFECTIVE. IN STEAM GENERATOR "A" 26 OF 315 TUBES | | INSPECTED WERE DETERMINED TO BE DEFECTIVE IN THE TUBE SHEET CREVICE REGION. | | THE CORRECTIVE ACTIONS TO BE TAKEN ARE; | | 1. THE ORIGINAL 20% SAMPLE INSPECTION OF THE "B" STEAM GENERATOR SLEEVES | | HAS BEEN EXPANDED TO 100% OF THE SLEEVED TUBES. | | 2. THE INSPECTION SCOPE WILL NOT HAVE TO BE EXPANDED SINCE 100% OF THE | | TUBES WILL BE INSPECTED AS PER THE ORIGINAL INSPECTION PLAN. | | 3. THOSE TUBES DETERMINED TO BE DEFECTIVE WILL BE PLUGGED. | | 4. ANALYSES WILL BE PERFORMED TO DETERMINE PLUGGING IMPACT ON ACCIDENT | | ANALYSES AND ENSURE PLUGGING RATE DOES NOT RESULT IN AN UNANALYZED | | CONDITION. | | | | THE RI HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28676 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/13/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/13/95 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: BOOTH |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KELLY RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THE SIGHTING OF AN OIL SHEEN IN THEIR DISCHARGE CANAL | | AND THE HUDSON RIVER TO THE NATIONAL RESPONSE CENTER, COAST GUARD, AND THE | | N.Y. DEPT OF ENVIRONMENTAL CONSERVATION. | | | | THE LICENSEE NOTICED APPROXIMATELY 1 GAL. OF OIL RUNOFF IN THEIR DISCHARGE | | CANAL AND ALSO APPROXIMATELY A 1.5' DIA SHEEN IN THE HUDSON RIVER. THEY ARE | | INVESTIGATING THE SOURCE OF THE OIL. THEY HAVE PUT OUT BOOMS TO CAPTURE THE | | OIL. THE RI HAS ALSO BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28677 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/13/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/13/95 | +------------------------------------------------+EVENT TIME: 14:35[EDT]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KELLY 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 83 POWER OPERATION | 83 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DISCOVERED THAT THE LOGIC SYSTEM FOR THE FEEDWATER COOLANT | | INJECTION SYSTEM IS OUTSIDE THE DESIGN BASIS. | | | | THE FEEDWATER COOLANT INJECTION SYSTEM WAS FOUND TO HAVE BOTH S1 AND S2 | | CONTACTS IN THE LOSS OF NORMAL POWER LOGIC. SINCE IT HAS ONE CONTACT FROM | | EACH SAFETY RELATED SECTION, THEY DETERMINED THAT ANOTHER FAILURE MECHANISM | | FOR THIS LOGIC EXISTED BECAUSE THEY WERE NOT PREVIOUSLY AWARE THAT AN S2 | | CONTACT WAS BEING USED ON THE LOGIC FOR THIS SYSTEM. THEY ARE INVESTIGATING | | THE DESIGN BASIS TO DETERMINE WHY AN S2 CONTACT WAS INSTALLED. AN | | EVALUATION WILL BE MADE AND THEY MAY POSSIBLY REMOVE THE S2 CONTACT. THEY | | PERFORMED AN OPERABILITY DETERMINATION ON THE FEEDWATER COOLANT INJECTION | | SYSTEM AND VERIFIED THAT THE SYSTEM WAS OPERABLE. THE RI, STATE AND LOCAL | | AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28678 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/13/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/13/95 | +------------------------------------------------+EVENT TIME: 13:55[CDT]| |NRC NOTIFIED BY: CONNER |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |COLLINS 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 STARTUP | 0 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN OIL LINE WHICH SUPPLIED HYDRAULIC FLUID TO REACTOR COOLANT SYSTEM (RCS) | | SNUBBERS WAS FOUND TO BE SUSCEPTIBLE TO DAMAGE DURING A SEISMIC EVENT. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "DURING THE 1995 REFUELING OUTAGE, IT WAS DISCOVERED THAT THERE WERE | | SEISMIC SUPPORTS MISSING ON THE TUBING THAT RUNS BETWEEN THE OIL RESERVOIRS | | AND THE SEISMIC SNUBBERS ON RC-3B AND RC-3D REACTOR COOLANT PUMP MOTORS. | | ANALYSIS SHOWS THAT THE REACTOR COOLANT SYSTEM (RCS) PIPING MEETS STRESS | | ALLOWABLES WITHOUT THE SNUBBERS. HOWEVER, THE SNUBBERS ARE INSTALLED TO | | PROTECT RCS CONNECTED PIPING SUCH AS CHEMICAL VOLUME CONTROL SYSTEM AND | | SAFETY INJECTION PIPING. THE RCS CONNECTED PIPING WOULD BE OVER STRESSED | | BY THE INCREASED DISPLACEMENT OF THE RCS DURING AN EARTHQUAKE IF THE | | SNUBBERS WERE NOT OPERABLE. THE LOSS OF OIL FROM THE SNUBBERS IF THE | | TUBING WERE TO FAIL DURING A SEISMIC EVENT WOULD PREVENT THE SNUBBERS FROM | | LOCKING UP DURING THE SEISMIC EVENT AND THUS NOT PERFORM THEIR DESIGN | | FUNCTION. SUPPORTS HAVE BEEN PLACED ON THE TUBING SUCH THAT INTERIM SEISMIC | | OPERABILITY CRITERION IS MET AND THE SNUBBERS ARE OPERABLE. THE EVENT WAS | | DISCOVERED AND REPAIRED WHILE THE PLANT WAS IN MODE 4." END OF TEXT. | | | | AN ENGINEERING ANALYSIS DETERMINED THAT AN OIL LINE FROM A REMOTE RESERVOIR | | TO THE SNUBBERS SUPPORTING THE RCS AND SUPPORT-SYSTEM PIPING (LIKE THE CVCS | | PIPING) MAY BE SUSCEPTIBLE TO DAMAGE DURING A SEISMIC EVENT. WHILE THE RCS | | PIPING WOULD NOT EXCEED ALLOWABLE STRESS LEVELS, THE SUPPORT-SYSTEM PIPING | | WOULD EXCEED THOSE STRESS LEVELS. THIS CONDITION RESULTED FROM MISSING OIL | | LINE SUPPORTS. ADDITIONAL SUPPORTS HAVE BEEN PLACED ON THE OIL LINES TO | | ALLEVIATE THIS CONDITION. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28679 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/13/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:38 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/13/95 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: BILLESBACH |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT THE PREVIOUS CONFIGURATION OF THE RHR MINIMUM | | FLOW VALVES COULD NOT MEET THE DESIGN BASIS REQUIREMENTS FOR POSSIBLE | | ACCIDENTS. | | | | THE FOLLOWING IS THE TEXT FROM THE LICENSEE'S FAX: | | "WHILE CLOSING OUT A DESIGN CHANGE PACKAGE THAT CHANGED THE NORMAL POSITION | | OF THE RHR SYSTEM MINIMUM FLOW VALVES(RHR-MOV-MO16A & B) FROM CLOSED TO | | OPEN, IT WAS DISCOVERED THAT UNDER THE