U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/17/96 - 12/18/96 ** EVENT NUMBERS ** 31463 31464 31465 31466 31467 31468 31469 31470 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31463 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 12/17/96 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 12:12 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 10:30[EST]| |NRC NOTIFIED BY: DAVE WILLIAMS |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KEN BARR RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | |BILL BEECHER PAO | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - RETIRED FPL EMPLOYEE VISITING THE PLANT SITE DIED OF A HEART ATTACK - | | | | A RETIRED FLORIDA POWER & LIGHT COMPANY EMPLOYEE VISITING THE PLANT SITE IN | | A SANTA CLAUS SUIT COLLAPSED FROM AN APPARENT HEART ATTACK. ONSITE MEDICAL | | PERSONNEL RESPONDED, PERFORMED CPR, AND REQUESTED OFFSITE ASSISTANCE. | | | | THE INDIVIDUAL WAS TRANSPORTED OFFSITE TO A LOCAL HOSPITAL FOR MEDICAL | | TREATMENT AND WAS LATER PRONOUNCED DEAD AT THE HOSPITAL. | | | | THE LICENSEE MAY ISSUE A PRESS RELEASE. | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31464 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 12/17/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: TOM McKEE |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NONCONTAMINATED INJURED PLANT EMPLOYEE TRANSPORTED TO OFFSITE HOSPITAL - | | | | AT 1400, THE LICENSEE DISCOVERED A PLANT EMPLOYEE UNCONSCIOUS IN A SECURED | | (FENCED-IN) HIGH VOLTAGE AREA. THE INDIVIDUAL HAD ENTERED THE FENCED-IN | | AREA TO PERFORM A TRANSFORMER OIL TEST. THE LICENSEE ADMINISTERED FIRST | | AID ONSITE AND DURING TRANSPORT OF THE INJURED INDIVIDUAL TO AN OFFSITE | | HOSPITAL. THE INDIVIDUAL IS NOT CONTAMINATED AND HIS STATUS WAS UNKNOWN | | AT THE TIME OF THE CALL. THE LICENSEE IS INVESTIGATING THIS SITUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1754 BY DAVE MOHR ENTERED BY DICK JOLLIFFE * * * | | | | THE INDIVIDUAL WAS PRONOUNCED DEAD AT THE HOSPITAL AT 1715. | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF LABOR AND THE NRC | | RESIDENT INSPECTOR AND ISSUED A PRESS RELEASE. THE HOO NOTIFIED R1DO | | SHANBAKY. | | | | * * * AT 1900 COMMISSIONERS ASSISTANTS BRIEFING HELD * * * | | | | PARTICIPANT WERE; AEOD JORDAN; NRR EO CHAFFEE, MATHEWS; NMSS EO COOL; | | STATE PROGRAMS BANGART; CONGRESSIONAL AFFAIRS MADDEN; EDO DROUIN; | | COMM McGAFFIGAN BEALL; COMM ROGERS SORENSEN; COMM DICUS LUBENAU; | | REGION 1 COWGILL (BRIEFER), BARKLEY, CRLENJAK. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31465 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 12/17/96 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 16:23 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 12:36[CST]| |NRC NOTIFIED BY: DOMINICK LoGALBO |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - UNIT 3 DIVISION II ECC SYSTEMS INOPERABLE DUE TO A BLOWN FUSE - | | | | AT 1236 (CST), THE UNIT 3 DIVISION II EMERGENCY CORE COOLING (ECC) SYSTEM | | INVERTER WAS LOST DUE TO A BLOWN FUSE. THE ECC SYSTEM DIVISION II INVERTER | | SUPPLIES POWER TO 2 OF 4 CHANNELS OF DRYWELL PRESSURE AND REACTOR WATER | | LEVEL SENSORS. THESE SENSORS FEED BOTH