U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/28/97 - 05/29/97 ** EVENT NUMBERS ** 32386 32390 32394 32398 32399 32400 32401 32402 32403 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32386 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/24/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/23/97 | +------------------------------------------------+EVENT TIME: 23:49[CDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSEN RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MINIMUM SECURITY PERSONNEL STAFFING REQUIREMENTS WERE NOT MET DUE TO A | | FITNESS-FOR-DUTY ISSUE WITH ONE MEMBER OF THE SECURITY STAFF. A REPLACEMENT | | SECURITY STAFF MEMBER HAS BEEN CONTACTED AND IS EN ROUTE TO THE SITE. | | (REFER TO HOO LOG FOR ADDITIONAL DETAILS.) | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * 1225 MAY 28, 1997, UPDATE FROM STEVE ROONEY RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. THE LICENSEE'S | | INVESTIGATION DETERMINED THAT SUFFICIENT NUMBERS OF SECURITY FORCE | | PERSONNEL AND ARMED RESPONSE PERSONNEL WERE ON SITE AND ON DUTY AT ALL | | TIMES AND THAT THE ORIGINAL REPORT WAS MADE IN ERROR. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (JACOBSON). (REFER TO THE HOO LOG FOR A SITE | | CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32390 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 05/25/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 14:34 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/25/97 | +------------------------------------------------+EVENT TIME: 13:25[CDT]| |NRC NOTIFIED BY: MIKE GALLE |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS DECKER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 IDENTIFIED SEVERAL MOV CONTROL POWER WIRING DISCREPANCIES WHICH | | COULD POTENTIALLY AFFECT THEIR ABILITY TO REMOTELY OPERATE THESE VALVES | | FROM THE HOT SHUTDOWN PANEL. | | | | "WHILE UNIT 2 WAS AT 100% POWER, AT 1325CDT ON 5/25/97, THE EXISTENCE OF A | | CONDITION THAT IS OUTSIDE THE DESIGN BASIS OF THE PLANT WAS IDENTIFIED IN | | THAT THE CONTROL CIRCUIT FOR MOV-8000A (PORV BLOCK VALVE) IS WIRED WITH THE | | CONTROL POWER FUSES FOR LOCAL AND REMOTE OPERATION CONNECTED IN SERIES. | | WITH THIS ARRANGEMENT, FAILURE OF THE FUSE FOR REMOTE (MAIN CONTROL BOARD) | | OPERATION WOULD PREVENT LOCAL (HOT SHUTDOWN PANEL) OPERATION. THIS | | CONDITION POTENTIALLY EXISTS FOR FOUR OTHER MOV's." | | | | THE CAUSE IS ATTRIBUTED TO PERSONNEL ERROR WHILE IMPLEMENTING A DESIGN | | CHANGE IN 1985. THE CONTROL CIRCUIT WAS NOT WIRED PER DESIGN. CORRECTIVE | | ACTIONS INCLUDE REWIRING THE CONTROL CIRCUIT TO CONFORM WITH PLANT DESIGN | | (IN PROGRESS) AND INSPECTING/REPAIRING FOUR OTHER POTENTIALLY AFFECTED | | MOV's, i.e., MOV-8000B (PORV BLOCK VALVE), LCV-115-B, D (RWST-CHARGING PUMP | | SUCTION VALVES) AND T1P17-MOV-3047 (CCW-MISCELLANEOUS HEADER ISOLATION | | VALVE). | | | | UNIT 2 HAS DECLARED MOV-8000A INOPERABLE AND ENTERED TECH SPEC 3.4.5 ACTION | | STATEMENT D WHICH REQUIRES THAT WITH ONE BLOCK VALVE INOPERABLE WITHIN 1 | | HOUR RESTORE THE BLOCK VALVE TO OPERABLE STATUS OR PLACE ITS ASSOCIATED | | PORV IN MANUAL CONTROL AND RESTORE THE INOPERABLE BLOCK VALVE TO OPERABLE | | STATUS WITHIN 72 HOURS OR BE WITHIN AT LEAST HOT