U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/06/97 - 06/09/97 ** EVENT NUMBERS ** 32319 32438 32439 32440 32441 32442 32443 32444 32445 32446 32447 32448 32449 32450 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32319 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/12/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:15 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/12/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 04:28[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/07/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JIM MCCORMICKBARGER RDO | | DOCKET: 0707002 | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN JORDAN | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY EQUIPMENT ACTUATION - (24-HOUR REPORT PER PROCEDURE UE2-RA1030, | | APPENDIX D, CRITERIA J, SAFETY EQUIPMENT FAILURE/ACTUATION) | | | | AT 0428, A URANIUM HEXAFLUORIDE (UF6) SMOKE DETECTOR ACTUATED IN THE CELL | | #33-7-2 LOCAL CONTROL CENTER CABINET IN THE X-333 PROCESS BUILDING. A | | SMALL WISP OF UF6 SMOKE WAS OBSERVED COMING FROM A SAMPLE U-TUBE BYPASS | | VALVE DURING PREPARATION FOR PULLING AN 'A' FEED SAMPLE. THE UF6 SMOKE | | DETECTOR IS A 'Q' SAFETY SYSTEM. A PORTABLE NEGATIVE AIR MACHINE (UF6/HF | | GULPER) WAS IN USE DURING THIS EVENT. THE OPERATOR WAS WEARING PROCEDURE | | SPECIFIED PERSONAL PROTECTIVE EQUIPMENT INCLUDING A FULL FACE RESPIRATOR | | AND GLOVES. THE RELEASE (WISP) STOPPED ON ITS OWN, AND THE SMOKE DETECTOR | | AUTOMATICALLY RESET. A HEALTH PHYSICS SURVEY OF THE LOCAL CONTROL CENTER | | DETECTED NO REMOVABLE ALPHA OR BETA/GAMMA CONTAMINATION. THE SAMPLE U-TUBE | | WAS REJECTED AND TAGGED FOR EVALUATION. | | | | PORTSMOUTH NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT OF ENERGY | | SITE REPRESENTATIVE. | | | | * * * UPDATE @ 1344 ON 06/07/97 FROM JORDAN TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE FOLLOWING IS THE TEXT OF A | | FACSIMILE RECEIVED BY THE OPERATION CENTER: | | | | "THE SUBJECT REPORT HAS BEEN DOWNGRADED BY THE SITE NUCLEAR REGULATORY | | AFFAIRS EVENT REPORTING & INVESTIGATION STAFF. | | | | "THE RATIONAL FOR THE DOWNGRADE IS BASED IN PART ON THE FOLLOWING DATA; | | THE UF6 SMOKE DETECTORS INSIDE THE LOCAL CONTROL CENTER (LCC) ARE NOT | | DESIGNATED AS 'Q' SYSTEMS. SAR ACCIDENT ANALYSIS SECTION 4.1.1.3 REFERS TO | | SHUTTING DOWN A CELL IN RESPONSE TO UF6 DETECTOR ACTUATIONS. IT CONTINUES, | | 'THIS ALSO POINTS OUT THAT THE UF6 DETECTORS INSTALLED IN THE LCCs SHOULD | | NOT BE TREATED AS ALARMS FOR INITIATING THE CELL SHUTDOWN SAFETY FUNCTION | | SINCE THEY CANNOT RESULT IN A LARGE RELEASE AND ARE MORE SUSCEPTIBLE TO | | ACTUATION FROM THE TEMPERATURE AND DUST ASSOCIATED WITH MERELY OPENING THE | | SAMPLE CABINET. THEY SHOULD BE RETAINED AS OPERATIONAL ALARMS AND | | RESPONDED TO AS WITH ANY UF6 RELEASE UNDER THE RADIATION PROTECTION AND | | EMERGENCY RESPONSE PROGRAMS. | | | | "THE UF6 DETECTOR HEADS LOCATED INSIDE THE LCC ARE EXCLUDED FROM THE 'Q' | | SYSTEM BOUNDARY DEFINITION. DISCUSSIONS WITH ENGINEERING, NUCLEAR SAFETY, | | AND CONFIGURATION MANAGEMENT CONFIRMED THAT THIS DETECTOR IS NOT A 'Q' | | SYSTEM. SINCE ACTUATION OF A NON-Q ALARM IS NOT REPORTABLE, THIS EVENT IS | | BEING DOWNGRADED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED R3DO BRENT CLAYTON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32438 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 