OLD CONFIGURATION(CLOSED), THE PLANT | | COULD NOT MEET THE DESIGN BASIS REQUIREMENTS FOR POSSIBLE ACCIDENTS. | | | | PRIOR TO THE DESIGN CHANGE, THE RHR MINIMUM FLOW VALVE WAS NORMALLY CLOSED | | AND OPENED WHEN THE PUMP DEVELOPED FLOW OF >2500 GPM PLUS A 10 SECOND TIME | | DELAY. IN THE EVENT OF A LOCA WITH A SINGLE FAILURE OF ONE ESSENTIAL | | ELECTRICAL DIVISION, A SITUATION COULD RESULT WHERE ONE LPCI LOOP IS | | INJECTING INTO THE BROKEN LOOP AND THE OTHER LPCI LOOP IS QUESTIONABLE | | BECAUSE THE RHR MIN FLOW VALVE REMAINS CLOSED . IN THIS CONDITION IT IS | | POSSIBLE THAT NONE OF THE RHR PUMPS WOULD BE INJECTING INTO THE CORE. | | | | THE CONCERN IS THAT THE PUMP VENDOR WILL ONLY STATE THAT THE RHR PUMPS WILL | | NOT SUFFER ANY IMMEDIATE DAMAGE RESULTING FROM RUNNING DEAD HEADED FOR UP | | TO 20 SECONDS. THEREFORE, IF THE MIN FLOW VALVE FAILS TO OPEN, THE RHR | | PUMPS MUST BE CAPABLE OF INJECTING INTO THE VESSEL IN 20 SECONDS AFTER THE | | PUMPS ARE AT SPEED, TO PREVENT PUMP DAMAGE DUE TO DEAD HEADING. | | | | THE ACCIDENTS THAT WOULD AFFECT THE RHR PUMPS INJECTION TIME, ARE THOSE | | ASSOCIATED WITH <100% LOCA'S. TWO POSSIBILITIES PRESENT THEMSELVES AS | | CHALLENGING THE DESIGN BASIS, THESE ARE 1) A LOCA WITH CONCURRENT LOSS OF | | OFF-SITE POWER(ALSO LOSS OF ESSENTIAL ELECTRICAL DIVISION EXISTS), AND 2) A | | LOCA WITHOUT A CONCURRENT "LOOP"(ALSO LOSS OF ESSENTIAL ELECTRICAL DIVISION | | EXISTS). OF THESE TWO, THE LATER SCENARIO, LOCA W/O "LOOP" IS MORE | | THREATENING IN THAT THE RHR PUMP DOES NOT HAVE TO WAIT FOR LOAD SHEDDING TO | | OCCUR AND WILL REACH FULL SPEED SOONER, INCREASING THE TIME THE PUMP CAN | | RUN DEAD HEADED. IN BOTH SCENARIOS, THERE WERE TWO POSSIBLE RHR INJECTION | | TIMES, 100% AND 80% BREAKS. TIME FOR RHR INJECTION @100% IS APPROX 26 | | SECONDS, AND TIME FOR INJECTION @ 80% IS APPROX 43 SECONDS. TIME TO | | INJECTION IS THE TIME IT TAKES FOR THE VESSEL PRESSURE TO DROP BELOW ABOUT | | 300 PSIG. | | | | IN THE LOCA WITH "LOOP" IT TAKES THE RHR PUMP APPROX 33 SECONDS TO GET TO | | SPEED, THEREFORE THE EARLIEST A DEAD HEADING CONCERN BECOMES PRESENT IS AT | | APPROX 53 SECONDS. THEREFORE, BY INTERPOLATION, THE LARGEST BREAK WHERE | | PUMP DAMAGE COULD OCCUR IS AT 68%, WHICH IS STILL ABOVE THE CAPABILITY OF | | THE REMAINING CORE SPRAY PUMP. BASED ON THIS DATA, THE ECCS RESPONSE TO | | THIS ACCIDENT SCENARIO IS MARGINAL AS TO WHETHER IT MEETS ITS DESIGN BASIS. | | | | THE LOCA W/O "LOOP" IS THE MORE SEVERE CASE IN THAT THE TIME DELAY FOR THE | | RHR PUMP TO BE AT SPEED IS SIGNIFICANTLY REDUCED. THIS TIME IS NOW 13 | | SECONDS, SO THEREFORE THE EARLIEST DEAD HEADING CONCERN IS AT ABOUT 33 | | SECONDS. THIS IS LESS THAN THE GE CALCULATED TIME WHEN RHR CAN INJECT INTO | | THE VESSEL, WHICH MEANS THAT THE AVAILABILITY OF THE RHR PUMP, FOR AN 80% | | BREAK IN THIS SCENARIO, CANNOT