STANDBY WITHIN THE NEXT 6 | | HOURS AND HOT SHUTDOWN WITHIN THE FOLLOWING 6 HOURS. THE LICENSEE IS | | MAKING REPAIRS WITH MOV-8000A IN THE OPEN POSITION AND WILL CONTINUE | | OPERATING AT 100% POWER. AT LEAST ONE VALVE WAS IDENTIFIED ON UNIT 1 IN A | | SIMILAR CONDITION; HOWEVER, SINCE UNIT 1 IS CURRENTLY IN MODE 5, THIS | | CONDITION IS NOT REPORTABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 05/28/97 @ 1123 EDT BY MIKE GALLE TAKEN BY MACKINNON * * * | | | | THE DATE OF THE DESIGN CHANGE IN THE THIRD PARAGRAPH WAS IN ERROR AND IT | | WAS CHANGED FROM 1995 TO "1985". R2DO (CHUCK HOSEY) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32394 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/27/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 12:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/27/97 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: EDDIE JONES |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK HOSEY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SEVERAL 'B' TRAIN ENGINEERED SAFETY FEATURE (ESF) COMPONENTS STARTED | | UNEXPECTEDLY DURING DIESEL GENERATOR SEQUENCER 'B' TIMER CALIBRATION | | TESTING. | | | | THE DIESEL GENERATOR SEQUENCER TIMER CALIBRATION TEST IS PERFORMED YEARLY, | | AND THIS IS THE FIRST TIME THIS TEST PROCEDURE HAS BEEN USED SINCE IT WAS | | REVISED. | | | | SEVERAL ESF COMPONENTS ACTUATED UNEXPECTEDLY DURING THE PERFORMANCE OF THE | | 'B' TRAIN DIESEL GENERATOR SEQUENCER TIMER CALIBRATION TEST. THERE WAS NO | | INJECTION TO THE REACTOR COOLANT SYSTEM SINCE NONE OF THE SAFETY INJECTION | | VALVES RECEIVED AN AUTOMATIC OPEN SIGNAL. THE TURBINE-DRIVEN AUXILIARY | | FEEDWATER PUMP STARTED AND INJECTED TO THE STEAM GENERATORS. (THIS DID | | NOT AFFECT THE REACTOR SIDE OF THE PLANT.) THE '1B' NUCLEAR DECAY PUMP | | (RHR) AUTOMATICALLY STARTED. THE '1B1' AND '1B2' COMPONENT COOLING WATER | | PUMPS AUTOMATICALLY STARTED. THE '1BNV' AND '1BNI' HIGH PRESSURE AND | | INTERMEDIATE PRESSURE INJECTION PUMPS AUTOMATICALLY STARTED. THE '1BUCYC' | | STANDBY CONTROL ROOM CHILLER SAFETY ALIGNED BUT DID NOT START, AND THE | | STEAM GENERATOR BLOWDOWN ISOLATION VALVES ISOLATED. | | | | THE DIESEL GENERATOR ASSOCIATED WITH THE SEQUENCER THAT WAS BEING TESTED | | DID NOT START BECAUSE IT WAS TAGGED OUT OF SERVICE PER THE SEQUENCER TIMER | | CALIBRATION TEST. THE LICENSEE IS CURRENTLY REVIEWING THE DIESEL GENERATOR | | SEQUENCER TIMER CALIBRATION TEST PROCEDURE TO FIND OUT IF THE PROCEDURE HAS | | ANY ERRORS. | | | | THE LICENSEE REDUCED POWER FROM 100% TO 97% IN ORDER TO REDUCE CONTAINMENT | | TEMPERATURE WHICH IS UNRELATED TO THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1514 MAY 28, 1997, UPDATE FROM MIKE CASH RECEIVED BY TROCINE * * * | | | | THIS UPDATE WAS SUBMITTED BY THE LICENSEE IN ORDER TO PROVIDE EDITORIAL | | CORRECTIONS AND ADDITIONAL DESCRIPTIONS REGARDING THE EVENT. | | | | THE FOLLOWING TEXT IS FROM A PORTION OF A FACSIMILE RECEIVED FROM THE | | LICENSEE: | | | | "DURING PERFORMANCE OF DIESEL GENERATOR SEQUENCER RELAY TESTING BY | | [LICENSEE] PERSONNEL ON 05/27/97, A PARTIAL BLACKOUT SIGNAL WAS GENERATED | | ON THE 'B' ESSENTIAL BUS. THIS SIGNAL RESULTED IN VARIOUS ESF RELATED | | VALVES AND COMPONENTS [CHANGING] CONFIGURATION. THE