06/06/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 06:02 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 06/06/97 | +------------------------------------------------+EVENT TIME: 01:22[CDT]| |NRC NOTIFIED BY: GRANT |LAST UPDATE DATE: 06/06/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DURING A | | SURVEILLANCE TEST. | | | | DURING THE PERFORMANCE OF A QUARTERLY HPCI SYSTEM OPERABILITY SURVEILLANCE | | TEST, THE GLAND SEAL LEAKOFF PUMP BEGAN CYCLING ON AND OFF EXCESSIVELY. THE | | LICENSE STOPPED THE TEST, DECLARED THE HPCI SYSTEM INOPERABLE, AND BEGAN AN | | INVESTIGATION INTO THE CAUSE. TECHNICAL SPECIFICATION 3.5.a.(3) REQUIRES | | THE LICENSEE TO RESTORE THE HPCI SYSTEM TO OPERABLE STATUS WITHIN 14 DAYS | | OR SHUT UNIT 2 DOWN. ALL OTHER EMERGENCY CORE COOLING SYSTEMS ARE FULLY | | OPERABLE, IF NEEDED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32439 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/06/97 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 08:30 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 06/06/97 | +------------------------------------------------+EVENT TIME: 03:47[CDT]| |NRC NOTIFIED BY: W. CUSACK |LAST UPDATE DATE: 06/06/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | #2 EMERGENCY DIESEL GENERATOR (EDG) STARTED UNEXPECTEDLY BUT DID NOT LOAD. | | | | WHILE CONDUCTING AN UNDERVOLTAGE AUTOMATIC START TEST OF THE #2 EDG, THE | | EDG STARTED UNEXPECTEDLY, BUT DID NOT LOAD. THE PURPOSE OF THE TEST WAS | | TO CHECK THE PROPER RESPONSE OF THE AIR START SOLENOIDS TO A SIMULATED | | UNDERVOLTAGE CONDITION ON THE #2A4 SAFETY BUS. THE AIR START SYSTEM HAD | | BEEN MANUALLY ISOLATED FROM THE EDG DURING THE TEST TO PREVENT THE EDG FROM | | ACTUALLY STARTING. THE AIR START SOLENOIDS OPENED, AS EXPECTED, DURING THE | | TEST AND RESIDUAL PRESSURE IN THE AIR START HEADER WAS SUFFICIENT TO ROLL | | THE EDG AND START IT. THE EDG WAS "WARM" FROM PREVIOUS TESTS. THE | | LICENSEE PROPERLY SECURED THE EDG AND CONSIDERS IT FULLY OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32440 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST. ELIZABETH HOSPITAL |NOTIFICATION DATE: 06/06/97 | | CITY: ELIZABETH REGION: 1 |NOTIFICATION TIME: 09:00 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 06/04/97 | |LICENSE#: 29-04333-01 AGREEMENT: N |EVENT TIME: 13:00[EDT]| | DOCKET: 03002476 |LAST UPDATE DATE: 06/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID SILK RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM DWYER (NRC REG 1) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ST. ELIZABETH HOSPITAL NOTIFIED NRC REGION 1 OF AN IODINE-131 CAPSULE FOUND | | IN A BAG OF MEDICAL WASTE THAT HAD BEEN RETURNED TO THE HOSPITAL. | | | | ON 04/23/97, A TRUCK CONTAINING MEDICAL WASTE HAD SET OFF A RADIATION ALARM | | AT A WASTE FACILITY. ON 06/04/97, AN I-131 CAPSULE WAS FOUND IN A MEDICAL | | WASTE BAG BY THE LICENSEE AFTER THE BAG HAD BEEN RETURNED TO THE HOSPITAL. | | THE CAPSULE WAS FOUND WRAPPED IN WAX PAPER INSIDE A CANDY WRAPPER INSIDE | | THE BAG. ON 06/05/97, THE LICENSEE ASSAYED THE CAPSULE AND DETERMINED IT | | CONTAINED 338 MICROCURIES OF I-131. ON 04/23/97, THE DATE THE CAPSULE SET | | OFF THE RADIATION MONITOR AT THE WASTE FACILITY, THE CAPSULE WOULD HAVE | | CONTAINED APPROXIMATELY 14 MILLICURIES OF I-131. BASED ON A PRELIMINARY | | REVIEW OF THE HOSPITAL RECORDS, ONLY TWO I-131 ADMINISTRATIONS