U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/06/97 - 02/07/97
** EVENT NUMBERS **
31739 31740 31741 31742 31743 31744 31745 31746
+----------------------------------+ +-----------------------+
|POWER REACTOR | |EVENT NUMBER: 31739 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/06/97 |
|UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 13:39 [ET]|
|RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/06/97 |
+------------------------------------------------+EVENT TIME: 11:00[EST]|
|NRC NOTIFIED BY: DAVE NEFF |LAST UPDATE DATE: 02/06/97 |
|HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+ NOTIFICATIONS |
|EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+
|10 CFR SECTION: |MICHAEL MODES 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | | |
| 2 | N N 0 REFUELING | 0 REFUELING |
| | | |
+-----+---------------------------------------------+--------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - DISCOVERY OF SIX STUCK STEAM FLOODING HVAC DAMPERS - |
| |
| ON 02/06/97, THE LICENSEE IDENTIFIED THAT UNIT 2 MAY HAVE OPERATED IN |
| AN UNANALYZED CONDITION THAT COULD HAVE ADVERSELY IMPACTED PLANT SAFETY. |
| WHILE PERFORMING PREVENTIVE MAINTENANCE ACTIVITIES DURING THE ONGOING |
| UNIT 2 REFUELING OUTAGE, THE LICENSEE IDENTIFIED SIX STEAM FLOODING HVAC |
| DAMPERS THAT WOULD NOT FUNCTION. EXCESSIVE FRICTION IN EITHER THE SOLENOID |
| OR ASSOCIATED BUSHING APPEARS TO BE THE CAUSE OF THE FAILURES. |
| |
| THESE SPECIFIC DAMPERS ARE LOCATED IN THREE VENTILATION DUCT WORK |
| PENETRATIONS IN THE WALLS SURROUNDING THE OUTBOARD MAIN STEAM ISOLATION |
| VALVE (MSIV) ROOM. EACH WALL PENETRATION HAS TWO STEAM FLOODING HVAC |
| DAMPERS ARRANGED IN SERIES. THE DAMPERS ARE REQUIRED TO CLOSE FOLLOWING A |
| HIGH ENERGY STEAM LINE BREAK (HELB) IN THE OUTBOARD MSIV ROOM TO PROTECT |
| SAFETY-RELATED EQUIPMENT IN THE ADJOINING ROOM. TWO OF THE HVAC WALL |
| PENETRATIONS COMMUNICATE WITH THE ADJOINING ROOM ON ELEVATION 253 OF THE |
| REACTOR ENCLOSURE, AND THE OTHER HVAC WALL PENETRATION IS CONNECTED TO DUCT |
| WORK LOCATED IN THE NEXT HIGHER FLOOR ON ELEVATION 283. |
| |
| THE LICENSEE HAS NO ANALYSIS FOR AN HELB IN THE OUTBOARD MSIV ROOM |
| COINCIDENT WITH THE STEAM TRAVELING TO THE ADJACENT ROOMS ON ELEVATIONS 253 |
| OR 283. SAFETY-RELATED EQUIPMENT LOCATED IN THE ADJOINING ROOM ON |
| ELEVATION 253 INCLUDES THE SCRAM SOLENOIDS AND HYDRAULIC CONTROL UNITS, |
| REDUNDANT REACTIVITY CONTROL SYSTEM SOLENOIDS, AND SEVERAL EMERGENCY CORE |
| COOLING SYSTEM MOTOR-OPERATED VALVE ELECTRICAL BREAKERS. IF AN HELB HAD |
| OCCURRED IN THE OUTBOARD MSIV ROOM AND IF THE DAMPERS HAD FAILED TO CLOSE, |
| THE ABILITY TO SHUT THE PLANT DOWN MAY HAVE BEEN ADVERSELY IMPACTED. |
| |
| THE LICENSEE HAS NOT PERFORMED A CALCULATION TO DETERMINE THE ACTUAL |
| TEMPERATURE, PRESSURE, AND HUMIDITY CONDITIONS THAT COULD RESULT FROM THIS |
| SCENARIO. BASED ON ENGINEERING JUDGMENT, THE LICENSEE HAS CONCLUDED THAT |
| THIS UNANALYZED CONDITION MAY ADVERSELY IMPACT PLANT SAFETY. |
| |
| CURRENTLY, THE UNIT 2 HVAC STEAM FLOODING DAMPERS ARE NOT REQUIRED TO BE |
| FUNCTIONAL WHILE UNIT 2 IS SHUTDOWN. THE LICENSEE IS REVIEWING THE OTHER |
| UNIT 2 HVAC STEAM FLOODING DAMPERS AND THE UNIT 1 HVAC STEAM FLOODING |
| DAMPERS. (UNIT 1 IS PRESENTLY OPERATING AT 100% POWER.) |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|POWER REACTOR | |EVENT NUMBER: 31740 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/06/97 |
|UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:55 [ET]|
|RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/06/97 |
+------------------------------------------------+EVENT TIME: 15:35[EST]|
|NRC NOTIFIED BY: JOHN WEBERS |LAST UPDATE DATE: 02/06/97 |
|HQ OPS OFFICER: RUDY KARSCH +-----------------------------+
+------------------------------------------------+ NOTIFICATIONS |
|EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+
|10 CFR SECTION: |MICHAEL MODES 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
+------------------------------------------------------------------------------+
| PIPING SUPPORTS FOR THE REACTOR BUILDING CLOSED COOLING WATER SYSTEM INSIDE |
| PRIMARY CONTAINMENT DO NOT MEET THE FINAL SAFETY ANALYSIS REPORT SEISMIC |
| REQUIREMENTS. A DESIGN BASIS SEISMIC LOAD WOULD EXCEED THE PIPE SUPPORTS' |
| ALLOWABLE STRESS LOADING. THE SUPPORTS DO CONFORM TO ASME CODE |
| REQUIREMENTS, SO THE LICENSEE PLANS TO KEEP THE UNIT AT POWER. CORRECTIVE |
| ACTION WILL BE DETERMINED. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31741 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|LICENSEE: U.S. AIR FORCE |NOTIFICATION DATE: 02/06/97 |
| CITY: TUCSON REGION: 4 |NOTIFICATION TIME: 17:21 [ET]|
| COUNTY: STATE: AZ |EVENT DATE: 01/01/96 |
|LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 00:00[MST]|
| DOCKET: |LAST UPDATE DATE: 02/06/97 |
| +-----------------------------+
| |PERSON ORGANIZATION|
| |THOMAS KOZAK, REG. 3 RDO |
| | |
+------------------------------------------------+PHIL HARRELL, REG. 4 RDO |
|NRC NOTIFIED BY: PAUL FEESER | |
|HQ OPS OFFICER: RUDY KARSCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NOT APPLICABLE | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------+-----------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DAVIS-MONTHAN AIR FORCE BASE, TUCSON, ARIZONA |
| |
| AN INVENTORY OF TRITIUM EXIT SIGNS DETERMINED THAT ONE SIGN WAS MISSING. |
| THE SIGN WAS PROBABLY LOST DURING BUILDING RENOVATION CONDUCTED IN JANUARY |
| OF 1996. THE SIGN CONTAINED 20 CURIES OF TRITIUM. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31742 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|LICENSEE: U.S. AIR FORCE |NOTIFICATION DATE: 02/06/97 |
| CITY: SACRAMENTO REGION: 4 |NOTIFICATION TIME: 17:21 [ET]|
| COUNTY: STATE: CA |EVENT DATE: 02/06/97 |
|LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 14:20[PST]|
| DOCKET: |LAST UPDATE DATE: 02/06/97 |
| +-----------------------------+
| |PERSON ORGANIZATION|
| |THOMAS KOZAK, REG. 3 RDO |
| | |
+------------------------------------------------+PHIL HARRELL, REG. 4 RDO |
|NRC NOTIFIED BY: PAUL FEESER | |
|HQ OPS OFFICER: RUDY KARSCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NOT APPLICABLE | |
|10 CFR SECTION: | |
|NMAT MATL IN UNCNTRL AREA | |
| | |
| | |
| | |
| | |
+------------------------------------------------+-----------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| McCLELLAN AIR FORCE BASE, SACRAMENTO, CALIFORNIA |
| |
| AN INDIVIDUAL FOUND A SMALL BOX IN AN UNUSED BUILDING ON THE BASE. UPON |
| EXAMINATION OF THE CONTENTS OF THE BOX, THE INDIVIDUAL DISCOVERED THREE |
| STRONTIUM-90 SOURCES ENCASED IN EPOXY. THE EPOXY WAS CRUMBLY AND FELL |
| APART DURING HANDLING. SUBSEQUENTLY, THE INDIVIDUAL ATE A DOUGHNUT AND |
| LATER DETERMINED THAT THE MATERIAL HE HAD BEEN HANDLING WAS RADIOACTIVE. |
| |
| THE LICENSEE HAS DETERMINED THAT THE APPROXIMATE CURIE CONTENT OF THE THREE |
| SOURCES WAS ONE MILLICURIE. BIO-ASSAYS WILL BE CONDUCTED FOR THE EXPOSED |
| INDIVIDUAL SINCE INGESTION MAY HAVE OCCURRED. THE INDIVIDUAL WAS NOT |
