U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/07/97 - 10/08/97 ** EVENT NUMBERS ** 32886 32892 32971 33037 33038 33039 33040 33041 33042 33043 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32886 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/08/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:38 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/08/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:10[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/07/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: HALCOMB | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE STEAM SUPPLY ISOLATION DUE TO HIGH CONDENSATE ALARM | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE CERTIFICATE HOLDER: | | "ON 9/8/97 AT 0010 HOURS, OPERATIONS PERSONNEL RECEIVED A STEAM SHUTDOWN | | ALARM ON AUTOCLAVE #3 IN THE X-343 FACILITY. THE STEAM SHUTDOWN WAS CAUSED | | BY AN ACTUATION OF THE HIGH CONDENSATE ALARM (BOTH 'A' AND 'B' PROBES). | | INVESTIGATION OF THE ALARMS REVEALED THAT THE AUTOCLAVE #3 HIGH CONDENSATE | | ALARM WAS CAUSED BY AN ACTUAL HIGH CONDENSATE CONDITION. THE AUTOCLAVE | | CONDENSATE IS A 'Q' SAFETY SYSTEM IN THE X-343 FACILITY. THE ACTUATION OF | | THE AUTOCLAVE HIGH CONDENSATE SYSTEM ALARM OCCURRED WHILE THE AUTOCLAVE WAS | | IN OPERATIONAL MODE II (HEATING). THIS EVENT IS REPORTABLE TO THE NRC PER | | EVENT REPORTING PROCEDURE UE2-RA-RE1030, APPENDIX D, SECTION J, PARAGRAPH | | #2 (24 HOUR REPORT). THE X-343 AUTOCLAVE #3 WAS IMMEDIATELY SHUT DOWN AND | | DECLARED INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT. THERE WAS NO RELEASE | | OF HAZARDOUS MATERIALS OR RADIOACTIVE CONTAMINATION EXPOSURES ASSOCIATED | | WITH THIS 'Q' SYSTEM ALARM ACTUATION. THE NRC RESIDENT INSPECTOR HAS BEEN | | NOTIFIED OF THIS EVENT." | | | | * * * 1633EDT 10/7/97 FROM ERIC SPAEPH TO S. SANDIN * * * | | THE REGULATEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "UPON FURTHER INVESTIGATION OF THE HIGH CONDENSATE LEVEL SAFETY SYSTEM | | ACTUATION, IT HAS BEEN DETERMINED THAT THE ACTUATION WAS DUE TO AN INVALID | | SIGNAL. IN THIS EVENT A SPURIOUS SIGNAL FROM THE 'B' CONDENSATE LEVEL | | PROBE CAUSED THE HCLS TO ACTUATE AND ISOLATE THE STEAM SUPPLY TO THE | | AUTOCLAVE. IT IS BELIEVED THAT AFTER THE STEAM SUPPLY WAS ISOLATED, THE | | AUTOCLAVE INTERNAL PRESSURE DROPPED WHICH REDUCED THE MOTIVE FORCE NEEDED | | TO DRIVE CONDENSATE THROUGH THE AUTOCLAVE DRAIN SYSTEM. APPROXIMATELY 30 | | SECONDS AFTER THE HCLS ACTUATION, THE CONDENSATE REMAINING IN THE AUTOCLAVE | | COLLECTED IN THE DRAIN LINE CAUSED THE 'A' CONDENSATE LEVEL PROBE TO SENSE | | A HIGH WATER LEVEL CONDITION." | | | | "THE SIGNAL FROM THE 'B' PROBE WAS DETERMINED TO BE AN INVALID BECAUSE THE | | AMOUNT OF WATER DRAINED FROM THE AUTOCLAVE FOLLOWING THE ACTUATION WAS NOT | | SUFFICIENT TO INDICATE THE PRESENCE OF DRAIN LINE BLOCKAGE. AN INSPECTION | | BY MAINTENANCE CONFIRMED THAT THE AUTOCLAVE DRAIN LINE WAS CLEAR OF ANY | | RESTRICTIONS WHICH COULD HAVE CAUSED WATER TO BACK UP INTO THE AUTOCLAVE. | | IN ADDITION, THE HIGH WATER LEVEL SIGNAL FROM THE 'A' PROBE OCCURRED AFTER | | THE SAFETY FUNCTION HAD BEEN COMPLETED AND WAS NOT THE RESULT OF A | | RESTRICTION IN THE DRAIN LINE." | | | | THE REGULATEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(CLAYTON) | | AND NMSS EO(COMBS). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32892 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/09/97 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 12:19 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/09/97 | +------------------------------------------------+EVENT TIME: 10:13[CDT]| |NRC NOTIFIED BY: JOE HESSLINE |LAST UPDATE DATE: 10/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |B. SPITZBERG, DO/IAT R4 | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM ON VITAL DOOR. IMMEDIATE | | COMPENSATORY MEASURES NOT TAKEN UPON DISCOVERY AND COMPENSATORY MEASURES | | NOW FULLY IMPLEMENTED. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | REFER TO HOO LOG FOR ADDITIONAL DETAILS. | | | | * * * UPDATE 1145EDT 10/7/97 FROM SCOTT HEAD TO S.SANDIN * * * | | THE LICENSEE AFTER FURTHER REVIEW AND DISCUSSION WITH REGION 4(DEXTER) IS | | RETRACTING THIS REPORT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | NOTIFIED R4IAT(MURRAY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32971 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 09/21/97 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 15:52 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/21/97 | +------------------------------------------------+EVENT TIME: 13:43[CDT]| |NRC NOTIFIED BY: CHAISSON |LAST UPDATE DATE: 10/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 +------------------------------------------------------------------------------+ | THE PLANT HAD A GROUP 5 ISOLATION OF THE REACTOR WATER CLEANUP SYSTEM. | | | | THIS OCCURRED DURING THE REMOVAL OF THE SYSTEM FROM SERVICE FOR MAINTENANCE | | AND TESTING. THE ISOLATION WAS DUE TO A DIFFERENTIAL FLOW ISOLATION | | SIGNAL. THE RETURN FLOW INDICATOR IS PEGGED DOWN SCALE WHICH MAY HAVE BEEN | | DUE TO A PERTURBATION IN THE SYSTEM. THE LICENSEE IS STILL INVESTIGATING | | THE CAUSE OF THE ISOLATION BUT SUSPECTS IT COULD BE A FLOW METER PROBLEM. | | THE LICENSEE ALSO VERIFIED THAT THERE IS NO SYSTEM LEAKAGE. THE ISOLATION | | SIGNAL HAS NOT YET BEEN RESET. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | | | * * * UPDATE AT 1045 ON 10/7/97, BY KOTTENSTETTE TAKEN BY WEAVER * * * | | THIS EVENT HAS BEEN RETRACTED. THE FLOW TRANSMITTER FAILED DOWNSCALE AND | | HAS BEEN REPLACED. THEREFORE, THE ISOLATION SIGNAL WAS INVALID AND THIS | | EVENT IS NOT REPORTABLE UNDER 10 CFR 50.72. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED. THE HOO NOTIFIED THE R3DO (CLAYTON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33037 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/07/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 04:14 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 03:10[CDT]| |NRC NOTIFIED BY: GEORGE TURNER |LAST UPDATE DATE: 10/07/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | |BLAINE MURRAY IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST KEYS | | | | COMPENSATORY MEASURES HAVE BEEN FULLY IMPLEMENTED. THE LICENSEE WILL | | NOTIFY THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33038 