HAD BEEN | | PERFORMED IN 1997, BOTH IN MARCH, AND EACH ONE WAS LESS THAN 4 MILLICURIES. | | BASED ON CALCULATIONS BY THE LICENSEE, THE I-131 CAPSULE FOUND IN THE | | MEDICAL WASTE COULD NOT HAVE BEEN EITHER OF THE CAPSULES THAT WERE | | ADMINISTERED BY THE HOSPITAL. | | | | THE LICENSEE NOTIFIED THE STATE OF NEW JERSEY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32441 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/06/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 12:20 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/05/97 | +------------------------------------------------+EVENT TIME: 13:20[EDT]| |NRC NOTIFIED BY: TONKINSON |LAST UPDATE DATE: 06/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 23 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24-HOUR REPORT DUE TO EXCEEDING LICENSED THERMAL POWER LIMIT | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "AT 1320 HOURS ON 06/05/97, A MOMENTARY CONTROL SIGNAL ANOMALY IN THE | | ELECTRO-HYDRAULIC CONTROL SYSTEM CAUSED SEVERAL UNIT 2 MAIN TURBINE BYPASS | | VALVES TO CYCLE OPEN AND THEN CLOSE. THE RESULTANT REACTOR PRESSURE SPIKE, | | THAT LASTED SEVERAL SECONDS, CAUSED A MOMENTARY POWER INCREASE THAT REACHED | | APPROXIMATELY 102.4% THERMAL POWER. ENGINEERING ANALYSIS CONCLUDED THAT | | THERE WAS NO ADVERSE IMPACT ON THE REACTOR VESSEL AND INTERNALS, REACTOR | | CORE, OR ANY OTHER SYSTEM OR COMPONENT IMPORTANT TO SAFETY AS A RESULT OF | | THIS EVENT. | | | | "APPROPRIATE TRANSIENT RESPONSE PROCEDURES WERE ENTERED FOR HIGH REACTOR | | PRESSURE AND UNANTICIPATED REACTIVITY ADDITION. POWER WAS REDUCED TO AND | | HAS REMAINED AT A NOMINAL 23% TO FACILITATE TROUBLESHOOTING. | | | | "THIS NOTIFICATION IS BEING MADE IN ACCORDANCE WITH LIMERICK UNIT 2 | | OPERATING LICENSE NPF-85 CONDITION 2.E FOR EXCEEDING THE MAXIMUM POWER | | LEVEL SPECIFIED BY OPERATING LICENSE CONDITION 2.C.1. WRITTEN FOLLOWUP | | WILL BE SUBMITTED WITHIN 30 DAYS AS SPECIFIED BY OPERATING LICENSE | | CONDITION 2.E." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32442 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/06/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:16 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/06/97 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: WALPOLE |LAST UPDATE DATE: 06/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - | | | | GE MODEL #IFCS RELAYS PROCURED FROM GENERAL ELECTRIC NUCLEAR ENERGY UNDER A | | SAFETY RELATED PURCHASE ORDER WERE DELIVERED WITH LOOSE HARDWARE AND WERE | | UNSUITABLE FOR USE AT MILLSTONE UNIT 1. SUBSEQUENT SURVEILLANCE BY YANKEE | | ATOMIC ELECTRIC COMPANY REVEALED DEFICIENCIES IN THE GENERAL ELECTRIC | | COMMERCIAL DEDICATION PROCESS. THE MANUFACTURING DEFECTS WHICH WERE | | IDENTIFIED BY NORTHEAST UTILITIES WOULD HAVE IMPACTED OPERATION OF THE | | RELAY. THE LICENSEE HAS DETERMINED THIS CONDITION TO BE A SUBSTANTIAL | | SAFETY HAZARD. | | | | REFER TO THE HOO LOG FOR LICENSEE CONTACT NAME AND TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32443 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/06/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:55 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/06/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON RDO | | DOCKET: 0707002 | | +------------------------------------------------+KEVIN RAMSEY NMSS | |NRC NOTIFIED BY: LOMBARD | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - | | | | THE CERTIFICATE HOLDER REPORTED A PROBLEM WITH THE LIFTING LUGS ON THE | | MODEL #48G UF6 CYLINDERS. WHILE INSPECTING A LOT OF NEW CYLINDERS, | | IMPROPER WELD OVERLAP WAS OBSERVED ON SOME OF THE LIFTING LUG WELDS. THIS | | CONDITION COULD CAUSE THE WELDS TO FAIL UNDER A LOWER LOAD THAN EXPECTED. | | THE CYLINDERS WERE SUPPLIED BY WESTERMAN INC, 245 NORTH BROAD STREET, | | BREMEN, OHIO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32444 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 06/06/97 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 19:07 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/06/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: MALONEY |LAST UPDATE DATE: 06/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADEQUATE HELB ANALYSIS FOR STEAM GENERATOR BLOWDOWN PIPING. | | | | THE LICENSEE HAS DETERMINED THAT THE HIGH ENERGY LINE BREAK (HELB) ANALYSIS | | FOR THE STEAM GENERATOR (S/G) BLOWDOWN PIPING DID NOT ACCOUNT FOR THE | | EFFECTS OF PIPE WHIP OR FLUID JET IMPINGEMENT ON NEARBY SAFETY RELATED | | CABLES. THIS CONDITION COULD AFFECT CONTROL AND POWER CABLES FOR THE | | #P25A EMERGENCY FEEDWATER (EFW) PUMP AND EFW PUMP ROOM VENTILATION FANS | | #35A AND #35B, POTENTIALLY DISABLING BOTH EFW PUMPS. ADDITIONALLY, S/G | | LEVEL AND HIGH PRESSURE SAFETY INJECTION FLOW INDICATION COULD BE AFFECTED. | | THE LICENSEE WILL CONTINUE THEIR ONGOING ENGINEERING REVIEW OF THIS ISSUE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32445 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ALEXIAN BROTHERS HOSPITAL |NOTIFICATION DATE: 06/06/97 | | CITY: ST. LOUIS REGION: 3 |NOTIFICATION TIME: 20:55 [ET]| | COUNTY: STATE: MO |EVENT DATE: 06/06/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[CDT]| | DOCKET: 03002303 |LAST UPDATE DATE: 06/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRENT CLAYTON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: H. ROBICHAUX | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION AT ALEXIAN BROTHERS HOSPITAL LOCATED IN ST LOUIS. | | | | A TECHNICIAN WAS ADMINISTERING TWO UNIT DOSES OF Tc-99m FOR BONE SCANS, | | AND PREPARED A KIT WITH Tc-99m TO PERFORM A RENAL FUNCTION SCAN. AFTER | | ADMINISTERING THE BONE SCAN DOSES, THE TECHNICIAN NOTICED THAT ONE OF | | THE PATIENTS WAS PASSING THE Tc-99m THROUGH THE KIDNEYS AND INTO THE | | BLADDER. | | AFTER ADMINISTERING THE OTHER DOSE, THE TECHNICIAN NOTICED THAT THE THIRD | | PATIENT WAS SHOWING A BONE UPTAKE. THE PHYSICIANS FOR BOTH PATIENTS WERE | | CONTACTED, AND NO HEALTH EFFECTS WERE EXPECTED TO OCCUR AS A RESULT OF THIS | | MISADMINISTRATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32446 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/07/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/07/97 | +------------------------------------------------+EVENT TIME: 18:52[EDT]| |NRC NOTIFIED BY: GREEN |LAST UPDATE DATE: 06/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 1 STARTUP | 1 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 OUTSIDE DESIGN BASIS | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE RECEIVED BY THE OPERATIONS CENTER: | | | | "DURING A REVIEW BY NMP2 OPERATIONS OF THE REMOTE SHUTDOWN SYSTEM | | OPERATION/CONTROL ROOM EVACUATION PROCEDURE, IT WAS DETERMINED THAT | | #2RCS*MOV18A AND MOV18B, THE REACTOR RECIRCULATION SYSTEM PUMP DISCHARGE | | BLOCKING