| WEARING ANY DOSIMETRY. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|POWER REACTOR | |EVENT NUMBER: 31743 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 02/06/97 |
|UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 17:25 [ET]|
|RX TYPE: [2] GE-4 |EVENT DATE: 02/06/97 |
+------------------------------------------------+EVENT TIME: 11:00[EST]|
|NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 02/06/97 |
|HQ OPS OFFICER: RUDY KARSCH +-----------------------------+
+------------------------------------------------+ NOTIFICATIONS |
|EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+
|10 CFR SECTION: |THOMAS KOZAK RDO |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
| | |
+-----+----------+-------+--------+--------------+--+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN |
| | | |
| | | |
+-----+---------------------------------------------+--------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE DISCOVERED AN ERROR IN THE COMPUTER PROGRAM USED TO CALCULATE |
| REACTOR THERMAL POWER. THIS ERROR COULD HAVE LED THE LICENSEE TO EXCEED |
| 100% POWER ON SEVERAL OCCASIONS. |
| |
| THE DENSITY COMPENSATION ALGORITHM IN THE PROCESS COMPUTER FOR CONVERSION |
| OF DIFFERENTIAL PRESSURE DATA INTO MASS FLOW RATES IS INCORRECT. THE |
| ALGORITHM TERM FOR THE RATIO OF THE SPECIFIC VOLUME AT THE REFERENCE |
| TEMPERATURE AND PRESSURE WITH THE SPECIFIC VOLUME AT THE PROCESS |
| TEMPERATURE AND PRESSURE SHOULD HAVE BEEN A SQUARE ROOT TERM. THIS ERROR |
| INTRODUCES A NON-CONSERVATIVE BIAS INTO THE HEAT BALANCE CALCULATION. THE |
| AFFECTED PARAMETERS ARE REACTOR WATER CLEANUP SYSTEM MASS FLOW AND CONTROL |
| ROD DRIVE MASS FLOW. THE RESULTING ERROR IS APPROXIMATELY 0.5 MWth. |
| |
| THE LICENSEE HAS IDENTIFIED ONE OR MORE OCCASIONS IN CYCLES ONE, TWO, AND |
| THREE WHEN THE CORE THERMAL POWER LIMIT MAY HAVE BEEN EXCEEDED. THE |
| CURRENT LICENSED POWER LIMIT OF 3,430 MWth HAS NOT BEEN EXCEEDED AS A |
| RESULT OF THIS ERROR. THE LICENSEE PLANS TO CORRECT THE CALCULATIONAL |
| ALGORITHM. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|POWER REACTOR | |EVENT NUMBER: 31744 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/06/97 |
|UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:02 [ET]|
|RX TYPE: [1] GE-4 |EVENT DATE: 02/06/97 |
+------------------------------------------------+EVENT TIME: 17:15[EST]|
|NRC NOTIFIED BY: JIM BROOKS |LAST UPDATE DATE: 02/06/97 |
|HQ OPS OFFICER: RUDY KARSCH +-----------------------------+
+------------------------------------------------+ NOTIFICATIONS |
|EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+
|10 CFR SECTION: |MICHAEL MODES 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
+------------------------------------------------------------------------------+
| A SHORT CIRCUIT OF CONTACTS COULD LEAD TO FAILURE OF VALVES TO CLOSE |
| RESULTING IN A RELEASE PATHWAY. |
| |
| THE LICENSEE DETERMINED THAT A SHORT CIRCUIT ACROSS CONTACTS 5/6 IN RELAYS |
| K42 OR K43 WILL PREVENT AUTOMATIC ISOLATION OF CONTAINMENT ATMOSPHERIC |
| CONTROL SYSTEM VALVES SB-16-19-6A OR 6B, SB-16-19-7A AND 7B, AND SB-16-19-8 |
| AND 10. THIS FAILURE MODE IS NOT SELF REVEALING. IF THE VALVES ARE OPEN |
| AND A LOSS OF COOLANT ACCIDENT OCCURS, THERE WILL BE A VENT PATH BETWEEN |
| THE SUPPRESSION CHAMBER AND THE DRYWELL THAT PARTIALLY BYPASSES THE VAPOR |
| SUPPRESSION FUNCTION OF THE SUPPRESSION POOL. THE SINGLE FAILURE OF THE |
| ABOVE RELAY CONTACTS PREVENTS AUTOMATIC CLOSURE OF THESE VALVES SHOULD A |