DIVISIONS OF INITIATION LOGIC FOR | | ALL UNIT 3 ECC SYSTEMS. OTHER SENSORS FOR REACTOR PRESSURE AND CONTAINMENT | | PARAMETERS ARE ALSO SUPPLIED BY THIS INVERTER, AS IS THE HPCI SYSTEM FLOW | | CONTROLLER. THE REMAINING CHANNELS OF INSTRUMENTATION POWERED BY THE | | DIVISION I ECC SYSTEM INVERTER ARE SUFFICIENT TO INITIATE THE LOGIC OF ALL | | ECC SYSTEM DIVISIONS. ALL OF THE ABOVE SYSTEMS REMAIN CAPABLE OF FULFILLING | | THEIR DESIGN FUNCTIONS WITH THE EXCEPTION OF THE HPCI SYSTEM WHICH WILL NOT | | INJECT INTO THE CORE DUE TO THE LOSS OF ITS FLOW CONTROLLER AND CORE SPRAY, | | LOOP II, WHICH WILL NOT INJECT INTO THE CORE DUE TO THE LOSS OF THE LOW | | REACTOR PRESSURE PERMISSIVE SIGNAL REQUIRED TO ELECTRICALLY OPEN THE SYSTEM | | INJECTION VALVE. ATWS/RPT LOGIC, DIV II, IS INOPERABLE DUE TO THE POWER | | LOSS BUT DIV I REMAINS CAPABLE OF PERFORMING THE SYSTEM DESIGN FUNCTIONS. | | | | THE LICENSEE DECLARED THE ECC SYSTEMS AND THE ABOVE INVERTER INOPERABLE | | DUE TO THE LOSS OF POWER AND/OR LOGIC INPUTS. SEVERAL TECH SPEC LCOs WERE | | APPLICABLE BUT THE MOST LIMITING IS TECH SPEC LCO A/S 3.2.B WHICH REQUIRES | | THE LICENSEE TO PLACE UNIT 3 IN AT LEAST COLD SHUTDOWN CONDITION WITHIN | | 24 HOURS WITH THE ABOVE EQUIPMENT INOPERABLE. | | | | AT 1500 (CST), THE LICENSEE REPLACED THE BLOWN FUSE, RESTORED ALL EQUIPMENT | | AND SYSTEMS TO OPERABLE STATUS, & EXITED ALL APPLICABLE TECH SPEC LCO A/Ss. | | | | THE LICENSEE WILL SUBMIT AN LER AND WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31466 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 12/17/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:30 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 12:30[CST]| |NRC NOTIFIED BY: ART DANIELS |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B.J. HOLT 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -DIVISION 2 OF RHR SERVICE WATER SYSTEM HAD BEEN OUTSIDE ITS DESIGN BASIS- | | | | DURING A REVIEW OF POTENTIAL WATER HAMMER ISSUES WITH THE RHR SERVICE WATER | | SYSTEM, THE LICENSEE IDENTIFIED THAT DIVISION 2 OF THE RHR SERVICE WATER | | SYSTEM HAD BEEN OUTSIDE OF ITS DESIGN BASIS. | | | | ASSUMING A FAILURE OF THE NONSAFETY RELATED DIKE DURING WHICH TIME THE | | LEVEL OF THE COOLING LAKE DROPS TO 690 FEET BY FLOWING THROUGH THE OPENING | | IN THE FAILED DIKE AND A CONCURRENT DESIGN BASIS ACCIDENT, A WATER HAMMER | | COULD OCCUR WHICH WOULD RESULT IN THE FAILURE OF THE DIVISION 2 RHR SERVICE | | WATER PIPING/SYSTEM. THIS SITUATION PLACES THE DIVISION 2 RHR SERVICE | | WATER SYSTEM OUTSIDE ITS DESIGN BASIS IN OPERATING CONDITIONS 1, 2, AND 3. | | THIS SITUATION IS APPLICABLE TO BOTH UNITS 1 AND 2. | | | | CURRENTLY, UNIT 1 IS IN OPERATING CONDITION 4 (COLD SHUTDOWN) IN A | | MAINTENANCE OUTAGE AND UNIT 2 IS IN OPERATING CONDITION 5 (DEFUELED) | | IN A REFUELING OUTAGE. IN OPERATING CONDITIONS 4 AND 5, THE RHR SERVICE | | WATER SYSTEM IS OPERABLE. | | | | DURING THE CURRENT OUTAGES ON BOTH UNITS 1 AND 2, THE LICENSEE IS | | INSTALLING A KEEP-FILL SYSTEM FOR EACH UNIT WHICH WILL ELIMINATE THE | | POTENTIAL FOR WATER HAMMER DURING DESIGN BASIS EVENTS IN OPERATING | | CONDITIONS 1, 2, AND 3. THESE KEEP-FILL SYSTEMS WILL BE INSTALLED AND | | OPERABLE PRIOR TO EITHER UNIT 1 OR 2 ENTERING OPERATING CONDITION 3 | | (HOT SHUTDOWN). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31467 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/17/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: PAUL DRIEHAUS |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 24 POWER OPERATION | 24 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - VALVE MOTOR OPERATORS ENERGIZED DURING S/U CONTRARY TO PLANT PROCEDURES - | | | | AT 1500, WITH UNIT 2 AT 24% POWER, DURING PLANT STARTUP, PLANT OPERATORS | | IDENTIFIED THAT ISOLATION VALVES #HV-041-209A AND B ON THE HIGH PRESSURE | | FEEDWATER FLUSH LINE TO THE MAIN CONDENSER (CONTAINMENT ISOLATION VALVES) | | WERE CLOSED, BUT THEIR MOTOR OPERATORS WERE ENERGIZED, CONTRARY TO PLANT | | STARTUP PROCEDURAL REQUIREMENTS. PLANT OPERATORS IMMEDIATELY DEENERGIZED | | THE VALVE MOTORS AND LOCKED OPEN THEIR CIRCUIT BREAKERS. | | | | NORMAL PLANT STARTUP PROCEDURE #GP-2 REQUIRES THAT THESE VALVES BE CLOSED | | AND DEENERGIZED PRIOR TO OPERATING ABOVE 600 PSIG REACTOR PRESSURE. THIS | | PROCEDURE STEP IMPLEMENTS A FIRE SAFE SHUTDOWN ANALYSIS REQUIREMENT TO | | MAINTAIN THESE VALVES CLOSED TO PROTECT HIGH/LOW PRESSURE SYSTEM INTERFACES | | (UFSAR TABLE 9A-12) IN THE EVENT OF A SIGNIFICANT FIRE IN THE MAIN CONTROL | | ROOM OR IN THE CABLE SPREADING ROOM. | | | | THIS SITUATION EXISTED BETWEEN 0900 ON 12/14/96 AND 1500 ON 12/16/96 WHILE | | UNIT 2 REACTOR PRESSURE EXCEEDED 600 PSIG DURING STARTUP. | | | | THIS SITUATION CONSTITUTES A NONCOMPLIANCE WITH OPERATING LICENSE CONDITION | | #2.C.3 FOR UNIT 2 REQUIRING A 24 HOUR NOTIFICATION PER THE UNIT 2 OPERATING | | LICENSE. | | | | DURING THE TIME THESE VALVES WERE NOT DEENERGIZED, THERE WERE SOME | | COMPENSATORY MEASURES ALREADY IN PLACE THAT COULD HAVE MITIGATED THE | | CONSEQUENCES OF A FIRE. THESE MEASURES INCLUDE CONTINUOUS OCCUPATION OF | | THE MAIN CONTROL ROOM WITH MANUAL FIRE SUPPRESSION EQUIPMENT, AUTOMATIC | | FIRE DETECTION AND DETECTION EQUIPMENT, AN HOURLY FIRE WATCH IN THE CABLE | | SPREADING ROOM, AND NO INCREASE IN COMBUSTIBLE MATERIALS IN THESE AREAS. IN | | THE EVENT OF AN ACTUAL FIRE IN ONE OF THESE AREAS, THE PLANT OPERATORS | | COULD HAVE MANUALLY CLOSED THESE VALVES. OTHER METHODS OF REACTOR | | INVENTORY MAKE-UP WOULD BE AVAILABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE AND FULL IMPACT OF THIS EVENT, AND | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31468 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/17/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 16:58 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 16:18[EST]| |NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -REMOTE S/D CAPABILITY COULD BE LOST DURING A CONTROL ROOM FIRE (IN 92-18)- | | | | DURING A LICENSEE ENGINEERING REVIEW OF 10 CFR PART 50, APPENDIX R FIRE | | INDUCED HOT SHORTS (AS DESCRIBED IN NRC INFORMATION NOTICE #92-18), THE | | LICENSEE DISCOVERED THAT THE POTENTIAL EXISTS FOR THE LOSS OF REMOTE | | SHUTDOWN CAPABILITY OF CERTAIN VALVES DURING A CONTROL ROOM FIRE. THE SHORT | | CIRCUITS COULD BYPASS THE TORQUE SWITCHES AND CAUSE SPURIOUS OPERATION OF | | RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING VALVES. THIS COULD RESULT IN | | STALLED THRUST CONDITIONS THAT COULD CAUSE MECHANICAL DAMAGE TO THE VALVES, | | AND HAD NOT BEEN PREVIOUSLY EVALUATED IN THE LICENSEE'S RESPONSE TO IN | | #92-18. THREE VALVES IN THE RHR SHUTDOWN COOLING SYSTEM (#2RHS*MOV-112, | | 142, AND 149) HAVE BEEN IDENTIFIED AS BEING SUSCEPTIBLE TO THIS CONDITION | | SINCE PORTIONS OF THE SHUTDOWN COOLING PIPING ARE NOT SINGLE FAILURE PROOF. | | | | THESE THREE VALVES, WHICH ARE ALL NORMALLY CLOSED, HAVE BEEN ELECTRICALLY | | DEENERGIZED UNDER ADMINISTRATIVE CONTROLS AS IMMEDIATE CORRECTIVE ACTION. | | IN ADDITION, THESE VALVES HAVE BEEN DECLARED INOPERABLE FOR REMOTE SHUTDOWN | | CONTROL. TECH SPEC LCO A/S 3.3.7.4 REQUIRES THE LICENSEE TO RESTORE THESE | | VALVES TO OPERABLE STATUS WITHIN 7 DAYS OR PLACE THE PLANT IN AT LEAST HOT | | SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS. | | | | THIS NOTIFICATION IS BEING MADE TO THE NRC SINCE THE LICENSEE IS CURRENTLY | | UNABLE TO CONFIRM THAT UNIT 2 IS WITHIN ITS DESIGN BASIS FOR APPENDIX R | | SHUTDOWN COOLING. | | | | THE LICENSEE IS CONTINUING TO REVIEW THIS CONDITION AND WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31469 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNITED METRO MATERIALS, INC. |NOTIFICATION DATE: 12/17/96 | | CITY: PHOENIX REGION: 4 |NOTIFICATION TIME: 17:59 [ET]| | COUNTY: STATE: AZ |EVENT DATE: 12/17/96 | |LICENSE#: 7-227 (AZ) AGREEMENT: Y |EVENT TIME: 15:00[MST]| | DOCKET: |LAST UPDATE DATE: 12/17/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LINDA HOWELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BILL WRIGHT, AZ RRA | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TROXLER ASPHALT CONTENT GAUGE STOLEN FROM ARIZONA LICENSEE SITE - | | | | BILL WRIGHT, ARIZONA RADIATION REGULATORY AGENCY (RRA), REPORTED THAT A | | TROXLER ASPHALT CONTENT GAUGE, MODEL #3241C, SN 3215, SOURCE #558608, WAS | | REMOVED (STOLEN) FROM A TRAILER AT THE SAN XAVIER ROCK & MATERIALS SITE | | IN TUCSON, ARIZONA. THE GAUGE WAS TAKEN BEFORE 0600 (MST) ON 12/17/96. THE | | GAUGE CONTAINED A 100 mCi Am-Be SOURCE. THE MARANA ARIZONA POLICE | | DEPARTMENT IS INVESTIGATING THIS INCIDENT (CASE #96-2432). THE ARIZONA RRA | | HAS SENT AN INVESTIGATOR TO THE SITE. THE STATE OF ARIZONA LICENSEE, UNITED | | METRO MATERIALS, INC, HAS SECURITY PERSONNEL ONSITE UNTIL 0500 (MST) EACH | | DAY. A TRUCK AND LABORATORY EQUIPMENT WERE ALSO STOLEN FROM THE SITE. | | TOM DUNWELL IS THE UNITED METRO MATERIALS RADIATION SAFETY OFFICER. | | | | THE STATES OF COLORADO, NEVADA, UTAH, NEW MEXICO, AND CALIFORNIA ARE ALSO | | BEING NOTIFIED OF THIS INCIDENT. | | | | SEE THE HOO LOG FOR TELEPHONE NUMBERS AND ADDRESSES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31470 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 12/17/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 23:57 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 12/17/96 | +------------------------------------------------+EVENT TIME: 23:05[EST]| |NRC NOTIFIED BY: CHRISTOPHER TABONE |LAST UPDATE DATE: 12/17/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO VITAL AREA BOUNDARY. IMMEDIATE | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+