U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/23/98 - 10/26/98 ** EVENT NUMBERS ** 34951 34952 34953 34954 34955 34956 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34951 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 10/23/98 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 10:10 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 10/22/98 | +------------------------------------------------+EVENT TIME: 13:54[EDT]| |NRC NOTIFIED BY: JOHN NEAL |LAST UPDATE DATE: 10/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 24-HOUR FITNESS FOR DUTY REPORT | | | | A NON-LICENSED SUPERVISOR WAS DETERMINED TO BE UNDER THE INFLUENCE OF | | ALCOHOL DURING A FOR-CAUSE TEST. THE EMPLOYEE'S ACCESS TO THE PLANT HAS | | BEEN TERMINATED. REFER TO THE HOO LOG FOR DETAILS. | | | | THE NRC RESIDENT WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34952 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/23/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 14:37 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/23/98 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 10/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 +------------------------------------------------------------------------------+ | FAILURE OF LOCAL EMERGENCY DIESEL GENERATOR PANEL TO FUNCTION AS DESIGNED | | | | WHILE PERFORMING FUNCTIONAL TESTS OF THE PLANT'S APPENDIX R LOCAL SHUTDOWN | | PANELS, THE LICENSEE DISCOVERED THAT THE LOCAL EMERGENCY DIESEL GENERATOR | | (EDG) PANEL WOULD NOT FUNCTION AS DESIGNED. WHEN SIMULATING A LOSS OF THE | | CONTROL ROOM CIRCUITRY, THE EDG COULD NOT BE STARTED BECAUSE OF A WIRING | | DEFICIENCY: THERE IS A WIRE IN THE WRONG PLACE DEENERGIZING THE CIRCUIT. | | THERE HAVE BEEN SOME CHANGES IN THE TESTING METHODOLOGY AND THIS CONDITION | | MAY NOT HAVE BEEN TESTED BEFORE; HOWEVER, THE INVESTIGATION IS ONGOING. THE | | PLANT IS CURRENTLY IN REFUELING OUTAGE AND THE NECESSARY MODIFICATIONS WILL | | BE COMPLETED PRIOR TO RESTART. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34953 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/23/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:42 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/23/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:00[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/23/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MIKE JORDAN RDO | | DOCKET: 0707001 |FREDERICK COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY SYSTEM ACTUATION DUE TO CONTROLLER FAILURE | | | | A SAFETY SYSTEM ACTUATION OCCURRED IN THE C-333-A FACILITY. AUTOCLAVE | | 4-SOUTH WAS FEEDING A UF6 CYLINDER WHEN A STEAM PRESSURE CONTROLLER PROBLEM | | ALLOWED THE STEAM PRESSURE INSIDE THE AUTOCLAVE TO REACH THE SAFETY SYSTEM | | TRIP SETTING. THE SAFETY SYSTEM PERFORMED AS DESIGNED AND PLACED THE | | AUTOCLAVE IN A SAFE CONDITION. THE STEAM PRESSURE CONTROL AND HIGH PRESSURE | | ISOLATION SAFETY SYSTEMS AND THE UF6 CYLINDER WERE DECLARED INOPERABLE. THE | | AUTOCLAVE WAS PLACED IN MODE 2 AS REQUIRED BY TSR 2.2.3.3. | | | | THIS IS A 24-HOUR REPORT IN ACCORDANCE WITH SAFETY ANALYSIS REPORT TABLE | | 6.9.1, CRITERION J.2 AS AN ACTUATION OF A SAFETY SYSTEM IN RESPONSE TO A | | VALID SIGNAL. THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34954 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 10/23/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 22:44 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 10/23/98 | +------------------------------------------------+EVENT TIME: 20:39[EDT]| |NRC NOTIFIED BY: KEN PACE |LAST UPDATE DATE: 10/23/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 90 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP ON TURBINE GOVERNOR VALVE CONTROLLER FAILURE | | | | DURING A PLANNED REACTOR SHUTDOWN TO ENTER REFUELING OUTAGE, THE TURBINE | | GENERATOR GOVERNOR VALVE CONTROLLER FAILED CAUSING ALL FOUR GOVERNOR VALVES | | TO GO FULL OPEN. REACTOR POWER INCREASED FROM ABOUT 85% TO 90% PRIOR TO | | THE REACTOR TRIP. THE CAUSE OF THE FAILURE IS UNKNOWN AND AN INVESTIGATION | | IS ONGOING. THE PROBLEM WILL BE CORRECTED PRIOR TO REACTOR STARTUP. THE | | REACTOR TRIP PROCEEDED NORMALLY WITH THE EXCEPTION THAT THE 'A' AND 'B' | | MAIN FEEDWATER REGULATING VALVES DID NOT GO FULL SHUT, STOPPING AT ABOUT | | 10% OPEN. AUXILIARY FEEDWATER STARTED ON LOW STEAM GENERATOR LEVEL AS | | EXPECTED ON THE REACTOR TRIP. THE PLANT IS IN NORMAL SHUTDOWN OPERATION IN | | FORCED CIRCULATION, WITH NORMAL FEEDWATER AND HEAT REMOVAL VIA THE STEAM | | GENERATORS AND STEAM DUMPS TO THE MAIN CONDENSER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34955 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 10/25/98 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 13:38 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 10/25/98 | +------------------------------------------------+EVENT TIME: 10:50[EST]| |NRC NOTIFIED BY: JIM KOVALCHICK |LAST UPDATE DATE: 10/25/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP III ISOLATION DURING TESTING | | | | DURING PLANNED MAINTENANCE, I & C TECHNICIANS WERE PERFORMING TRIP TESTING | | OF THE E-32 BUS OVERCURRENT RELAYS FOR THE UNIT 2 4KV EMERGENCY BUS. | | HOWEVER, THE E-33 BUS (UNIT 3 4KV EMERGENCY BUS) WAS LOCKED OUT INSTEAD. | | THE UNIT 3 'A' REACTOR PROTECTION SYSTEM (RPS) MOTOR GENERATOR SET SLOWED | | AND THE OUTPUT AUTOMATICALLY TRIPPED DEENERGIZING THE '3A' RPS BUS. A HALF | | RPS SCRAM AND A HALF GROUP I PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) | | ISOLATION SIGNAL OCCURRED. AN INBOARD GROUP III PCIS ISOLATION OCCURRED | | AFFECTING UNIT 3 REACTOR BUILDING VENTILATION, CONTAINMENT O2 MONITORING, | | DRYWELL ATMOSPHERE RADIATION MONITORING, AND THE INSTRUMENT N2 COMPRESSOR | | SUCTION LINE. BECAUSE THE 'C' STANDBY GAS FAN WAS DEENERGIZED BY THE LOSS | | OF THE E-33 BUS, THE UNIT 2 REACTOR OPERATOR MANUALLY ISOLATED UNIT 2 | | DRYWELL VENTILATION AND STARTED THE 'B' STANDBY GAS TREATMENT FAN, IN | | ANTICIPATION OF AN AUTOMATIC ISOLATION. | | | | THE E-33 BUS WAS REENERGIZED AND ALL PROTECTIVE SIGNALS HAVE BEEN RESET AND | | ALL AFFECTED SYSTEMS HAVE BEEN RETURNED TO NORMAL. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34956 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/25/98 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 14:43 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/25/98 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 10/25/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |NINF INFORMATION ONLY |STUART RICHARDS EO | | |LARRY NICOLSON, R1 IAT | | |JOHN DAVIDSON, NMSS IAT | | |RICHARD ROSANO, NRR IAT | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANNED TAX PROTEST HELD IN FRONT OF FACILITY | | | | AT ABOUT 2:OO PM, A DEMONSTRATION WAS HELD IN FRONT OF THE GATES OF THE | | INDIAN POINT 2 NUCLEAR POWER PLANT AS PART OF A PROTEST CONCERNING A | | PROPOSED TAX WRITE-OFF FOR THE CONSOLIDATED EDISON COMPANY THAT IS INCLUDED | | ON THE NOVEMBER BALLOT. THE DEMONSTRATION, ATTENDED BY ABOUT 800 PEOPLE, | | WAS PEACEFUL AND LASTED APPROXIMATELY 30 MINUTES. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+