| CONTAINMENT ISOLATION DEMAND OCCUR. REMOTE MANUAL OPERATION OF THE VALVES |
| FROM THE CONTROL ROOM IS STILL POSSIBLE. THE LICENSEE DETERMINED THAT |
| THERE IS NO CREDIBLE FAILURE THAT COULD CAUSE THE VALVES TO OPEN IF THEY |
| WERE CLOSED. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|POWER REACTOR | |EVENT NUMBER: 31745 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/06/97 |
|UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 19:39 [ET]|
|RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/06/97 |
+------------------------------------------------+EVENT TIME: 19:30[EST]|
|NRC NOTIFIED BY: PAUL BENYEDA |LAST UPDATE DATE: 02/06/97 |
|HQ OPS OFFICER: RUDY KARSCH +-----------------------------+
+------------------------------------------------+ NOTIFICATIONS |
|EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+
|10 CFR SECTION: |MICHAEL MODES 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 N 0 REFUELING | 0 REFUELING |
| | | |
| | | |
+-----+---------------------------------------------+--------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE FOUND THAT THE VENTILATION EXHAUST FAN FOR THE SOLID |
| RADIOACTIVE WASTE BUILDING DISCHARGES DIRECTLY TO THE ENVIRONMENT AND DOES |
| NOT HAVE A RADIOACTIVE MONITORING INSTRUMENT. EFFLUENT MONITORING IS |
| REQUIRED BY 10 CFR PART 20 AND BY 10 CFR PART 50, GENERAL DESIGN CRITERION |
| 64. THE LICENSEE IS INVESTIGATING CORRECTIVE ACTION. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+----------------------------------+ +-----------------------+
|POWER REACTOR | |EVENT NUMBER: 31746 |
+----------------------------------+ +-----------------------+
+------------------------------------------------+-----------------------------+
|FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 02/07/97 |
|UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 04:36 [ET]|
|RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/07/97 |
+------------------------------------------------+EVENT TIME: 01:20[EST]|
|NRC NOTIFIED BY: PAT McGINNIS |LAST UPDATE DATE: 02/07/97 |
|HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+ NOTIFICATIONS |
|EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+
|10 CFR SECTION: |CAUDLE JULIAN RDO |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
| | |
+-----+----------+-------+--------+--------------+--+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INADVERTENT START OF A MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP DURING TESTING |
| |
| DURING PERFORMANCE OF AN ENGINEERED SAFEGUARD ACTUATION TEST ON THE 'A' |
| MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP, THE PUMP WAS INADVERTENTLY STARTED. |
| THIS ACTUATION OCCURRED WHEN THE PERSONNEL INVOLVED IN THE TEST WERE |
| ENSURING THAT THE RELAY TO BE ACTUATED WAS CORRECTLY IDENTIFIED AS TO ITS |
| LOCATION AND STATE. AFTER LOCATING THE CORRECT RELAY, THE RELAY WAS |
| INADVERTENTLY TOUCHED ON THE MANUAL ACTUATION BAR. THIS CAUSED THE RELAY |
| TO PICKUP AND START THE 'A' AUXILIARY FEEDWATER PUMP. THE PUMP WAS |
| SECURED, AND THE TEST WAS SUBSEQUENTLY PERFORMED SATISFACTORILY. |
| |
| ACCORDING TO THE GUIDANCE OF NUREG 1022, THIS ACTUATION WAS INVALID BECAUSE |
| IT WAS NOT INITIATED IN RESPONSE TO ACTUAL PLANT CONDITIONS AND BECAUSE |
| THERE WAS NOT A NEED FOR THE SAFETY FUNCTION. HOWEVER, IN ACCORDANCE WITH |
| NUREG 1022, VOLUNTARY REPORTING IS REQUIRED BECAUSE THE SYSTEM (PRESSURIZED |
| WATER REACTOR AUXILIARY FEEDWATER) IS LISTED IN TABLE 2. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+