U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/03/97 - 01/06/97 ** EVENT NUMBERS ** 31537 31538 31539 31540 31541 31542 31543 31544 31545 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31537 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 01/03/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 08:25 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/02/97 | +------------------------------------------------+EVENT TIME: 14:30[CST]| |NRC NOTIFIED BY: DON GRISSETTE |LAST UPDATE DATE: 01/03/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSITIVE RANDOM FITNESS-FOR-DUTY TEST | | | | A LICENSED SENIOR REACTOR OPERATOR TESTED POSITIVE FOR MARIJUANA DURING A | | RANDOM FITNESS-FOR-DUTY TEST. THE INDIVIDUAL WAS REMOVED FROM DUTY AND HAS | | BEEN REFERRED TO AN EMPLOYEE'S ASSISTANCE PROGRAM. THE INDIVIDUAL'S SITE | | ACCESS HAS ALSO BEEN SUSPENDED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO | | LOG FOR A LICENSEE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31538 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/03/97 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 13:12 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 01/03/97 | +------------------------------------------------+EVENT TIME: 12:20[EST]| |NRC NOTIFIED BY: SECKENS |LAST UPDATE DATE: 01/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 | | 2 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE STATE REGARDING EXCEEDANCE OF DISCHARGE PERMIT LIMIT | | | | ON 01/03/97, THE LICENSEE NOTIFIED THE MARYLAND STATE DEPARTMENT OF THE | | ENVIRONMENT THAT A PLANT DISCHARGE ON 12/16/96 EXCEEDED THE STATE LIMITS | | FOR FECAL COLIFORM. THE RESULTS OF THE PLANT DISCHARGE SAMPLE TAKEN ON | | 12/16/96 WERE RECEIVED BY THE LICENSEE ON 01/03/97. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31539 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/03/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 14:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/03/97 | +------------------------------------------------+EVENT TIME: 11:15[PST]| |NRC NOTIFIED BY: SKAGGS |LAST UPDATE DATE: 01/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MURRAY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DENNIG EO | | |SIGELSKI FEMA | | |BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO MUD SLIDE AFFECTING ACCESS TO THE PLANT SITE | | | | THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO THE CLOSURE OF THE PLANT | | ACCESS ROAD BECAUSE OF A MUD SLIDE. THE SLIDE OCCURRED SEVERAL MILES FROM | | THE PLANT SITE, AND DOES NOT DIRECTLY AFFECT SITE OPERATIONS. THE LICENSEE | | ESTIMATES THAT 8 TO 12 HOURS WILL BE NEEDED TO REOPEN THE ROAD. AN EXTRA | | OPERATING CREW IS ONSITE FOR REQUALIFICATION TRAINING AND IS AVAILABLE TO | | OPERATE BOTH UNITS, IF NECESSARY. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1505 FROM GELZER TAKEN BY STRANSKY * * * | | | | THE COUNTY ESTIMATES THAT ONE LANE OF THE ACCESS ROAD WILL BE REOPENED | | WITHIN 3 HOURS. THE LICENSEE IS CURRENTLY WORKING TO PROVIDE ALTERNATE | | ACCESS TO THE SITE VIA A DIRT ROAD TO THE NORTH. | | | | * * * UPDATE AT 1740 FROM SKAGGS TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1430 PST. ONE LANE OF THE ACCESS ROAD | | HAS BEEN REOPENED, AND SOME PLANT EMPLOYEES ARE BEING SENT HOME EARLY TO | | ASSIST IN TRAFFIC CONTROL. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | THE HOO NOTIFIED R4DO (MURRAY), EO (BATEMAN), AND FEMA (CIBOCH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31540 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 01/03/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 01/03/97 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: PIETRUSKI |LAST UPDATE DATE: 01/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 +------------------------------------------------------------------------------+ | ISOLATED SECTIONS OF PIPING COULD EXCEED ASME CODE ALLOWABLE STRESSES | | | | WHILE PERFORMING ANALYSES IN RESPONSE TO NRC GENERIC LETTER 96-06, THE | | LICENSEE DISCOVERED THAT, WHEN ISOLATED, PORTIONS OF REACTOR BUILDING | | CLOSED COOLING WATER SYSTEM AND SHUTDOWN COOLING SYSTEM PIPING AND THEIR | | ASSOCIATED VALVES COULD EXCEED THEIR ASME CODE ALLOWABLE STRESSES DURING | | CERTAIN DESIGN BASIS ACCIDENTS. THE LICENSEE REPORTED THAT THE SAME | | ANALYSES DETERMINED THAT THE AFFECTED PIPING WOULD NOT RUPTURE AS A RESULT | | OF THESE ACCIDENTS, AND THAT THE AFFECTED VALVES WOULD PERFORM THEIR | | CONTAINMENT ISOLATION FUNCTION. HOWEVER, THIS SITUATION WOULD CONSTITUTE A | | CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31541 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/03/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/03/97 | +------------------------------------------------+EVENT TIME: 15:20[CST]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 01/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 +------------------------------------------------------------------------------+ | ERROR IN FUEL ANALYSIS COULD HAVE RESULTED IN VIOLATION OF A SAFETY LIMIT | | | | THE LICENSEE WAS NOTIFIED BY GE NUCLEAR ENERGY THAT AN ERROR HAD BEEN | | MADE IN THE MAXIMUM EXTENDED OPERATING DOMAIN (MEOD) ANALYSIS PERFORMED | | DURING CYCLE 1. THIS ERROR AFFECTED CALCULATIONS PERFORMED IN SUPPORT OF | | CYCLES 2, 3, 4, 5, AND 6. | | | | SPECIFICALLY, THE MINIMUM CRITICAL POWER RATIO FOR <100% POWER (MCPRp) | | COULD HAVE BEEN VIOLATED DURING A TURBINE PRESSURE REGULATOR DOWNSCALE | | FAILURE. THIS ERROR HAS BEEN CORRECTED IN THE ANALYSIS FOR UPCOMING | | CYCLE 7. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31542 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/03/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:23 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/03/97 | +------------------------------------------------+EVENT TIME: 19:58[EST]| |NRC NOTIFIED BY: MOHNEY |LAST UPDATE DATE: 01/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INADEQUATE INTERFACE BETWEEN SAFETY AND NONSAFETY CIRCUITRY COULD PREVENT | | OPERATION OF EMERGENCY DIESEL GENERATOR (EDG) ROOM VENTILATION FANS DURING | | DEGRADED VOLTAGE CONDITION | | | | THE LICENSEE DISCOVERED THAT THE INTERFACE BETWEEN THE CLASS 1E EDG ROOM | | VENTILATION CIRCUITRY AND THE NON-CLASS 1E FIRE SUPPRESSION SYSTEM | | CIRCUITRY IS NOT ADEQUATE FOR ALL PLANT CONDITIONS. SPECIFICALLY, DURING A | | DEGRADED VOLTAGE CONDITION, THE VENTILATION FANS COULD FAIL TO START DURING | | AN EDG ACTUATION IF THE VOLTAGE TO THE NONSAFETY FIRE SUPPRESSION SYSTEM | | BUS HAD NOT DEGRADED SUFFICIENTLY TO CAUSE THE BUS TO TRIP. | | | | THE LICENSEE HAS DECLARED ALL FOUR EDGs INOPERABLE, AND HAS ENTERED | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION 3.0.3. THE | | LICENSEE IS CURRENTLY TAKING CORRECTIVE ACTIONS (LIFTING LEADS IN THE | | INTERFACE BETWEEN THE EDG ROOM VENTILATION LOGIC AND THE FIRE SUPPRESSION | | SYSTEM), AND DOES NOT EXPECT THAT A PLANT SHUTDOWN WILL BE NECESSARY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0504 ON 01/04/97 BY MOHNEY ENTERED BY JOLLIFFE * * * | | | | AT 2052 ON 01/03/97, THE LICENSEE LIFTED FOUR INTERFACE LEADS, DECLARED | | ALL FOUR EDGs OPERABLE, AND EXITED TECH SPEC LCO A/S 3.0.3. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31543 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/04/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:45 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/04/97 | +------------------------------------------------+EVENT TIME: 17:40[EST]| |NRC NOTIFIED BY: DAUGHERTY |LAST UPDATE DATE: 01/04/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE STATE OF PA REGARDING UNTREATED SEWAGE RELEASE | | | | THE LICENSEE NOTIFIED THE PENNSYLVANIA STATE DEPARTMENT OF ENVIRONMENTAL | | PROTECTION AND DOWNSTREAM WATER USERS ON THE OHIO RIVER REGARDING THE | | RELEASE OF UNTREATED SEWAGE FROM THE PLANT. THE UNIT 2 SEWAGE TREATMENT | | SYSTEM HAD BEEN IMPROPERLY PLACED IN RECIRCULATION MODE, WITH A PLUG LEFT | | IN THE RETURN PIPING TO THE SURGE TANK. THIS CAUSED THE SYSTEM TO OVERFLOW, | | AND RAW SEWAGE TO BE RELEASED AT THE NORMAL EFFLUENT RELEASE POINT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31544 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/05/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 05:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/05/97 | +------------------------------------------------+EVENT TIME: 01:24[PST]| |NRC NOTIFIED BY: DICK WILLETT |LAST UPDATE DATE: 01/05/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PHYSICAL SECURITY EVENT - | | | | AT 0124 (PST), THE MAIN PLANT SECURITY COMPUTER AND THE BACKUP PLANT | | SECURITY COMPUTER WERE LOST. | | | | AT 0135 (PST), THE MAIN PLANT SECURITY COMPUTER WAS RESTORED TO SERVICE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31545 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/06/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 06:16 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/06/97 | +------------------------------------------------+EVENT TIME: 05:56[EST]| |NRC NOTIFIED BY: CHRIS HYNES |LAST UPDATE DATE: 01/06/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 98 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -AUTO Rx TRIP FROM 98% POWER DUE TO MAIN TURBINE TRIP FOR UNKNOWN REASONS- | | | | WHILE PLANT TECHNICIANS WERE TROUBLESHOOTING A LOSS OF REHEAT STEAM TO THE | | MOISTURE SEPERATOR REHEATERS, THE UNIT 2 MAIN TURBINE TRIPPED FOR UNKNOWN | | REASONS WHICH CAUSED THE REACTOR TO TRIP FROM 98% POWER. ALL CONTROL RODS | | INSERTED COMPLETELY. THE AUXILIARY FEEDWATER SYSTEM STARTED ON LOW STEAM | | GENERATOR WATER LEVEL SIGNAL, AS EXPECTED. STEAM IS BEING DUMPED TO THE | | MAIN CONDENSER. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE MAIN TURBINE TRIP. | | | | THE LICENSEE EXPECTS TO RESTART UNIT 2 ON 01/07/97. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+