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/07/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 07:59 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/06/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:35[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/07/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 |FRED COMBS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: M.C. MAURER | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UF6 LEAK CONTAMINATES FOUR PEOPLE | | | | "ON 10/6/97 AT 1635 HOURS, A SMALL URANIUM HEXAFLUORIDE (UF6) LEAK OCCURRED | | ON THE PURGE AIR INSTRUMENT LINE ON AUTOCLAVE 3 SOUTH AT THE C-333-A FEED | | FACILITY. AS A RESULT OF THIS LEAK, PROCESS GAS LEAK DETECTOR (PGLD) HEAD | | YE-613-13 IN THE AUTOCLAVE HEATED HOUSING ALARMED. THIS PGLD HEAD IS A "Q" | | SAFETY SYSTEM ITEM. THE AUTOMATIC ACTUATION OF A 'Q' SAFETY SYSTEM | | RESULTING FROM A VALID CONDITION IS REPORTABLE IN ACCORDANCE WITH CRITERIA | | J2 OF PROCEDURE UE2-RA-RE1030, 'NUCLEAR EVENT REPORTING'. | | | | "THE 3 SOUTH AUTOCLAVE AND FIVE OTHER IN SERVICE AUTOCLAVES AT C-333-A WERE | | PLACED INTO CONTAINMENT IN ACCORDANCE WITH THE ALARM RESPONSE PROCEDURE. | | THE LEAKING PIPING WAS EVACUATED BELOW ATMOSPHERE AND THE PIPING LEAK WAS | | TEMPORARILY PLUGGED. THE SUBJECT PIPING WAS LEAK RATED TO ENSURE THAT THE | | PLUG WAS LEAK TIGHT. THE AUTOCLAVE WAS DECLARED INOPERABLE AT 2125 HOURS | | ON 10-6-97. THE 3 SOUTH AUTOCLAVE WILL REMAIN OUT OF SERVICE UNTIL THE | | LEAK IS REPAIRED. | | | | "HEALTH PHYSICS SURVEYS AND SAMPLING INDICATE THAT NO SIGNIFICANT | | CONTAMINATION RESULTED FROM THIS RELEASE. PRECAUTIONARY BIOASSAY SAMPLES | | WERE SUBMITTED BY PERSONNEL WORKING IN THE RELEASE AREA." | | | | SEVENTEEN PEOPLE SUBMITTED BIOASSAY SAMPLES. THIRTEEN SHOWED NO ACTIVITY. | | THE OTHER FOUR PEOPLE'S RESULTS WERE AS FOLLOWS: ONE AT 4 æg/ml, ONE AT | | 6æg/ml AND TWO PEOPLE WERE IN THE RANGE OF 10 - 15 æg/ml. | | | | THE CONTAMINATIONS ARE BELIEVED TO HAVE OCCURRED WHILE PERSONNEL WERE | | INVESTIGATING AN ALARMING LEAK DETECTOR. THE NRC RESIDENT INSPECTOR WAS | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33039 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/07/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 07:59 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/06/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:45[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/07/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 |FRED COMBS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: M.C. MAURER | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VALID ACTUATION OF AUTOCLAVE STEAM PRESSURE CONTROL SYSTEM DUE TO OPERATOR | | ACTIONS FOLLOWING SMALL UF6 RELEASE. | | | | "ON 10/6/97 AT 1654 HOURS, OPERATORS PLACED SIX IN-SERVICE AUTOCLAVES INTO | | CONTAINMENT IN RESPONSE TO A SMALL URANIUM HEXAFLUORIDE (UF6) RELEASE ON | | AUTOCLAVE POSITION 3 SOUTH (REFERENCE EVENT REPORT [PAD-97-0096]). AFTER | | MITIGATING THE RELEASE, AUTOCLAVE 2 NORTH, 2 SOUTH, 3 NORTH, 4 NORTH, AND 4 | | SOUTH WERE RETURNED TO SERVICE AFTER ENSURING VALVE CLARITY IN ACCORDANCE | | WITH TSR LCO 2.2.4.11. STEAM HEATING WAS REINITIATED ON AUTOCLAVE 4 NORTH | | AT 2038 HOURS. AT 2045 HOURS, THE