SIGNAL ALSO RESULTED | | IN AN [AUTOMATIC] START OF THE TURBINE-DRIVEN AUXILIARY FEEDWATER (TDCA) | | PUMP. THE REACTOR OPERATOR AT THE CONTROLS (ROATC) USED MODULATING RESET | | TO GAIN MANUAL CONTROL OF THE TDCA CONTROL VALVES. THE TDCA CONTROL VALVES | | WERE THROTTLED CLOSED TO PLACE THE TDCA PUMP INTO RECIRCULATION. WITH THE | | TDCA CONTROL VALVES LESS THAN FULL OPEN AT REACTOR POWER ABOVE 10%, | | PROCEDURES REQUIRE THAT THE TDCA PUMP BE DECLARED INOPERABLE. THE | | MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP WAS INOPERABLE AS A RESULT OF THE | | SEQUENCER TESTING. TWO INOPERABLE AUXILIARY FEEDWATER PUMPS REQUIRED THE | | UNIT TO ENTER [TECHNICAL SPECIFICATION] ACTION STATEMENT 3.7.1.2.b WHICH | | REQUIRES [THAT THE UNIT BE PLACED IN A] HOT STANDBY [CONDITION] WITHIN 6 | | HOURS AND [A] HOT SHUTDOWN [CONDITION] WITHIN THE FOLLOWING 6 HOURS." | | | | "WHILE SECURING FROM THE TEST, [LICENSEE] PERSONNEL CAUSED A PARTIAL SAFETY | | INJECTION SIGNAL WHICH RESULTED IN AN [AUTOMATIC] START OF [THE] SAFETY | | INJECTION PUMPS. HOWEVER, A COMPLETE SAFETY INJECTION VALVE ALIGNMENT WAS | | NOT PRESENT, AND THERE WAS NO RESULTING SAFETY INJECTION INTO THE REACTOR | | COOLANT SYSTEM. THE [TDCA] PUMP WAS RETURNED TO OPERABLE STATUS, AND THE | | STATION EXITED TECHNICAL SPECIFICATION ACTION [STATEMENT] 3.7.1.2.b. THE | | ESF VALVES AND SAFETY INJECTION PUMPS WERE RETURNED TO NORMAL ALIGNMENT." | | | | "THE PLANT CONTINUED TO OPERATE ON MODE 1 AT APPROXIMATELY 100% POWER | | DURING THE ESF ACTUATION." | | | | "THIS EVENT IS REPORTABLE UNDER THE CRITERIA OF 10CFR50.72(b)(2)(ii), ANY | | EVENT OR CONDITION THAT RESULTS IN MANUAL OR AUTOMATIC ACTUATION OF ANY | | [ESF] INCLUDING THE REACTOR PROTECTION SYSTEM. A LICENSEE EVENT REPORT | | WILL BE GENERATED WITHIN 30 DAYS AS REQUIRED BY 10CFR50.73(a)(2)(iv)." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (HOSEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32398 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 05/28/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 07:59 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/28/97 | +------------------------------------------------+EVENT TIME: 06:40[CDT]| |NRC NOTIFIED BY: KARL EHRHARDT |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 +------------------------------------------------------------------------------+ | - EMERGENCY OPERATIONS FACILITY LOST POWER FOR UNKNOWN REASONS - | | | | AT 0640 (CDT), POWER TO THE GRAND GULF EMERGENCY OPERATIONS FACILITY (EOF) | | WAS LOST. THE EOF DIESEL GENERATOR (DG) DID NOT START TO POWER THE EOF. | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE LOSS OF POWER AND THE REASON | | THE EOF DG DID NOT START. THE BACKUP EOF IS AVAILABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32399 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/28/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/27/97 | +------------------------------------------------+EVENT TIME: 11:36[EDT]| |NRC NOTIFIED BY: JOHN MILLER |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -REACTOR POWER MOMENTARILY INCREASED TO 105% DUE TO A FAILED UPS INVERTER- | | | | AT 1136 ON 05/27/97, AN ELECTRICAL FAILURE CAUSED A TRIP OF THE 'C' MAIN | | FEEDWATER