U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/04/96 - 12/05/96 ** EVENT NUMBERS ** 31402 31403 31404 31405 31406 31407 31408 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31402 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 12/04/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 09:03 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 12/04/96 | +------------------------------------------------+EVENT TIME: 05:23[EST]| |NRC NOTIFIED BY: JOHN BASS |LAST UPDATE DATE: 12/04/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM SIGNAL DUE TO SCRAM DISCHARGE VOLUME BEING FILLED. | | | | A ONE ROD OUT INTERLOCK SURVEILLANCE WAS BEING PERFORMED WITH THE MODE | | SWITCH IN REFUEL PER TECHNICAL SPECIFICATION TABLE 2.1 WITH ALL RODS FULLY | | INSERTED. WHEN THE MODE SWITCH WAS PLACED IN THE SHUTDOWN POSITION | | FOLLOWING COMPLETION OF THE ONE ROD OUT INTERLOCK SURVEILLANCE, THE | | EXPECTED RPS ACTUATION OCCURRED (i.e. MANUAL REACTOR SCRAM). AFTER A SHORT | | DELAY, THE OPERATOR RESET THE SCRAM SIGNAL INSERTED BY REPOSITIONING THE | | MODE SWITCH. A SHORT TIME LATER, A SECOND SCRAM OCCURRED DUE TO THE | | EXPECTED FILLING OF THE SCRAM DISCHARGE VOLUME. THE SECOND ACTUATION WAS | | CAUSED BY THE OPERATOR PREMATURELY RESETTING THE FIRST SCRAM. ALL CONTROL | | RODS WERE FULLY INSERTED IN THE CORE PRIOR TO AND AFTER THE ACTUATIONS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31403 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 12/04/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 09:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/04/96 | +------------------------------------------------+EVENT TIME: 09:21[EST]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 12/04/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PUBLIC NOTIFICATION SYSTEM OUT OF SERVICE FOR MAINTENANCE. | | | | LICENSEE WAS NOTIFIED BY JPS COMMUNICATIONS THAT THEY ARE PERFORMING | | MAINTENANCE ON THEIR PUBLIC NOTIFICATION SYSTEM AND IT WILL BE OUT OF | | SERVICE FROM 0900 UNTIL 1600 HOURS. LICENSEE WILL NOTIFY THE STATES OF | | VERMONT, NEW HAMPSHIRE, AND MASSACHUSETTS OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 1025 12/4/96 FROM MAY TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE PUBLIC NOTIFICATION | | SYSTEM IS STILL OPERATING ON ITS BACKUP SYSTEM. THEREFORE, THIS CONDITION | | IS NOT REPORTABLE. THE R1DO (MEYER) HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31404 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 12/04/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 11:40 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/03/96 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: RADISHOFSKI |LAST UPDATE DATE: 12/04/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MEYER RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED ERROR IN CORE THERMAL POWER CALCULATION | | | | THE LICENSEE MADE A 24 HOUR ENS NOTIFICATION BASED ON THE POTENTIAL TO HAVE | | EXCEEDED THE MAXIMUM LICENSED THERMAL