STEAM PRESSURE CONTROL SYSTEM ON | | AUTOCLAVE 4 NORTH ACTUATED. STEAM HEATING WAS REINITIATED ON AUTOCLAVE 3 | | NORTH AT 2017 HOURS. AT 2110 HOURS, THE STEAM PRESSURE CONTROL SYSTEM ON | | AUTOCLAVE 3 NORTH ACTUATED. THE STEAM PRESSURE CONTROL SYSTEM IS A 'Q' | | SYSTEM REQUIRED BY THE TSR TO LIMIT THE MAXIMUM CYLINDER TEMPERATURE BY | | LIMITING THE SATURATED STEAM PRESSURE IN THE AUTOCLAVE. ACTUATION OF THE | | STEAM PRESSURE CONTROL SYSTEM RESULTS IN THE AUTOMATIC CLOSURE OF THE STEAM | | VALVES SERVING THE AUTOCLAVE. THE AUTOMATIC ACTUATION OF A 'Q' SAFETY | | SYSTEM RESULTING FROM A VALID CONDITION IS REPORTABLE IN ACCORDANCE WITH | | CRITERIA J2 OF PROCEDURE UE2-RA-RE1030, 'NUCLEAR EVENT REPORTING'." | | | | SYSTEMS ENGINEERING INVESTIGATED THE ACTUATIONS IN ACCORDANCE WITH | | PROCEDURE CP4-CO-AR8333A-13. THE AUTOCLAVE SYSTEMS WERE DETERMINED BY | | SYSTEMS ENGINEERING TO BE FUNCTIONING PROPERLY AND HAD ACTUATED DUE TO A | | VALID HIGH STEAM CONDITION (PRESSURE > 7 PSIG). THE HIGH STEAM CONDITION | | WAS BELIEVED TO BE A RESULT OF OPERATOR ACTIONS WHILE RETURNING THE | | AUTOCLAVES TO SERVICE." | | | | "AFTER ENSURING VALVE CLARITY IN ACCORDANCE WITH TSR LCO 2.2.4.11, CYLINDER | | HEATING WAS RESUMED ON POSITIONS 3 NORTH AND 4 NORTH." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33038 FOR UF6 RELEASE REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33040 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/07/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 13:13[CDT]| |NRC NOTIFIED BY: JEFF HEATON |LAST UPDATE DATE: 10/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 80 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DESIGN BASIS OFFSITE RADIATION DOSES MAY BE EXCEEDED. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON OCTOBER 7, 1997, COMED DETERMINED THAT BYRON UNIT 1 IS OUTSIDE OF | | DESIGN BASES IN THAT ALLOWABLE OFFSITE DOSES MAY BE EXCEEDED. THE PROJECTED | | PRIMARY-TO-SECONDARY ACCIDENT LEAKAGE IN THE EVENT OF A MAIN STEAMLINE | | BREAK COULD RESULT IN EXCEEDING THE MAXIMUM SITE ALLOWABLE | | PRIMARY-TO-SECONDARY LEAKAGE LIMIT. IN CONJUNCTION WITH REACTOR COOLANT | | SYSTEM SPECIFIC ACTIVITY AT THE MAXIMUM ALLOWED BY TECHNICAL SPECIFICATIONS | | (0.35 MICROCURIES PER GRAM), THIS COULD ALSO RESULT IN EXCEEDING ALLOWABLE | | OFFSITE DOSES. | | | | ON OCTOBER 7, 1997, BYRON EXCEEDED 448.5 DAYS OPERATING ABOVE 500øF. AT | | THAT TIME, CONTRIBUTION TO PRIMARY-TO-SECONDARY STEAM GENERATOR LEAKAGE DUE | | TO CIRCUMFERENTIAL CRACKING EVALUATED ALONG WITH OTHER CONTRIBUTORS (i.e. | | IPC, F*) DID NOT ENSURE THE MAXIMUM SITE ALLOWABLE PRIMARY-TO-SECONDARY | | LEAKAGE LIMIT WAS STILL MET. WITH CONSIDERATION OF THE CURRENT DOSE | | EQUIVALENT IODINE-131 LIMIT OF 0.35 MICROCURIES PER GRAM, THE PREDICTED | | PRIMARY-TO-SECONDARY LEAKAGE IN THE EVENT OF AN ACCIDENT COULD NOT ENSURE | | THAT THE OFFSITE DOSE WOULD BE A SMALL PERCENTAGE OF 10CFR100 LIMITS. | | | | BYRON UNIT 1 OPERATION WILL PROCEED ON THE BASIS OF AN OPERABILITY | | ASSESSMENT (97-62) OF CURRENT PLANT CONDITIONS (NO INDICATED LEAKAGE FROM | | CIRCUMFERENTIAL CRACKS, CONSERVATIVE TECHNICAL SPECIFICATION REQUIRED PLANT | | SHUTDOWN AT 150 GPD PRIMARY-TO-SECONDARY