BE GUARANTEED. | | | | THE CURRENT CONFIGURATION OF THE RHR MIN FLOW VALVE BEING OPEN, PREVENTS | | DEAD HEADING AND POSSIBLE DAMAGE TO THE RHR PUMPS DURING ACCIDENT | | CONDITIONS." | | | | THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28680 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/13/95 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 17:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/13/95 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: BAIN |LAST UPDATE DATE: 04/13/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NORTH CAROLINA DIVISION OF ENVIRONMENTAL | | MANAGEMENT OF A POSITIVE INDICATION OF TRITIUM IN WATER SAMPLES. | | | | THE N.C. DIVISION OF ENVIRONMENTAL MANAGEMENT WAS NOTIFIED, PER AGREEMENT, | | OF CONFIRMED POSITIVE INDICATION OF TRITIUM IN WATER SAMPLES OBTAINED FROM | | A MONITORING WELL IN THE EXCLUSION AREA OF THE BRUNSWICK SITE. GROUND WATER | | SAMPLING WAS BEING PERFORMED IN ACCORDANCE WITH A SITE ASSESSMENT PLAN | | IMPLEMENTED AS A RESULT OF TESTING AND REPAIRS MADE TO THE UNIT 2 RADWASTE | | EFFLUENT LINE IN MAY '94. REPAIRS TO THE RADWASTE EFFLUENT LINE WERE | | COMPLETED ON 6/2/94. THERE IS NO EVIDENCE OF A LEAK IN THE LINE SINCE THE | | COMPLETION OF THE REPAIR. THERE IS NO SAFETY SIGNIFICANCE FOR THE EVENT. | | THE LEVEL OF ACTIVITY DETECTED IS MINIMAL AND DOES NOT PRESENT A THREAT TO | | THE ENVIRONMENT OR TO THE HEALTH AND SAFETY OF THE PUBLIC OR ON-SITE | | PERSONNEL. THE RI WAS ALSO NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28681 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 04/14/95 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 05:44 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/14/95 | +------------------------------------------------+EVENT TIME: 05:10[EDT]| |NRC NOTIFIED BY: BLESS |LAST UPDATE DATE: 04/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BRIAN SHERON EO | | |AUSTIN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED - FIRE IN THE AUX BUILDING VENTILATION SYSTEM | | | | A FIRE WAS REPORTED IN THE AUXILIARY BUILDING VENTILATION SYSTEM AT 0510. | | THE FIRE WAS ATTACKED IMMEDIATELY WITH PORTABLE CO2 EXTINGUISHERS. SEVERAL | | MINUTES LATER A FIRE HOSE WAS BROUGHT TO THE SCENE AND THE FIRE WAS | | DECLARED OUT AT 0529. THE UNUSUAL EVENT WAS DECLARED AT 0528. | | | | THE FIRE WAS CAUSED BY WELDING IN THE TURBINE BUILDING ON THE 12' LEVEL. | | THE FIRE WAS IN AN EXPANSION JOINT OF THE AUX BUILDING VENTILATION SYSTEM | | ON THE 5' LEVEL. THIS PART OF THE VENTILATION SYSTEM IS AT THE BOUNDARY OF | | THE TURBINE BUILDING AND THE AUX BUILDING. THE FIRE WAS OVERHAULED AT 0544 | | AND THE UNUSUAL EVENT WAS TERMINATED AT 0555. | | | | THE LICENSEE NOTIFIED THE THREE SURROUNDING COUNTIES AND THE MARYLAND STATE | | POLICE. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+