HEATER STRING WHICH RESULTED IN A MAIN FEEDWATER TEMPERATURE | | DECREASE (APPROXIMATELY 100øF) AND A REACTOR POWER INCREASE. REACTOR POWER | | REACHED 105% FOR SEVERAL SECONDS BEFORE PLANT OPERATORS MANUALLY REDUCED | | POWER TO 80%. | | | | PLANT OPERATORS SUBSEQUENTLY BYPASSED THE FAILED COMPONENT, AN | | UNINTERRUPTIBLE POWER SUPPLY INVERTER, AND RESTORED ALL OTHER PLANT | | COMPONENTS TO NORMAL OPERATION. | | | | AT 0229 ON 05/28/97, PLANT OPERATORS RESTORED REACTOR POWER TO 100%. | | | | THE LICENSEE WILL REPAIR/REPLACE THE FAILED INVERTER. | | | | THIS EVENT IS A 24 HOUR REPORT; A VIOLATION OF FACILITY OPERATING LICENSEE, | | SECTION 2F (MAXIMUM POWER). | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32400 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/28/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 14:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/28/97 | +------------------------------------------------+EVENT TIME: 12:51[EDT]| |NRC NOTIFIED BY: JOHN MILLER |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE OF A HIGH PRESSURE COOLANT INJECTION MINIMUM FLOW VALVE TO CLOSE | | DURING SURVEILLANCE TESTING | | | | WHILE PERFORMING A HIGH PRESSURE COOLANT INJECTION PUMP SURVEILLANCE TEST, | | THE MINIMUM FLOW VALVE FAILED TO CLOSE, AS DESIGNED. AS A RESULT, THE | | HIGH PRESSURE COOLANT INJECTION SYSTEM WAS DECLARED INOPERABLE AT 1251, AND | | A 14-DAY TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION WAS | | ENTERED. THE LICENSEE ALSO COMMENCED TROUBLESHOOTING ON THE MINIMUM FLOW | | VALVE FLOW TRANSMITTER. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND THE LOWER | | ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32401 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: HARBIN CLINIC, ROME, GEORGIA |NOTIFICATION DATE: 05/28/97 | | CITY: ROME REGION: 2 |NOTIFICATION TIME: 16:51 [ET]| | COUNTY: FLOYD STATE: GA |EVENT DATE: 05/28/97 | |LICENSE#: GA1278-1 AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/28/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES HOSEY, REG 2 RDO | | | | +------------------------------------------------+ROBERT BORES, REG 1 RDO | |NRC NOTIFIED BY: RICHARD WOODRUFF/REGION 2 |JOHN JACOBSON, REG 3 RDO | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING CONTAMINATED LEAD APRONS AT THE HARBIN | | CLINIC LOCATED IN ROME, GEORGIA | | | | AT APPROXIMATELY 1500, THE STATE OF GEORGIA RECEIVED A REPORT FROM THE | | HARBIN CLINIC (A NUCLEAR MEDICAL FACILITY LOCATED IN ROME, GEORGIA) | | REGARDING CONTAMINATED LEAD APRONS. THE STATE OF GEORGIA (TOM HILL) | | NOTIFIED THE NRC REGION 2 OFFICE (RICHARD WOODRUFF) AT APPROXIMATELY 1600. | | THE NRC REGION 2 OFFICE (RICHARD WOODRUFF) NOTIFIED THE NRC OPERATIONS | | CENTER AT 1651. | | | | IT WAS REPORTED THAT THE CONTAMINATED LEAD APRONS WERE NEW AND THAT THEY | | HAD UNIFORM RADIATION (1 MILLIREM ON CONTACT). THE APRONS WERE PURCHASED | | FROM PICKER X-RAY LOCATED IN OHIO AND WERE MANUFACTURED BY EZ-EM LOCATED IN | | PORT CHESTER, NEW YORK. THE LEAD USED IN MANUFACTURING THE APRONS CAME | | FROM BAR-RAY LOCATED IN LITTLESTOWN, PENNSYLVANIA. | | | | THE STATE OF GEORGIA PLANS TO SEND A REPRESENTATIVE TO HARBIN CLINIC TO | | PICK UP AN APRON FOR ANALYSIS. THE STATE