LEAKAGE). IN ADDITION, COMED WILL | | ENSURE THAT REACTOR COOLANT SYSTEM DOSE EQUIVALENT IODINE-131 IS MAINTAINED | | AT OR BELOW 0.20 MICROCURIES PER GRAM AS REQUESTED IN A JANUARY 31, 1997 | | LICENSE AMENDMENT REQUEST SUBMITTAL. (NOTE: THE CURRENT UNIT 1 REACTOR | | COOLANT SYSTEM DOSE EQUIVALENT IODINE-131 CONCENTRATION IS APPROXIMATELY | | 1E-4 MICROCURIES PER GRAM.) WITH CONSIDERATION OF THE REDUCED DOSE | | EQUIVALENT IODINE-131 LIMIT OF 0.20 MICROCURIES PER GRAM, THE PREDICTED | | PRIMARY-TO-SECONDARY LEAKAGE IN THE EVENT OF AN ACCIDENT DOES NOT EXCEED | | THE REVISED MAXIMUM ALLOWABLE SITE LEAKAGE AND THE OFFSITE DOSE WOULD STILL | | REMAIN A SMALL PERCENTAGE OF THE 10CFR100 LIMITS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33041 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/07/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 17:05[CDT]| |NRC NOTIFIED BY: DAN KLOPSTEIN |LAST UPDATE DATE: 10/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |CREED IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS FOR DUTY QUESTIONED DUE TO SLEEPING ON WATCH. IMMEDIATE | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE NRC RESIDENT INSPECTOR WILL | | BE INFORMED. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33042 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/07/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:12[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/07/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 |FREDERICK COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CAGE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 1 HOUR REPORT | | | | DURING A DAILY WALKDOWN OF CLASSIFIED INFORMATION REPOSITORIES, FOUR | | REPOSITORIES WERE FOUND UNLOCKED. THE LICENSEE IS CURRENTLY CONTACTING THE | | CUSTODIANS OF THESE REPOSITORIES TO DETERMINE WHETHER ANY INFORMATION IS | | MISSING. THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33043 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/08/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 01:51 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 01:15[EDT]| |NRC NOTIFIED BY: FIELDS |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 72 HOUR LCO ACTION STATEMENT AFTER DECLARING BOTH THE | | "2HVS-1A" AND "2HVS-1D" CONTAINMENT FAN COOLERS OUT OF SERVICE. | | | | WHILE TROUBLESHOOTING THE CAUSE OF THE LOW FLOW ANNUNCIATOR ALARM ON BOTH | | CONTAINMENT FAN COOLERS, IT WAS DETERMINED THE "2HVS-1D" CONTAINMENT FAN | | COOLER WAS WIRED INCORRECTLY FOR RUNNING AT SLOW SPEED. THE LICENSEE | | DISCOVERED THAT THE SLOW SPEED LEADS WERE REVERSED CASUING THE FAN TO | | OPERATE IN THE OPPOSITE DIRECTION. THE FAN IS REQUIRED TO RUN AT SLOW | | SPEED DURING A DESIGN BASIS ACCIDENT. THE FAN COOLER WAS DECLARED OUT OF | | SERVICE FOR BEING INCORRECTLY WIRED AND THEY ENTERED A 72HR. LCO ACTION | | STATEMENT TO RETURN ONE COOLER TRAIN BACK TO SERVICE OR BE IN MODE 3 WITHIN | | THE NEXT 6 HRS AND MODE 4 IN THE FOLLOWING 6 HRS. THE SECOND FAN COOLER | | "2HVS-1A" DOES NOT APPEAR TO BE WIRED INCORRECTLY, BUT IT ALSO WAS DECLARED | | OUT OF SERVICE DUE TO AN APPARENT LOW FLOW SWITCH PROBLEM. THE RESIDENT | | INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+