U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/16/97 - 09/17/97 ** EVENT NUMBERS ** 32932 32933 32934 32935 32936 32937 32938 32939 32940 32941 32942 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32932 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/16/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 01:20 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/15/97 | +------------------------------------------------+EVENT TIME: 23:11[EDT]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STATION SERVICE WATER (SSW) PUMP AUTOMATICALLY STARTED DURING TESTING | | | | THE FOLLOWING IS TEXT FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THE 'D' SSW PUMP AUTO STARTED FROM A SUSPECTED LOW FLOW SIGNAL WHILE | | RESTORING THE PUMPS CONTROL LOGIC FROM THE 'EMERGENCY TAKEOVER' MODE OF | | OPERATION TO THE 'NORMAL' MODE. THE REMOTE SHUTDOWN SYSTEM SURVEILLANCE | | TEST WAS IN PROGRESS. THIS WAS AN UNEXPECTED RESPONSE. SERVICE WATER PUMP | | LOW FLOW AUTO START IS AN ESF SIGNAL LISTED IN THE HOPE CREEK UFSAR TABLE | | 7.3.15. THE PUMP WAS SHUT DOWN BY OPERATORS IN THE CONTROL ROOM. | | TROUBLESHOOTING IS IN PROGRESS TO DETERMINE THE CAUSE." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32933 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/16/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 10:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/15/97 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: STEWART |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VIOLATION OF LICENSE CONDITION REGARDING FIRE PROTECTION | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON SEPTEMBER 15, 1997, SITE FIRE PROTECTION IDENTIFIED THAT ANNUAL | | INSPECTIONS OF PORTABLE FIRE EXTINGUISHERS HAVE NOT BEEN PERFORMED AS | | REQUIRED BY NFPA 10 AND OSHA 29CFR1910.157(E)(3). THIS CONSTITUTES A | | FAILURE TO MAINTAIN A PROVISION OF THE FIRE PROTECTION PROGRAM AS DESCRIBED | | IN THE UPDATED FINAL SAFETY ANALYSIS REPORT, AND, AS SUCH, IS A | | NON-COMPLIANCE WITH LICENSE CONDITION 2.C(3). THIS NON-COMPLIANCE IS | | REPORTABLE UNDER LICENSE CONDITION 2.F (UNIT 1) AND 2.E (UNIT 2). THE | | CONSEQUENCE OF THIS NON-COMPLIANCE IS MINIMAL IN THAT THE FIRE | | EXTINGUISHERS ARE NOT RELIED UPON TO SUPPORT SAFE SHUTDOWN OF THE PLANT IN | | THE EVENT OF A FIRE. | | | | WHILE LOADING DATA FOR SOFTWARE FOR ADMINISTRATIVE CONTROL OF PORTABLE FIRE | | EXTINGUISHER INSPECTIONS, SITE FIRE PROTECTION PERSONNEL IDENTIFIED THAT | | THE CORPORATE FIRE SHOP HAD NOT BEEN PERFORMING THE CODE REQUIRED ANNUAL | | INSPECTIONS AS HAD BEEN PREVIOUSLY ASSUMED BY THE SITE. AN INVESTIGATION IS | | UNDERWAY TO IDENTIFY THE EXACT CAUSE AND DURATION OF THE NON-COMPLIANCE. | | THE INSPECTION WILL COMMENCE ON SEPTEMBER 16, 1997, AND IS EXPECTED TO BE | | COMPLETE WITHIN FIVE WORKING DAYS." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32934 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/16/97 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 13:08 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 12:25[EDT]| |NRC NOTIFIED BY: CRAIG MOWREY |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF THE ARRIVAL OF A CONTAMINATED TOOL ONSITE | | | | WHILE SURVEYING A VENDOR'S TOOLS ARRIVING ONSITE FOR THE CURRENT UNIT 4 | | REFUELING OUTAGE, HEALTH PHYSICS PERSONNEL DISCOVERED LOW LEVELS OF | | RADIOACTIVITY ON A PNEUMATIC HOSE APPROXIMATELY EIGHT FEET IN LENGTH. THE | | OWNER OF THE TOOLS IS NOT LICENSED TO RECEIVE BYPRODUCT MATERIAL. THE | | ACTIVITY LEVEL IS APPROXIMATELY 19,000 DISINTEGRATIONS PER MINUTE (FOR THE | | ENTIRE HOSE) WHEN COUNTED IN A SMALL ARTICLES MONITOR, AND THE ALARM | | SETPOINT OF THE SMALL ARTICLES MONITOR IS 4,000 DISINTEGRATIONS PER MINUTE. | | ISOTOPIC ANALYSIS OF THE HOSE USING A MULTI-CHANNEL ANALYZER INDICATES THE | | PRESENCE OF COBALT-60, MANGANESE-54, ZINC-65, AND NATURALLY OCCURRING | | ISOTOPES. THERE WAS NO LOOSE SURFACE CONTAMINATION FOUND, AND THE | | CONTAMINATION WAS NOT DETECTABLE WITH A FRISKER. THE HOSE IS CURRENTLY | | BEING HELD INSIDE THE TURKEY POINT RADIATION CONTROL AREA. | | | | THE LICENSEE BELIEVES THAT THE HOSE MAY HAVE COME FROM ANOTHER UTILITY, AND | | THE VENDOR (TRI TOOLS, INC.) HAS BEEN NOTIFIED. THE VENDOR DOES NOT HAVE A | | MEANS OF TRACING THE HOSE BUT PLANS TO ATTEMPT TO TRACE THE ASSEMBLY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE STATE OF FLORIDA, | | DEPARTMENT OF HEALTH, AND BUREAU OF RADIATION CONTROL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32935 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF MICHIGAN |NOTIFICATION DATE: 09/16/97 | | CITY: ANN ARBOR REGION: 3 |NOTIFICATION TIME: 13:40 [ET]| | COUNTY: WASHTENAW STATE: MI |EVENT DATE: 09/15/97 | |LICENSE#: 21-00215-04 AGREEMENT: N |EVENT TIME: 14:40[EDT]| | DOCKET: |LAST UPDATE DATE: 09/16/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRUCE JORGENSEN RDO | | |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MARK DRISCOLL | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION INVOLVING AN UNDERDOSE OF IODINE-131 | | | | A PRESCRIBED DOSE FOR A PATIENT WAS 1 mCi OF IODINE-131 (SODIUM IODIDE | | FORM), AND THE DOSE GIVEN TO A PATIENT WAS 100 ęCi OF IODINE-131 (SODIUM | | IODIDE FORM). THE REFERRING PHYSICIAN HAS BEEN NOTIFIED, AND THERE ARE NO | | ANTICIPATED ADVERSE HEALTH EFFECTS FOR THE PATIENT. AN ADDITIONAL DOSE OF | | 900 ęCi WAS GIVEN TO THE PATIENT TO COMPLETE THE PRESCRIBED DOSE. IT WAS | | LATER IDENTIFIED THAT THE PATIENT DID NOT HAVE A THYROID. | | | | THE UNDERDOSE WAS DISCOVERED AT APPROXIMATELY 1330 ON SEPTEMBER 15, 1997, | | WHEN THE COUNT RATE OF THE PATIENT WAS LOWER THAN EXPECTED. THE RADIATION | | SAFETY OFFICER WAS NOTIFIED AT APPROXIMATELY 1440 ON SEPTEMBER 15, 1997. | | | | THE LICENSEE CURRENTLY BELIEVES THAT THE CAUSE OF THE UNDERDOSE WAS A | | COMPUTER ENTRY ERROR. TWO VIALS OF IODINE-131 WERE RECEIVED BY THE | | LICENSEE ON THE SAME DAY (AUGUST 25, 1997). ONE VIAL WAS 25 mCi/ml, AND | | THE OTHER VIAL WAS 5 mCi/ml. BOTH VIALS WERE ENTERED INTO THE COMPUTER AS | | 25 mCi/ml. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC REGION 3 OFFICE. (REFER TO THE HOO | | LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32936 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/16/97 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 16:25 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 09/16/97 | +------------------------------------------------+EVENT TIME: 15:20[CDT]| |NRC NOTIFIED BY: TOM SCOTT |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JOHNSON 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 +------------------------------------------------------------------------------+ | DISCOVERY OF A CONDITION WHERE THE AUTOMATIC ISOLATION OF A FAULTED STEAM | | GENERATOR DURING CERTAIN MAIN STEAM LINE OR FEEDWATER LINE BREAKS WOULD NOT | | HAVE