U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/21/95 - 06/22/95 ** EVENT NUMBERS ** 28968 28972 28973 28974 28975 28976 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28968 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/20/95 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 06/20/95 | +------------------------------------------------+EVENT TIME: 18:03[EDT]| |NRC NOTIFIED BY: MARTIN ARNOLD |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STEVEN VARGA EO | |NLCO TECH SPEC LCO A/S |BELCHER FEMA | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 0 STARTUP | 0 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED AND TERMINATED AT 1803 EDT DUE TO REACTOR COOLANT SYSTEM | | LEAKAGE IN EXCESS OF 50 GALLONS PER MINUTE DUE TO A FAILED CHARGING PUMP | | RELIEF VALVE. | | | | AT 1735 EDT A CHARGING PUMP RELIEF VALVE WENT FULLY OPEN CAUSING A REACTOR | | COOLANT LEAK OF 75 GALLONS PER MINUTE. AT 1750 EDT THE LEAK WAS STOPPED BY | | ISOLATING PUMP "A". ABOUT 1125 GALLONS OF PRIMARY COOLANT WERE RELEASED | | VIA THE 3/4 INCH RELIEF LINE TO A DRAIN TO A LIQUID RAD WASTE HOLD UP TANK. | | PRESSURIZER LEVEL FLUCTUATED SLIGHTLY (BETWEEN 10 TO 15%) BUT WAS | | CONTROLLED WITH ADDITIONAL CHARGING FROM PUMPS "B" AND "C" AND BY REDUCING | | LETDOWN. THE LEAK EXCEEDED THE TECH SPEC 3.1.5.1 LIMIT OF 1 GALLON PER | | MINUTE. | | | | THE PLANT WAS IN THE PROCESS OF RESTART FOLLOWING A REFUELING OUTAGE. | | CONSEQUENTLY ACTIVITY WAS LOW. GROSS ACTIVITY WAS MEASURED AT 1.15 EXP -3 | | MICRO-CURIES PER CUBIC CENTIMETER DUE TO MIXED NUCLIDES. NO PERSONNEL WERE | | EXPOSED. | | | | THE LICENSEE WILL REPAIR OR REPLACE THE FAILED VALVE AND CONTINUE WITH | | PLANT RESTART. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE STATE AND THREE | | LOCAL COUNTY WARNING POINTS. | | | | ** UPDATE @ 0917 EDT ON 6/21/95 ***FROM LICENSEE: DORMAN BY:McGINTY ** | | THE LICENSEE PROVIDED A FOLLOWUP NOTIFICATION TO SPECIFY THAT A PRESS | | RELEASE REGARDING THE EVENT HAD BEEN ISSUED AT ABOUT 2000 EDT ON 6/20/95. | | THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR. HOO NOTIFIED THE R2DO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28972 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 06/21/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 09:44 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 09:31[EDT]| |NRC NOTIFIED BY: BROWN |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 +------------------------------------------------------------------------------+ | NON-PLANT WORKERS ESTABLISHED A PICKET LINE ON PLANT ACCESS ROAD. | | | | THE LICENSEE REPORTED THAT COMPENSATORY MEASURES HAVE BEEN IMPLEMENTED DUE | | TO NON-PLANT WORKERS ESTABLISHING A PICKET LINE ON THE PLANTS ACCESS ROAD. | | THE PICKET LINE, HOWEVER, IS BEING OBSERVED BY SOME OF THE UNION PLANT | | WORKERS, AND TELEVISION NEWS MEDIA HAVE ARRIVED AT THE PICKET LINE. THE | | LICENSEE HAS IMPLEMENTED THE NORMAL STRIKE CONTINGENCY PLAN, WHICH INCLUDES | | RE-ARRANGING SCHEDULES AND PERSONNEL TO COVER THE POSITIONS NORMALLY | | OCCUPIED BY THE PEOPLE WHO WILL NOT CROSS THE LINE. THE LICENSEE HAS | | INFORMED THE RESIDENT INSPECTOR, AND MAY ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28973 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: INDIANA DOT |NOTIFICATION DATE: 06/21/95 | | CITY: REGION: 3 |NOTIFICATION TIME: 11:45 [ET]| | COUNTY: VIGO STATE: IN |EVENT DATE: 06/20/95 | |LICENSE#: 13-26344-01 AGREEMENT: N |EVENT TIME: 18:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/21/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DONALD FINE | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BBBB 20.403 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INDIANA DOT - STOLEN TROXLER GAUGE | | | | THE INDIANA DEPARTMENT OF TRANSPORTATION REPORTED A MODEL 3440 TROXLER | | GAUGE STOLEN. THE GAUGE CONTAINS 8 mCi OF Cs-137 AND 40 mCi OF Am 241. | | THE GAUGE WAS STOLEN SOMETIME BETWEEN 3:00 PM ON JUNE 20TH AND 7:00 AM ON | | JUNE 21ST. | | | | THE LICENSEE FILED A REPORT WITH THE INDIANA STATE POLICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28974 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 06/21/95 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 12:06 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 01:38[EDT]| |NRC NOTIFIED BY: GLENN DISHONG |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 81 POWER OPERATION | 81 