POWER LIMIT OF 3441 MWt FOR BOTH | | UNITS. DURING A DESIGN BASIS DOCUMENT REVIEW OF THE REACTOR WATER CLEANUP | | SYSTEM, THE LICENSEE DISCOVERED THAT A FACTOR USED TO CONVERT GALLONS PER | | MINUTE TO POUNDS MASS PER HOUR WAS INCORRECT. THIS CONVERSION FACTOR IS | | USED IN THE CORE THERMAL POWER CALCULATION. THE ERROR RESULTED IN A LESS | | CONSERVATIVE FLOW RATE, AND THE POTENTIAL FOR OPERATING AT 0.8 MWt GREATER | | THAN THE LICENSED THERMAL POWER LIMIT. | | | | THE LICENSEE REPORTED THAT NO SAFETY LIMITS WERE APPROACHED OR EXCEEDED. | | THE LICENSEE HAS SET THE ADMINISTRATIVE CORE THERMAL POWER LIMIT TO 3440 | | MWt TO ACCOUNT FOR THE ERROR. THE LICENSEE HAS CONTACTED THE NRC RESIDENT | | INSPECTOR REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31405 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 12/04/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 16:05 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 12/04/96 | +------------------------------------------------+EVENT TIME: 15:25[EST]| |NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 12/04/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |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 DISCOVERED DURING A DESIGN REVIEW A CONDITION AFFECTING BOTH | | EMERGENCY DIESEL GENERATORS. | | | | "A REVIEW OF THE PROTECTION PROVIDED BY THE 51V RELAY REVEALED THAT THE | | RELAY WILL NOT PROVIDE LOSS OF OFFSITE POWER PROTECTION (LOOP) DURING EDG | | TESTING. AS A RESULT, POSSIBLE OVERSPEED OF THE DIESEL OR FAILURE OF THE | | SEQUENCER TO RECOGNIZE A LOOP MAY OCCUR DURING EDG TESTING CONCURRENT WITH | | A LOOP. SHORT TERM CORRECTIVE ACTIONS INCLUDE: | | | | 1. VERIFYING STABLE GRID PRIOR TO PARALLELING THE DIESEL AND, | | 2. DECLARING THE DIESEL INOPERABLE DURING THE TEST PER T.S. 3.8.1. | | | | LONG TERM CORRECTIVE ACTIONS WILL INCLUDE MODIFICATION TO ELIMINATE THIS | | POTENTIAL FAILURE." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31406 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 12/04/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 16:05 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 12/04/96 | +------------------------------------------------+EVENT TIME: 15:25[EST]| |NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 12/04/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 IDENTIFIED DURING A PROCEDURAL REVIEW A COMMON MODE FAILURE | | SCENARIO INVOLVING THE AIR HANDLER (AH) EQUIPMENT FOR THE REACTOR AUXILIARY | | BUILDING (RAB). | | | | "A COMMON MODE FAILURE EXISTS FOR THE RAB ELECTRICAL EQUIPMENT PROTECTION | | FAN AH-16 (1A-SA) AND AH-16 (1B-SB). THE 'COMMON MODE FAILURE' IS THAT | | ONLY ONE FIRE DETECTION ZONE (1-151) IS USED AS A PERMISSIVE IN THE START | | CIRCUIT OF BOTH SAFETY TRAINS. AS SHORT TERM CORRECTIVE MEASURES, THE | | MAINTENANCE SURVEILLANCE PROCEDURES WILL BE REVISED TO ENSURE ONLY ONE | | TRAIN OF VENTILATION IS MADE INOPERABLE AND PROCEDURES ARE BEING REVISED TO | | BYPASS THE PERMISSIVE AND RESTART THE AH-16 FANS IF A FAILURE OCCURS DURING | | AN EMERGENCY. LONG TERM CORRECTIVE ACTIONS WILL BE TO MODIFY THE PLANT TO | | RESOLVE THIS CONCERN." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31407 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 12/04/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:03 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 12/04/96 | +------------------------------------------------+EVENT TIME: 16:50[EST]| |NRC NOTIFIED BY: WILLIAM McCOLLUM |LAST UPDATE DATE: 12/04/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A SINGLE FAILURE VULNERABILITY OF THE UNIT 1 | | STANDBY GAS TREATMENT SYSTEM. | | | | "ADVERSE CONDITION REPORT #M1-96-0995 IDENTIFIED A SINGLE FAILURE | | VULNERABILITY OF THE STANDBY GAS TREATMENT SYSTEM (SGTS). DURING DRYWELL | | VENT/PURGE OPERATIONS, A FAILURE OF 1-AC-10 TO CLOSE ON AN SGTS INITIATION | | WOULD NOT GUARANTEE SGTS COULD ACHIEVE THE REQUIRED .25 INCHES Wg NEGATIVE | | DIFFERENTIAL PRESSURE IN THE REACTOR BUILDING, IF THE SGTS INITIATION | | RESULTED FROM A SIGNAL FROM THE RADIATION MONITORS. | | | | THE REDUCTION IN REACTOR BUILDING NEGATIVE PRESSURE UNDER THE ABOVE | | SCENARIO RESULTS FROM THE FACT THAT ON AN SGTS INITIATION FROM THE RAD | | MONITORS, AN ISOLATION SIGNAL IS NOT GENERATED TO CLOSE THE ATMOSPHERIC | | CONTROL SYSTEM VALVES. 1-AC-10 IS THE ONLY VALVE TO CLOSE IN THIS | | CONDITION, AND ITS ISOLATION IS CAUSED BY AN ELECTRICAL INTERLOCK BETWEEN | | 1-AC-10 AND 1-SG-1A AND 1B. THEREFORE, IF 1-AC-10 FAILS TO CLOSE DUE TO A | | MECHANICAL OR ELECTRICAL MALFUNCTION, THE FLOW PATH TO SGTS IS | | SIMULTANEOUSLY ALIGNED TO BOTH PRIMARY AND SECONDARY CONTAINMENT. THIS | | ALIGNMENT REDUCES THE SGTS FLOW FROM THE REACTOR BUILDING RESULTING IN A | | REDUCED BUILDING NEGATIVE PRESSURE. | | | | REVIEW OF THIS ISSUE BY TECH SUPPORT CONCLUDES THAT THE CONDITION IS | | REPORTABLE UNDER THE REQUIREMENTS OF 50.72(b)(1)(ii) SINCE FAILURE OF | | 1-AC-10 TO CLOSE DURING A SGTS INITIATION WOULD COMPROMISE THE ABILITY OF | | SGTS TO MAINTAIN THE REQUIRED .25 INCHES Wg NEGATIVE DIFFERENTIAL PRESSURE | | IN THE REACTOR BUILDING DURING ACCIDENTS WHICH WOULD CAUSE SGTS TO INITIATE | | FROM THE RAD MONITORS (e.g. FUEL HANDLING). THIS CONDITION IS OUTSIDE THE | | DESIGN BASIS OF THE PLANT." | | | | THE LICENSEE HAS CORRECTIVE ACTIONS UNDER REVIEW AND HAS INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 31408 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ABB INDUSTRIAL SYSTEMS |NOTIFICATION DATE: 12/04/96 | | CITY: COLUMBUS REGION: 3 |NOTIFICATION TIME: 18:00 [ET]| | COUNTY: FRANKLIN STATE: OH |EVENT DATE: 12/02/96 | |LICENSE#: 34-0025503 AGREEMENT: N |EVENT TIME: 15:30[EST]| | DOCKET: |LAST UPDATE DATE: 12/04/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MONTE PHILLIPS RDO | | |FREDERICK COMBS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: GATTONE (R III)/ALLGEIER |GLENN MEYER (RI) RDO | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT 1605 HOURS, ABB INDUSTRIAL