OCCURRED AS ASSUMED BY THE LICENSEES SAFETY ANALYSIS | | | | ON 05/14/97, ARKANSAS UNIT 2 REPORTED A CONDITION THAT INVOLVED THE | | POTENTIAL FOR PREMATURE INITIATION OF THE RECIRCULATION ACTUATION SIGNAL IF | | A LOSS OF COOLANT ACCIDENT HAD OCCURRED WITH ONE CHANNEL OF REFUELING WATER | | TANK LEVEL TRIPPED AND ANOTHER LEVEL CHANNEL HAD FAILED (SEE EVENT #32332). | | THIS CONDITION WAS REPORTED IN LICENSE EVENT REPORT 50-368/97-003-00 ON | | JUNE 13, 1997. A SUBSEQUENT REVIEW OF GENERIC IMPLICATIONS OF THIS | | CONDITION IDENTIFIED A SIMILAR POTENTIAL HAD EXISTED FOR STEAM GENERATOR | | DIFFERENTIAL PRESSURE INSTRUMENTATION IN THE EMERGENCY FEEDWATER ACTUATION | | SIGNAL (EFAS). WITH ONE CHANNEL IN A TRIPPED STATE AS ALLOWED BY TECHNICAL | | SPECIFICATIONS, COMBINED WITH ANOTHER SINGLE FAILURE, THE AUTOMATIC | | ISOLATION OF A FAULTED STEAM GENERATOR DURING CERTAIN MAIN STEAM LINE OR | | FEEDWATER LINE BREAKS WOULD NOT HAVE OCCURRED AS ASSUMED BY THE LICENSEE'S | | SAFETY ANALYSIS. ARKANSAS UNIT 2 HAS BEEN UNABLE TO DETERMINE ANY TIME THAT | | OPERATION AT POWER WITH STEAM GENERATOR DIFFERENTIAL PRESSURE IN A TRIPPED | | STATE ACTUALLY OCCURRED. ADMINISTRATIVE CONTROLS HAVE BEEN ESTABLISHED TO | | PREVENT OPERATION IN THIS CONDITION UNTIL THE CHANGE TO TECHNICAL | | SPECIFICATION REQUESTED BY ARKANSAS IS APPROVED BY THE NRC. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | SEE EVENT #32941 FOR A SIMILAR NOTIFICATION FROM WATERFORD. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32937 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING INC. |NOTIFICATION DATE: 09/16/97 | | CITY: MILLS REGION: 4 |NOTIFICATION TIME: 17:00 [ET]| | COUNTY: JOHNSON STATE: WY |EVENT DATE: 09/16/97 | |LICENSE#: SUA1341 AGREEMENT: N |EVENT TIME: 15:00[MDT]| | DOCKET: |LAST UPDATE DATE: 09/16/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JOHNSON RDO | | |MIKE WEBER, NMSS EO | +------------------------------------------------+JOE HOLONICH NMSS | |NRC NOTIFIED BY: JOHN VASELIN | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPILLED 2,440 GALLONS OF WASTE WATER CONTAINING 78.5 PPM NATURAL URANIUM | | | | THE LICENSEE ACCIDENTALLY RUPTURED A 2-INCH PVC PIPE WHICH CIRCULATES WATER | | FROM THE WASTE POND TO THE FILTRATION UNIT. APPROXIMATELY 2,440 GALLONS OF | | POND WASTE WATER CONTAINING 78.5 PPM NATURAL URANIUM SPILLED FROM THE PIPE. | | APPROXIMATELY 1,000 GALLONS OF POND WASTE WATER WAS RECOVERED. THE OTHER | | 1,440 GALLONS OF THE POND WASTE WATER DRAINED AN ADDITIONAL 100 TO 200 | | YARDS BEFORE IT WAS SOAKED UP BY THE GROUND. ALL THE WATER REMAINED IN THE | | OWNER'S CONTROLLED AREA. THE TOTAL AMOUNT OF NATURAL URANIUM NOT RECOVERED | | WAS LESS THAN ONE POUND. THE LICENSEE REPORTED THIS EVENT PER CONDITION 36 | | OF ITS LICENSE WHICH REQUIRES THE LICENSEE TO NOTIFY THE NRC WITHIN 48 | | HOURS AFTER THE OCCURRENCE. THE LICENSEE NOTIFIED THE WYOMING STATE | | DEPARTMENT OF ENVIRONMENTAL QUALITY OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32938 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/16/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:09 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/16/97 | +------------------------------------------------+EVENT TIME: 14:53[EDT]| |NRC NOTIFIED BY: PIETRUSKI |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA 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 +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT MANUALLY STARTED DUE TO CONCERNS ABOUT POSSIBLE | | INSTRUMENT DRIFT OF THE AREA RADIATION MONITORS. | | | | AT 1453 EDT, THE STANDBY GAS TREATMENT SYSTEM WAS MANUALLY STARTED AND | | PLACED INTO SERVICE DUE TO CONCERNS ABOUT POSSIBLE INSTRUMENT DRIFT OF THE | | AREA RADIATION MONITORS WHICH AUTOMATICALLY START THE SYSTEM. | | | | THE SETPOINTS FOR THE AREA RADIATION MONITORS ARE CURRENTLY BEING REVIEWED, | | AND AFTER THE REVIEW IS COMPLETED, THE SETPOINTS WILL BE CHANGED TO ACCOUNT | | FOR INSTRUMENT DRIFT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32939 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/16/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 17:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/16/97 | +------------------------------------------------+EVENT TIME: 16:20[EDT]| |NRC NOTIFIED BY: DEPUYDT |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INSTALLED PLANT MODIFICATION INTRODUCED THE POSSIBILITY OF A SINGLE FAILURE | | WHICH COULD RESULT IN THE LOSS OF BOTH TRAINS OF THE ESF VENTILATION | | SYSTEM. | | | | AT 1620 ON 09/16/97, THE LICENSEE DETERMINED THAT A PLANT MODIFICATION | | INSTALLED BETWEEN DECEMBER 1996 AND AUGUST 1997 INTRODUCED THE POSSIBILITY | | OF A SINGLE FAILURE WHICH COULD RESULT IN THE LOSS OF BOTH TRAINS OF THE | | ESF VENTILATION SYSTEM IF THE 85-PSI AIR HEADER WAS TO BE LOST. PRIOR TO | | THE INSTALLATION OF THE PLANT MODIFICATION, THE ESF VENTILATION SYSTEM | | CHARCOAL INLET AND BYPASS DAMPERS BOTH UTILIZED A 20-PSI AIR HEADER AND | | WERE POSITIONED SUCH THAT THE CHARCOAL BYPASS DAMPERS WERE NORMALLY OPEN | | AND WOULD FAIL CLOSED; AND THE CHARCOAL INLET DAMPERS WERE NORMALLY CLOSED | | AND WOULD FAIL OPEN. THE PLANT MODIFICATION INSTALLED NEW BYPASS DAMPERS | | WHICH REQUIRED HIGHER AIR PRESSURE TO OPERATE AND WERE, THEREFORE, | | TRANSFERRED TO THE 85-PSI HEADER. IF THE 85-PSI AIR HEADER WAS LOST, IT | | WOULD RESULT IN THE REPOSITIONING OF THE NORMALLY OPEN BYPASS DAMPERS | | WITHOUT THE OPENING OF THE CHARCOAL INLET DAMPERS ON BOTH TRAINS. THIS | | WOULD RESULT IN DEAD HEADING OF THE FILTER TRAIN FANS AND LOSS OF COOLING | | TO ECCS EQUIPMENT. | | | | LICENSEE ENGINEERING DEPARTMENT PERSONNEL ARE PURSUING A RESOLUTION TO THIS | | PROBLEM WHICH WILL BE IMPLEMENTED PRIOR TO STARTUP OF BOTH UNITS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32940 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/16/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 19:39 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/16/97 | +------------------------------------------------+EVENT TIME: 18:00[CDT]| |NRC NOTIFIED BY: J JAECKLE |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL FTS 2000 PHONE CIRCUITS AND ALL LONG DISTANCE PHONE CIRCUITS THAT GO | | THROUGH THE LOCAL EXCHANGE ARE INOPERABLE. | | | | AT 1800 CDT, THE LICENSEE DETERMINED THAT ALL ENS, HPN, AND FTS 2000 | | CIRCUITS, AS WELL AS LOCAL LONG DISTANCE CIRCUITS WERE INOPERABLE. | | COMMUNICATIONS WITH THE NRC WAS VERIFIED TO BE OPERABLE VIA COMPANY TIE | | LINE THROUGH MILWAUKEE EXCHANGES, AS WELL AS VIA A DIRECT LINE TO WISCONSIN | | ELECTRIC SYSTEM CONTROL CENTER SERVICE. THE LOCAL TELEPHONE COMPANY HAS | | VERIFIED THAT THE PROBLEM IS WITHIN THEIR SYSTEM AND THEY ARE | | TROUBLESHOOTING THE PROBLEM. NO ESTIMATE OF REPAIR TIME IS CURRENTLY | | AVAILABLE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS EVENT