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED AT 1130 EDT THAT A DESIGN ERROR IN A MOD COMMON TO | | TWO EMERGENCY DIESEL GENERATORS (EDG) PLACED THE PLANTS OUTSIDE OF THEIR | | DESIGN BASIS. | | | | EDG "E4" WAS OUT OF SERVICE FOR MAINTENANCE AND FOR INSTALLATION OF A | | MODIFICATION. EDG "E2" HAD THE SAME MOD INSTALLED ON 6/4/95. AT 0138 EDT | | THE LICENSEE DETERMINED THAT A DESIGN PROBLEM WITH THE MOD WOULD PREVENT | | AUTO CLOSURE OF THE EDG OUTPUT CIRCUIT BREAKERS UPON LOSS OF POWER TO THEIR | | RESPECTIVE EMERGENCY LOAD CENTERS. CONSEQUENTLY THE "E2" EDG WAS DECLARED | | INOPERABLE AT 0138 EDT. THE SIMULTANEOUS INOPERABILITY OF THE "E2" AND | | "E4" EDGs IS NOT PART OF THE DESIGN BASIS. | | | | THE DESIGN ERROR WAS CORRECTED AND THE "E2" EDG WAS DECLARED OPERABLE AT | | 0250 EDT ON 6/21/95. MAINTENANCE AND MOD WORK IS CONTINUING ON THE "E4" | | EDG. WITH ONE EDG OUT OF SERVICE THE LICENSEE IS IN A SEVEN DAY LCO PER | | TECH SPEC 3.9.B.3. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28975 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 06/21/95 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 21:59 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 20:02[CDT]| |NRC NOTIFIED BY: JIM HUEBNER |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP DUE TO LOW LEVEL IN ONE STEAM GENERATOR. | | | | WHILE PREPARING TO INITIATE AUXILIARY FEEDWATER FLOW FOR MAKE UP TO THE | | STEAM GENERATORS DURING UNIT HEAT UP, A REACTOR TRIP OCCURRED BECAUSE OF | | LOW WATER LEVEL IN ONE STEAM GENERATOR. ALL CONTROL RODS (SHUTDOWN BANKS) | | FULLY INSERTED. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28976 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/21/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 23:36 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/21/95 | +------------------------------------------------+EVENT TIME: 23:03[EDT]| |NRC NOTIFIED BY: WILLIAM SPAHN |LAST UPDATE DATE: 06/21/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 REPORTED THAT DESIGN DISCREPANCIES HAVE THE POTENTIAL TO | | PREVENT THE FULFILLMENT OF THE SAFETY FUNCTION OF THE SECONDARY CONTAINMENT | | AIR TREATMENT SYSTEM. | | | | THE LICENSEE HAS DETERMINED THAT DURING SBGT (STANDBY GAS TREATMENT) | | OPERATION WITH SUBSEQUENT FAILURE OF THE OTHER SBGT TRAIN CONCURRENT WITH | | THE LOSS OF NON-QA INSTRUMENT AIR, RECIRCULATION THROUGH THE IDLE SBGT | | FILTER TRAIN VIA FAIL OPEN ON LOSS OF AIR VALVES COULD POTENTIALLY RESULT | | IN THE INABILITY TO MAINTAIN SAFETY TECH SPEC REQUIRED NEGATIVE PRESSURE IN | | SECONDARY CONTAINMENT. THE CONDITION IS APPARENTLY THE RESULT OF A POOR | | ORIGINAL DESIGN CHARACTERISTIC. | | | | FOR THIS POTENTIAL "WINDMILLING" PROBLEM, THE LICENSEE HAS DECLARED BOTH | | SBGT TRAINS INOPERABLE (@ 2200 EDT), AND HAS 24 HOURS TO RETURN ONE TRAIN | | TO OPERATION OR TO BE SHUTDOWN PER T/S SECTION 3.7.B. THE LICENSEE | | ANTICIPATES RETURNING ONE SBGT TRAIN TO SERVICE, THUS ENTERING A 7 DAY LCO, | | AND WILL INITIATE THE PROCESS OF TAGGING OUT AND ISOLATING ONE OF THE SBGT | | TRAINS. THE LICENSEE WILL BE PERFORMING A SPECIAL TEST IN THE NEW | | ALIGNMENT TO CONFIRM THAT SECONDARY CONTAINMENT REQUIREMENTS ARE MET. | | | | ADDITIONALLY, THE LICENSEE HAS ALSO EVALUATED T/S LCO 3.7.B.6, WHICH | | REQUIRES THAT "PRIMARY CONTAINMENT SHALL BE PURGED THROUGH THE SBGT SYSTEM | | AT ALL TIMES WHEN PRIMARY CONTAINMENT IS REQUIRED". THIS ALIGNMENT | | REQUIREMENT COULD POTENTIALLY CHALLENGE THE OPERABILITY (STRUCTURAL/LEAKAGE | | INTEGRITY) OF BOTH TRAINS OF THE SBGT FILTER HOUSING (FABRICATED OF SHEET | | METAL) IF LOCA TORUS/DRYWELL PRESSURE CONDITIONS OF APPROXIMATELY 45 PSIG | | WERE EXPERIENCED COINCIDENTALLY WITH PURGING/VENTING OPERATIONS. | | | | FOR THIS CONCERN, THE LICENSEE WILL RESTRICT VENTING OF PRIMARY CONTAINMENT | | TO THE SGTS AS A CORRECTIVE ACTION. THE LICENSEE WILL ALSO BE EVALUATING | | THE ABILITY TO ISOLATE A POSTULATED DEGRADED SBGT TRAIN AFTER RECEIPT OF A | | GROUP 2 ISOLATION (PRIMARY CONTAINMENT PRESSURE > 2.0 PSI) SIGNAL, AND THE | | POTENTIAL FOR DEGRADATION TO THE RESERVE SGTS FILTER HOUSING IF A LOCA WERE | | EXPERIENCED. | | | | THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR, AND HAS NOTIFIED STATE AND | | LOCAL AUTHORITIES. LONG TERM CORRECTIVE ACTIONS FOR THE PROBLEMS ARE BEING | | EVALUATED. | +------------------------------------------------------------------------------+