U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/10/95 - 08/11/95 ** EVENT NUMBERS ** 29066 29178 29179 29180 29181 29182 29183 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ANDERSON, GREENWOOD & CO (AGCO) |NOTIFICATION DATE: 07/14/95 | | CITY: STAFFORD REGION: 4 |NOTIFICATION TIME: 15:24 [ET]| | COUNTY: STATE: TX |EVENT DATE: 07/14/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 08/10/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: J. ALAN WEST |VERN HODGE NRR | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ANDERSON, GREENWOOD & CO (AGCO) OF STAFFORD, TEXAS, CALLED TO REPORT A | | PROBLEM WITH RELIEF VALVES IN ACCORDANCE WITH 10 CFR PART 21. | | | | AGCO HAS INFORMATION INDICATING THAT AGCO MODEL 81P RELIEF VALVES, IF | | ADJUSTED IN THE FIELD USING AIR AS THE TEST MEDIA, MAY NOT EXHIBIT A SET | | PRESSURE WITHIN THE SPECIFICATION TOLERANCE. THESE RELIEF VALVES ARE | | DESIGNED FOR LIQUID THERMAL RELIEF APPLICATIONS AND ARE FACTORY SET AND | | SEALED TO THE SPECIFIED SET PRESSURE USING WATER AS THE TEST MEDIA. | | | | AGCO RECOMMENDS USING WATER AS A TEST MEDIA WHEN ADJUSTMENTS ARE MADE IN | | THE FIELD; HOWEVER, THEY DO SUPPLY THEIR BUYERS WITH A PROCEDURE TO ADJUST | | THE SETPOINT OF THE VALVES WITH AIR. PRELIMINARY TESTS DONE BY AGCO SHOW | | THAT VALVES MAY EXHIBIT UP TO A 40% SET PRESSURE DEVIATION WHEN THE AIR | | METHOD IS USED. THESE TESTS ALSO INDICATE THE DEVIATION WILL BE LARGEST | | FOR LOW SET PRESSURES (100 PSI). | | | | AGCO HAS SUPPLIED MODEL 81P RELIEF VALVES TO THE FOLLOWING UTILITIES: DUKE | | POWER COMPANY, NORTHEAST UTILITIES, VIRGINIA POWER, PENNSYLVANIA POWER AND | | LIGHT, BOSTON EDISON, CENTERIOR SERVICE, NEBRASKA PUBLIC POWER DISTRICT, | | VERMONT YANKEE, OMAHA PUBLIC POWER DISTRICT, GPU NUCLEAR CORPORATION, | | GEORGIA POWER, PUBLIC SERVICE ELECTRIC AND GAS, AND ENTERGY. | | | | * * * * * UPDATE RECEIVED BY FACSIMILE (SIGNED BY WEST) AT APPROXIMATELY | | 1534 ON AUGUST 10, 1995. TAKEN BY TROCINE. * * * * * | | | | THIS CORRESPONDENCE PROVIDED THE RESULTS OF TESTING PERFORMED TO EVALUATE | | THE PROBLEM REPORTED BY AGCO ON JULY 14, 1995. TESTING WAS PERFORMED TO | | ESTABLISH THE AMOUNT OF DEVIATION FROM NAME PLATE SET PRESSURE THAT COULD | | RESULT FROM AGCO'S MODEL 81P VALVE USING AIR AS THE TEST MEDIA INSTEAD OF | | WATER. VALVES WERE ASSEMBLED AND SET PRESSURE ADJUSTMENTS WERE MADE | | FOLLOWING THE FACTORY PROCEDURE USING WATER AS THE TEST MEDIA. THE VALVES | | WERE THEN CHECKED USING AIR AS A TEST MEDIA. IF THE AIR TEST METHOD DID | | NOT RESULT IN THE SAME SET PRESSURE VALUE, THEN FURTHER ADJUSTMENTS WERE | | MADE TO SATISFY THE AIR METHOD CRITERIA. FOR VALVES WHERE ADJUSTMENTS WERE | | NECESSARY, THE FACTORY WATER METHOD WAS REPEATED, AND THE RESULTING SET | | PRESSURE WAS RECORDED. THE DIFFERENCE BETWEEN THE FIRST WATER TEST SETTING | | AND THE SECOND WATER TEST READING REPRESENTED THE POTENTIAL DEVIATION FROM | | NAME PLATE SET THAT COULD RESULT FROM ADJUSTING THE VALVE USING THE AIR | | METHOD. | | | | TWO SERIES OF TESTS WERE PERFORMED: ONE USING KEL-F SEAT MATERIAL AND | | ANOTHER USING PEEK SEAT MATERIAL. SET PRESSURES RANGING FROM 100 PSI TO | | 2,000 PSI WERE TESTED. THE POTENTIAL SET PRESSURE DEVIATION ABOVE NAME | | PLATE WAS DETERMINED TO BE 4% TO 15% FOR MODEL 81P VALVES WITH KEL-F SEAT | | MATERIAL AND A SET PRESSURE RANGE OF 100 PSIG TO 750 PSIG. THE POTENTIAL | | SET PRESSURE DEVIATION ABOVE NAME PLATE WAS DETERMINED TO BE 20% TO 40% FOR | | MODEL 81P VALVE A WITH PEEK SEAT MATERIAL AND A SET PRESSURE RANGE OF 100 | | PSIG TO 750 PSIG. THERE WAS NO IDENTIFIED POTENTIAL SET PRESSURE DEVIATION | | ABOVE NAME PLATE FOR MODEL 81P VALVES WITH EITHER KEL-F OR PEEK SEAT | | MATERIAL AND A SET PRESSURE RANGE GREATER THAN 750 PSIG. | | | | SINCE THE AIR TEST METHOD WAS BASED ON THE VALVE'S FIRST LEAKAGE ON | | INCREASING PRESSURE, RESULTS WERE VERY DEPENDENT ON THE EFFECTIVENESS OF | | THE VALVE SEAT. PEEK IS A VERY HARD PLASTIC RELATIVE TO KEL-F AND REQUIRES | | MORE SEATING LOAD TO EFFECT A SEAL. THEREFORE, THE POTENTIAL DEVIATION FOR | | PEEK SEAT MATERIAL IS GREATER THAN FOR KEL-F SEAT MATERIAL. FOR BOTH | | MATERIALS, THE HIGHER SET PRESSURES (GREATER THAN 750 PSIG) SHOWED NO | | DEVIATION BETWEEN WATER AND AIR TEST METHODS. FOR THE LOWER SET PRESSURES, | | THE RANGE OF DEVIATIONS SHOWED NO SIGNIFICANT TREND. | | | | AGCO STATED THAT THE REFERENCED DEVIATIONS ARE ONLY APPLICABLE TO AGCO'S | | MODEL 81P LIQUID RELIEF VALVES THAT HAVE HAD SET PRESSURES ADJUSTED AFTER | | SHIPMENT FROM THE FACTORY USING AIR AS THE TEST MEDIA AND FIRST CRACK | | (LEAK) AT 95% OF SET PRESSURE AS THE CRITERIA. ANY VALVE THAT HAS AGCO'S | | FACTORY LEAD SEAL UNBROKEN OR HAS BEEN ADJUSTED USING THE WATER TEST METHOD | | IS UNAFFECTED. | | | | AGCO ALSO STATED THAT THE MODEL 81P VALVE SHOULD ONLY BE SET PRESSURE | | ADJUSTED USING THE WATER TEST METHOD DESCRIBED IN PROCEDURE NO5.9040.180, | | REVISION F, FOR SET PRESSURES BELOW 750 PSIG AND THAT EITHER THE WATER OR | | AIR TEST METHOD MAY BE USED FOR SET PRESSURES ABOVE 750 PSIG. AGCO IS | | CURRENTLY IN THE PROCESS OF PREPARING LETTERS EXPLAINING THESE FINDINGS AND | | RECOMMENDED PROCEDURES TO ALL CUSTOMERS WHO HAVE PURCHASED THIS MODEL | | VALVE. | | | | THE NRC OPERATIONS CENTER NOTIFIED NRR/RVIB (HODGE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29178 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 08/10/95 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 00:20 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 08/09/95 | +------------------------------------------------+EVENT TIME: 19:17[EDT]| |NRC NOTIFIED BY: HURCHALLA |LAST UPDATE DATE: 08/10/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEROME BLAKE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESSURIZER PORVs DECLARED INOPERABLE AFTER STROKE TIME TESTING IN MODE 4. | | | | ST. LUCIE UNIT 1 IS RETURNING TO MODE 5 (COLD SHUTDOWN) AFTER ENTERING MODE | | 4 (HOT SHUTDOWN) EARLIER IN THE DAY. DURING PRESSURIZER POWER OPERATED | | RELIEF VALVE (PORV) STROKE TIME TESTING, IT WAS NOT POSSIBLE TO VERIFY | | OPERABILITY. UNIT 1 WILL BE MAINTAINED IN MODE 5 UNTIL THIS ISSUE CAN BE | | RESOLVED. | | | | THE STROKE TIME TESTING INVOLVES CHECKING FLOW AS INDICATED BY ACOUSTIC | | MONITORS. THE APPROPRIATE LED LIGHT INDICATIONS ON THE ACOUSTIC MONITORS | | WERE UNABLE TO BE VERIFIED. THERE ARE OTHER INDICATIONS THAT THE PORVs | | WERE INDEED OPENING, BUT THEY DECIDED TO RETURN TO MODE 5 TO BE ABLE TO | | TAKE A CLOSER LOOK AT THE OPERABILITY. THE LICENSEE HAS DECLARED THE | | PRESSURIZER PORVs INOPERABLE AND IS PREPARING TO COOL DOWN TO MODE 5. UNIT | | 1 IS IN A 24-HOUR TS LCO TO ENTER MODE 5 AND ESTABLISH AN RCS VENT. UNIT 1 | | IS CURRENTLY AT 260 PSIA AND 275øF. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29179 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 08/10/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 03:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/09/95 | +------------------------------------------------+EVENT TIME: 23:01[CDT]| |NRC NOTIFIED BY: WINTERS |LAST UPDATE DATE: 08/10/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BRIEF INOPERABILITY OF SAFETY EQUIPMENT DURING THE PERFORMANCE OF A GROUND | | CHECKING PROCEDURE. | | | | THE '1A' SAFETY INJECTION (SI) PUMP WAS OUT OF SERVICE FOR A PLANNED | | MAINTENANCE OUTAGE. THE LICENSEE WAS PERFORMING GROUND CHECKS IN | | ACCORDANCE WITH APPROVED PROCEDURES AND WITH A TECH SPEC INTERPRETATION | | ALLOWING THE PERFORMANCE OF GROUND CHECKING ON ESSENTIAL EQUIPMENT. DURING | | THE COURSE OF THE GROUND CHECKING, THE DC FEED TO THE '1A' DIESEL GENERATOR | | WAS OPENED UP FOR APPROXIMATELY 5 SECONDS. THIS MADE THE EMERGENCY POWER | | SUPPLY TO THE '1B' SI PUMP INOPERABLE; THEREFORE, THERE WERE NO SAFETY | | INJECTION PUMPS AVAILABLE FOR APPROXIMATELY 5 SECONDS. | | | | ALSO IN ACCORDANCE WITH THE GROUND CHECKING PROCEDURE, THE DC CONTROL POWER | | TO AN ESSENTIAL SAFEGUARDS BUS (#148) WAS OPENED, WHICH MADE ALL THE | | BREAKERS AND COMPONENTS SUPPLIED BY THAT BUS INOPERABLE. THIS INCLUDED THE | | BRIEF INOPERABILITY (5 SECONDS) OF THE '1B' SI PUMP, THE '1B' CONTAINMENT | | SPRAY PUMP, THE '1B' AUX FEEDWATER PUMP, THE '1B' RHR PUMP, THE 'OD' | | COMPONENT COOLING PUMP, THE '1B' SERVICE WATER PUMP, AND THE '1A' AND '1D' | | REACTOR CONTAINMENT FAN COOLERS. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. ALL AFFECTED SYSTEMS HAVE | | BEEN RESTORED TO OPERABILITY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29180 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/10/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 12:56 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/10/95 | +------------------------------------------------+EVENT TIME: 10:55[EDT]| |NRC NOTIFIED BY: DAVID MOHRE |LAST UPDATE DATE: 08/10/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STATE NOTIFICATION OF AN UNPLANNED RELEASE OF APPROXIMATELY 7 POUNDS OF | | FREON-22. | | | | THE LICENSEE REPORTED AN UNPLANNED RELEASE OF APPROXIMATELY 7 POUNDS OF | | CHLORODIFLUOROMETHANE (FREON-22) TO THE NEW YORK STATE DEPARTMENT OF | | ENVIRONMENTAL CONSERVATION (REPORT NUMBER 95-5766). THIS NOTIFICATION IS | | REQUIRED UNDER TITLE 6 OF THE NEW YORK STATE CODE OF RULES AND REGULATIONS. | | | | THE FREON-22 RELEASE WAS FROM A FACILITY AIR CONDITIONING SYSTEM LOCATED | | INSIDE A HEATING VENTILATION AND AIR CONDITIONING ROOM. THE LICENSEE | | IDENTIFIED A LEAKING COMPONENT AND LOW SYSTEM PRESSURE WHEN A REFRIGERANT | | COMPRESSOR TRIPPED OFF. THE LEAKING COMPONENT WAS ISOLATED, AND THE LEAK | | WAS STOPPED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29181 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 08/10/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 13:03 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 08/08/95 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: FRAN SULLIVAN |LAST UPDATE DATE: 08/10/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEROME BLAKE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR AN AUTOMATIC ENGINEERED SAFETY FEATURE ACTUATION THAT WAS NOT | | PART OF A PREPLANNED SEQUENCE DURING TESTING. | | | | AT 1230 ON AUGUST 10, 1995, THE LICENSEE IDENTIFIED THAT AN AUTOMATIC | | ENGINEERED SAFETY FEATURE COULD HAVE ACTUATED THAT WAS NOT PART OF A | | PREPLANNED SEQUENCE DURING TESTING. AS A RESULT OF THE PERFORMANCE OF | | SURVEILLANCE PROCEDURE