VALVES, ARE POWERED FROM NONEMERGENCY (BLACK) POWER SUPPLIES | | WHICH ARE NOT ENERGIZED AFTER A COMPLETE LOSS OF OFFSITE POWER (LOOP). | | THESE VALVES ARE INSIDE THE DRYWELL, WHICH BECAUSE THE ATMOSPHERE IS | | INERTED WITH NITROGEN GAS DURING REACTOR OPERATION, WOULD BE INACCESSIBLE | | TO OPERATE LOCALLY BY HAND AFTER A CONTROL ROOM EVACUATION. | | | | "ONE OF THESE VALVES MUST BE SHUT TO PLACE A SHUTDOWN COOLING LOOP OF | | RESIDUAL HEAT REMOVAL SYSTEM IN OPERATION OR THE CORE WILL BE BYPASSED AND | | MINIMAL COOLING WILL BE ACHIEVED. BOTH LOOPS OF REMOTE SHUTDOWN SYSTEM | | SHUTDOWN COOLING CONTROLS HAVE BEEN DECLARED INOPERABLE, ENTERING A 7 DAY | | SHUTDOWN LCO PER TECHNICAL SPECIFICATION 3.3.7.4." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32447 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/08/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 05:16 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/08/97 | +------------------------------------------------+EVENT TIME: 02:36[EDT]| |NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 06/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ALL 3 PRESSURIZER SAFETY VALVES FAILED THEIR INITIAL SET PRESSURE TEST - | | | | DURING TECH SPEC SURVEILLANCE SHOP TEST AT WYLE LABS, ALL THREE PRESSURIZER | | SAFETY VALVES (#PCV-464, 466, & 468) FAILED THEIR INITIAL SET PRESSURE | | TEST. THE REQUIRED LIFT POINT IS 2485 PSIG +/- 1%. THE INITIAL LIFT | | POINTS WERE PCV-464 @ 2560 PSIG, PCV-466 @ 2581 PSIG, AND PCV-468 @ 2533 | | PSIG. | | | | THE VALVES WERE REFURBISHED AND RETESTED SATISFACTORILY AT WYLE LABS. | | | | THE LICENSEE IS DETERMINING THE ROOT CAUSE OF THE EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32448 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 06/08/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 08:59 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 06/08/97 | +------------------------------------------------+EVENT TIME: 05:30[EDT]| |NRC NOTIFIED BY: GREGG LESSIG |LAST UPDATE DATE: 06/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 27 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO REACTOR TRIP DURING ADJUSTMENT OF POWER RANGE NUCLEAR INSTRUMENTS - | | | | WHILE LICENSEE TECHNICIANS WERE ADJUSTING POWER RANGE NUCLEAR INSTRUMENTS, | | AN AUTO REACTOR TRIP FROM 27% POWER OCCURRED DUE TO THE PRESENCE OF 2 OF 4 | | POWER RANGE RATE TRIP LOGIC SIGNALS. ALL CONTROL RODS INSERTED COMPLETELY. | | STEAM IS BEING DUMPED TO THE ATMOSPHERE VIA THE STEAM GENERATORS POWER | | OPERATED RELIEF VALVES. | | | | FOLLOWING THE TRIP, TWO 6.9 KV NON-SAFETY BUSES FAILED TO AUTO TRANSFER TO | | THE STARTUP TRANSFORMERS, AS EXPECTED. THIS LOSS OF AC POWER TO NON-SAFETY | | BUS #1A TRIPPED THE SOLE RUNNING MAIN FEEDWATER PUMP WHICH CAUSED AN ESF | | ACTUATION OF THE TWO MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS. | | | | THE PLANT IS STABLE IN MODE 3 (HOT STANDBY). THE LICENSEE IS INVESTIGATING | | THE CAUSE OF THE TRIP AND THE LOSS OF POWER TO NON-SAFETY BUS #1A. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32449 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/08/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 18:05 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/08/97 | +------------------------------------------------+EVENT TIME: 14:41[EDT]| |NRC NOTIFIED BY: WOODBURY |LAST UPDATE DATE: 06/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 +------------------------------------------------------------------------------+ | EDG AUTO STARTED DURING A SURVEILLANCE TEST. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "UNIT 1 WAS OPERATING AT 100% POWER. WHILE PREPARING FOR A SCHEDULED | | MAINTENANCE OUTAGE ON EMERGENCY DIESEL GENERATOR #4, EDGs #1, 2, AND 3 | | WERE BEING RUN TO SATISFY TECHNICAL SPECIFICATION SURVEILLANCE | | REQUIREMENTS. AT 1441 ON 06/08/97, THE CONTROL ROOM OPERATOR PLACED | | EDG #2 IN 'LOCAL MANUAL' IN ACCORDANCE WITH THE APPROPRIATE PROCEDURE. | | COINCIDENT WITH DEPRESSING THE PUSHBUTTON, 4160 VAC EMERGENCY BUS #E-2 | | NORMAL POWER SUPPLY BREAKERS OPENED. THIS RESULTED IN AN UNDERVOLTAGE | | CONDITION ON BUS #E-2 WHICH INITIATED AN AUTOMATIC START OF EDG #2 AND | | TRANSFERRED THE CONTROL CIRCUIT BACK TO AUTO. EDG #2 STARTED, AND WHEN | | UP TO SPEED AND VOLTAGE, PICKED UP BUS #E-2 LOADS. | | | | "THE MOMENTARY LOSS OF POWER TO BUS #E-2 RESULTED IN THE FOLLOWING ESF | | ACTUATIONS: HALF SCRAM DIV II ACTUATED, BOTH STANDBY GAS TREATMENT TRAINS | | STARTED, SECONDARY CONTAINMENT ISOLATED, GROUP 6 (CONTAINMENT ATMOSPHERE | | CONTROL SYSTEM) DIV II AND ALL APPLICABLE CONTAINMENT MONITORS ISOLATED, | | GROUP 3 (RWCU SYSTEM SUCTION) ISOLATED, GROUP 2 (DRYWELL FLOOR AND | | EQUIPMENT DRAINS) DIV II ISOLATED, HALF GROUP 1 (MAIN STEAM) DIV II | | ISOLATED, REACTOR SAMPLE VALVE #1-B32-F020 CLOSED, AND GROUP 10 (DRYWELL | | PNEUMATICS) DIV II ISOLATED. ALL SYSTEMS FUNCTIONED AS REQUIRED." | | | | THE #E-2 BUS CONTINUES TO BE SUPPLIED BY THE #2 EDG WHILE TROUBLESHOOTING | | CONTINUES. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #32450 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32450 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/08/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 22:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/08/97 | +------------------------------------------------+EVENT TIME: 19:13[EDT]| |NRC NOTIFIED BY: HARDIN |LAST UPDATE DATE: 06/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 +------------------------------------------------------------------------------+ | VARIOUS ESF ACTUATIONS OCCURRED WHEN EDG TRIPPED DUE TO FUEL OIL LEAK. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "UNIT 1 WAS OPERATING AT 100% POWER. DUE TO A LOGIC PROBLEM ENCOUNTERED ON | | THE PREVIOUS SHIFT ASSOCIATED WITH THE NORMAL FEEDER BREAKERS TO 4160 VAC | | BUS #E-2 (NOTE: SEE EVENT #32449), EDG #2 WAS RUNNING AND SUPPLYING | | 4160 VAC BUS #E-2. A FUEL OIL LEAK DEVELOPED ON EDG #2 WHICH REQUIRED | | THE EDG TO BE TRIPPED. | | | | "WHEN THE EDG WAS TRIPPED AT 1913, BUS #E-2 WAS DEENERGIZED CAUSING THE | | FOLLOWING ESF ACTUATIONS: RPS DIV II ACTUATED, BOTH STANDBY GAS TREATMENT | | TRAINS STARTED, SECONDARY CONTAINMENT ISOLATED, GROUP 2 (DRYWELL FLOOR AND | | EQUIPMENT DRAINS) DIV II ISOLATED, GROUP 3 (RWCU SYSTEM SUCTION) ISOLATED, | | GROUP 6 (CONTAINMENT ATMOSPHERE CONTROL SYSTEM) DIV II AND ALL APPLICABLE | | CONTAINMENT MONITORS ISOLATED, HALF GROUP 1 (MAIN STEAM) DIV II ISOLATED, | | REACTOR SAMPLE VALVE #1-B32-F020 CLOSED, AND GROUP 10 (DRYWELL PNEUMATICS) | | DIV II ISOLATED. ALL SYSTEMS FUNCTIONED AS REQUIRED." | | | | THE LICENSEE WAS ABLE TO REENERGIZE BUS #E-2 FROM ITS OFFSITE POWER SUPPLY. | | REPAIRS TO THE EDG FUEL SYSTEM AND LOGIC CONTINUE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+