OF GEORGIA ALSO NOTIFIED THE | | STATES OF NEW YORK AND PENNSYLVANIA, AND IT WAS REPORTED THAT THE STATES OF | | NEW YORK AND PENNSYLVANIA ARE FOLLOWING UP ON THIS ISSUE. | | | | THE NRC REGION 2 OFFICE NOTIFIED THE NRC REGION 1 OFFICE (CRAIG GORDON), | | NRC OFFICE REGION 3 (MONTE PHILLIPS), AND NRC OFFICE OF STATE PROGRAMS | | (LLOYD BOLLING). THE NRC REGION 2 OFFICE ALSO PLANS TO ISSUE A PRELIMINARY | | NOTIFICATION REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32402 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 05/28/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 19:06 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/28/97 | +------------------------------------------------+EVENT TIME: 16:07[EDT]| |NRC NOTIFIED BY: HAROLD BRUGH |LAST UPDATE DATE: 05/28/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF THE RELEASE OF FREON DUE TO A HEATING VENTILATION | | AND AIR CONDITIONING LINE FAILURE | | | | A BREAK IN THE DISCHARGE LINE OF A NON-SAFETY-RELATED CONDENSING UNIT | | CAUSED THE RELEASE OF 53 POUNDS OF REFRIGERANT 22 (FREON). THIS AMOUNT | | WAS IN EXCESS OF THE COMPREHENSIVE ENVIRONMENTAL RESPONSE COMPENSATION | | AND LIABILITY ACT REPORTABLE QUANTITY LIMIT OF 1 POUND. AS A RESULT, THE | | LICENSEE NOTIFIED THE NATIONAL RESPONSE CENTER, LOCAL EMERGENCY PLANNING | | VIA THE VAN BUREN COUNTY SHERIFF, AND THE POLLUTION EMERGENCY ALERT SYSTEM. | | THE LEAK HAS BEEN ISOLATED, AND THE LICENSEE PLANS TO REPAIR THE CONDENSING | | UNIT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32403 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/28/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:22 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/28/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 06:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/28/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN JACOBSON RDO | | DOCKET: 0707002 | | +------------------------------------------------+ | |NRC NOTIFIED BY: RON CRABTREE | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CRITICALITY CONTROL 24-HOUR REPORT (BULLETIN 91-01) PER PROCEDURE | | UE2-RA-RE1030, APPENDIX D, SECTION 4(a) | | | | AT 0600, CHEMICAL OPERATIONS PERSONNEL DISCOVERED USED HEPA FILTERS LAYING | | WITHIN A MAINTENANCE BOUNDARY AREA IN THE X-333 PROCESS BUILDING THAT WERE | | NOT SPACED 2 FEET EDGE TO EDGE AS REQUIRED. THIS LACK OF PROPER SPACING | | REPRESENTED A LOSS OF ONE REQUIRED CONTROL OR CONTINGENCY BECAUSE THE | | NON-DESTRUCTIVE ANALYSIS MEASUREMENTS HAD NOT BEEN COMPLETED UPON FILTER | | REMOVAL TO DETERMINE THAT THE TOTAL URANIUM-235 WAS A SAFE MASS. | | | | THE FILTERS WERE IMMEDIATELY SPACED 2 FEET EDGE TO EDGE TO MEET THE | | REQUIREMENTS, AND A NON-DESTRUCTIVE ANALYSIS WAS PERFORMED. THE ESTIMATED | | AMOUNT OF MATERIAL INVOLVED IN THIS EVENT WAS 32 GRAMS OF URANIUM-235 AT 3% | | TO 5% ENRICHMENT. THE PROCESS LIMIT FOR THAT AREA OF THE X-333 PROCESS | | BUILDING WAS 10% ENRICHMENT. THE MINIMUM CRITICAL MASS OF URANIUM-235 AT | | THIS ENRICHMENT LEVEL WAS 720 GRAMS. | | | | PORTSMOUTH NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT OF ENERGY | | REPRESENTATIVE ON SITE. | +------------------------------------------------------------------------------+