SP358A TO TEST THE 2-OUT-OF-3 ENGINEERED SAFETY | | FEATURE ACTUATION LOGIC, THE LICENSEE IDENTIFIED A SUSPECTED PROBLEM OF THE | | ENGINEERED SAFETY MATRIX. TROUBLESHOOTING ON AUGUST 8, 1995, REVEALED THAT | | THE WIRING MATRIX WAS SUCH THAT CORE FLOOD VALVE 25 (WHICH IS A CONTAINMENT | | ISOLATION VALVE FOR THE CORE FLOOD TANK) WOULD HAVE GONE CLOSED IF 1 OUT OF | | 3 CHANNELS TRIPPED IN LIEU OF 2 OUT OF 3 CHANNELS. DURING PRE-PLANNED | | TESTING, PERFORMANCE OF A SURVEILLANCE PROCEDURE, OR ANY TIME ONE | | PARTICULAR CHANNEL IS TRIPPED; THE CORE FLOOD VALVE WOULD HAVE CLOSED. THIS | | DID NOT ACTUALLY OCCUR BUT COULD HAVE HAPPENED AT ANY TIME. THE VALVE IS | | NORMALLY CLOSED, AND THERE WAS NO VALVE MOVEMENT. THE LICENSEE HAS | | CORRECTED THE PROBLEM. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29182 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 08/10/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:43 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/10/95 | +------------------------------------------------+EVENT TIME: 14:40[EDT]| |NRC NOTIFIED BY: DOUGLAS HEFFERNAN |LAST UPDATE DATE: 08/10/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT FOUR SERVICE WATER PIPING WELDS FOR THE CONTAINMENT AIR | | RECIRCULATION FANS WOULD NOT HAVE SURVIVED A DESIGN BASIS SEISMIC EVENT. | | | | DURING REFUELING OUTAGE 18, SERVICE WATER PIPING REPAIRS WERE PERFORMED ON | | THE SUPPLY AND RETURN HEADERS FOR THE CONTAINMENT AIR RECIRCULATION FAN | | COOLERS. FOUR WELDS WERE CUT OUT AND SENT TO THE CORPORATE DESIGN AND | | SUPPORT GROUP FOR EVALUATION DURING FEBRUARY 1995, AND THE ANALYSIS OF THE | | TWO WORST WELDS REVEALED THAT THESE FOUR WELDS WOULD NOT HAVE SURVIVED A | | DESIGN BASIS SEISMIC EVENT. THE PIPING WOULD NOT HAVE CATASTROPHICALLY | | FAILED BUT WOULD HAVE HAD GROSS LEAKAGE WHICH WOULD HAVE RENDERED ALL FOUR | | CONTAINMENT AIR RECIRCULATION FANS INOPERABLE. INSUFFICIENT MARGIN EXISTED | | TO MEET REQUIREMENTS OF GENERIC LETTER 91-18 (INFORMATION TO LICENSEES | | REGARDING TWO NRC INSPECTION MANUAL SECTIONS ON RESOLUTION OF DEGRADED AND | | NONCONFORMING CONDITIONS AND ON OPERABILITY). THIS EVENT IS HISTORICAL | | ONLY. ALL APPLICABLE WELDS WERE REPLACED DURING THE REFUELING OUTAGE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE STATE OF CONNECTICUT, | | AND THE LOCAL TOWN SELECTMEN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29183 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/10/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 19:56 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/10/95 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: STEVEN M. SMITH |LAST UPDATE DATE: 08/10/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSITIVE RANDOM FITNESS-FOR-DUTY TEST FOR MARIJUANA FROM A MAINTENANCE | | CONTRACTOR SUPERVISOR. | | | | AT 1445 ON AUGUST 10, 1995, THE LICENSEE'S MEDICAL DEPARTMENT WAS NOTIFIED | | OF A CONFIRMED POSITIVE TEST RESULT FOR MARIJUANA FROM A RANDOM SAMPLE | | OBTAINED FROM A MAINTENANCE CONTRACTOR SUPERVISOR ON AUGUST 7, 1995. THE | | LICENSEE IMMEDIATELY TERMINATED THE INDIVIDUAL'S UNESCORTED ACCESS TO THE | | PLANT AND HAS ALSO INITIATED A REVIEW OF THE INDIVIDUAL'S WORK ACTIVITIES | | SINCE THE INDIVIDUAL'S LAST NEGATIVE TEST RESULT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO MAKE A | | COURTESY NOTIFICATION TO THE REGIONAL OFFICE TOMORROW. | +------------------------------------------------------------------------------+