SYSTEMS LOCATED IN COLUMBUS, OHIO, INFORMED | | AN NRC REGION III RADIATION SPECIALIST (BOB GATTONE) THAT TWO SOURCES | | ENROUTE TO BEIJING, CHINA, WERE BELIEVED MISSING. ABB FOLLOWED UP BY | | MAKING A COURTESY NOTIFICATION TO THE NRC OPERATIONS CENTER INCLUDING A | | CHRONOLOGY. BOTH MISSING SOURCES ARE TYPICALLY USED TO GAUGE THICKNESS IN | | THE PAPER MANUFACTURING PROCESS. | | | | THE FIRST MISSING SOURCE IS 70mCi OF STRONTIUM-90 (SPECIAL FORM), MODEL | | S18, PACKED IN A TYPE "A" CONTAINER (4-1/2 GALLON STEEL DRUM). SURFACE | | RADIATION READINGS WERE 3mR/Hr WITH A TRANSPORTATION INDEX OF 0.1. ON | | 9/17/96, THIS SOURCE WAS SHIPPED FROM ABB IN COLUMBUS, OHIO, VIA FEDERAL | | EXPRESS TO THE STREAMLINE COMPANY, A SHIPPER, LOCATED IN LOS ANGELES, CA. | | ON 10/23, STREAMLINE, UNABLE TO COMPLETE SHIPPING, TURNED OVER THE SHIPMENT | | TO THE EXPEDITORS COMPANY, ANOTHER SHIPPER, LOS ANGELES OFFICE. THEY, IN | | TURN, FORWARDED THE SHIPMENT TO THEIR COLUMBUS, OHIO, OFFICE WHERE IT WAS | | RECEIVED ON 10/31. AC EXPRESS, A THIRD SHIPPER, ACCEPTED THE SHIPMENT ON | | 11/1 FOR TRANSFER TO AIR CHINA AT JFK AIRPORT IN NEW YORK WITH A SCHEDULED | | FLIGHT DEPARTURE OF 11/24. WHEN AC EXPRESS ACCEPTED THE SHIPMENT THEY | | INFORMED EXPEDITORS THAT THE SHIPPING DOCUMENTS WERE MISSING. EXPEDITORS, | | IN TURN, NOTIFIED ABB WHO PROVIDED THEM WITH REPLACEMENT DOCUMENTS ON 11/7. | | ON 11/21 EXPEDITORS SENT THE REPLACEMENT DOCUMENTS TO AC EXPRESS, NEW YORK. | | ON 11/25 AC EXPRESS ADVISED EXPEDITORS THAT THE SHIPMENT COULD NOT BE | | LOCATED. THE ABB SHIPPING DEPARTMENT WAS ALSO INFORMED ON 11/25, HOWEVER, | | THE RADIOLOGICAL OPERATIONS MANAGER DID NOT LEARN OF THIS PROBLEM UNTIL | | 1530 HOURS ON 12/2. | | | | THE SECOND MISSING SOURCE IS 250mCi KRYPTON-85 (GASEOUS), MODEL S11, PACKED | | IN A TYPE "A" CONTAINER. SURFACE RADIATION READINGS WERE 0.2 mR/Hr. ON | | 10/22/96, THIS SOURCE WAS SHIPPED FROM ABB IN COLUMBUS, OHIO, TO THE | | EXPEDITORS COMPANY, COLUMBUS, OHIO, OFFICE. IT IS NOT CLEAR WHETHER FEDEX | | HANDLED THE SHIPMENT. AC EXPRESS ACCEPTED THE SHIPMENT ON 11/1. IDENTICAL | | CIRCUMSTANCES OCCURRED WITH THIS SHIPMENT AS DESCRIBED ABOVE INCLUDING THE | | LOST SHIPPING DOCUMENTS. | | | | ON 11/25, AC EXPRESS COMMENCED AN ALL STATION TRACE FOR BOTH MISSING | | SHIPMENTS WITH NO RESULTS AS OF 12/4. | | | | THE LICENSEE NOTED THAT BOTH SHIPMENTS POSE NO THREAT TO PUBLIC HEALTH OR | | SAFETY. HOWEVER, IF THE SOURCES WERE REMOVED FROM THEIR SHIELDED | | CONTAINERS, CONTACT EXPOSURES IN THE RANGE OF 10,000 RADS/HR BETA WOULD BE | | EXPECTED. NEITHER SOURCE HAS A LOCKING DEVICE TO PREVENT TAMPERING. THE | | LICENSEE IDENTIFIED THAT THE STRONTIUM-90 SOURCE WAS LICENSED MATERIAL | | GREATER THAN 1,000 TIMES THE QUANTITY SPECIFIED IN APPENDIX C TO PART 20. | | | | SEE HOO LOG FOR TELEPHONE NUMBERS. | | | | R1DO (MEYER) CONTACTED REGION I STAFF TO ENSURE STATE OF NEW YORK WAS | | NOTIFIED. | +------------------------------------------------------------------------------+