NOTIFICATION. | | | | * * * UPDATE AT 1158 BY JOLLIFFE * * * | | | | ALL PHONE CIRCUITS ARE NOW FULLY OPERABLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32941 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 09/16/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 20:34 [ET]| |RX TYPE: [3] CE |EVENT DATE: 09/16/97 | +------------------------------------------------+EVENT TIME: 18:58[CDT]| |NRC NOTIFIED BY: SNOWDEN |LAST UPDATE DATE: 09/16/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JOHNSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A CONDITION WHERE THE AUTOMATIC ISOLATION OF A FAULTED STEAM | | GENERATOR DURING CERTAIN MAIN STEAM LINE OR FEEDWATER LINE BREAKS WOULD NOT | | HAVE OCCURRED AS ASSUMED BY THE LICENSEE'S SAFETY ANALYSIS | | | | ON 05/15/97, WATERFORD 3 REPORTED A CONDITION THAT INVOLVED THE POTENTIAL | | FOR PREMATURE INITIATION OF THE RECIRCULATION ACTUATION SIGNAL IF A LOSS OF | | COOLANT ACCIDENT HAD OCCURRED COINCIDENT WITH ONE CHANNEL OF REFUELING | | WATER STORAGE POOL (RWSP) LEVEL INSTRUMENTATION IN THE TRIPPED CONDITION | | AND FAILURE OF ANOTHER CHANNEL OF RWSP LEVEL INSTRUMENTATION. THIS | | CONDITION WAS REPORTED IN LICENSEE EVENT REPORT 50-382/97-016-00 ON JUNE | | 16, 1997. A SUBSEQUENT REVIEW OF GENERIC IMPLICATIONS FOR THAT CONDITION | | IDENTIFIED A SIMILAR POTENTIAL HAD EXISTED FOR STEAM GENERATOR DIFFERENTIAL | | PRESSURE INSTRUMENTATION ASSOCIATED WITH THE EMERGENCY FEEDWATER ACTUATION | | SIGNAL (EFAS). WITH ONE CHANNEL IN A TRIPPED CONDITION AS ALLOWED BY | | TECHNICAL SPECIFICATIONS, COMBINED WITH A FAILURE OF ANOTHER CHANNEL OF | | STEAM GENERATOR DIFFERENTIAL PRESSURE INSTRUMENTATION AND A MAIN STEAM LINE | | BREAK, THE AUTOMATIC ISOLATION OF A FAULTED STEAM GENERATOR FROM EMERGENCY | | FEEDWATER WOULD NOT HAVE OCCURRED AS ASSUMED BY THE LICENSEE'S SAFETY | | ANALYSIS. THIS CONDITION WOULD ALSO HAVE AN IMPACT ON A FEEDWATER LINE | | BREAK. THE LICENSEE HAS BEEN UNABLE TO DETERMINE ANY TIME THAT OPERATION AT | | POWER WITH STEAM GENERATOR DIFFERENTIAL PRESSURE INSTRUMENTATION IN A | | TRIPPED CONDITION ACTUALLY OCCURRED. ADMINISTRATIVE CONTROLS HAVE BEEN | | ESTABLISHED TO PREVENT OPERATION IN THIS CONDITION UNTIL THE TECHNICAL | | SPECIFICATIONS CAN BE CHANGED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | SEE EVENT #32936 FOR SIMILAR NOTIFICATION FROM ARKANSAS UNIT 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32942 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 09/17/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 01:56 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/16/97 | +------------------------------------------------+EVENT TIME: 21:47[EDT]| |NRC NOTIFIED BY: DAVE WALSH |LAST UPDATE DATE: 09/17/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 22 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 SHUTTING DOWN DUE TO INCREASED TREND IN UNIDENTIFIED DRYWELL LEAKAGE | | | | ON 09/12/97, THE LICENSEE OBSERVED AN INCREASE IN UNIT 2 DRYWELL LEAKAGE. | | PRIOR TO 09/12/97, STEADY STATE DRYWELL LEAKAGE VALUES WERE APPROXIMATELY | | 0.02 GPM. ON 09/12/97, THE LICENSEE OBSERVED AN INCREASE IN CONTAINMENT | | PARTICULATE RADIATION ALONG WITH AN INCREASE IN DRYWELL SUMP ACTIVITY. | | CHEMISTRY SAMPLES OF REACTOR BUILDING SUMPS REVEALED THE PRESENCE OF | | SODIUM-24, INDICTING A HIGH PROBABILITY THAT THE SOURCE OF LEAKAGE WAS | | FROM THE REACTOR WATER CLEANUP SYSTEM OR THE REACTOR RECIRCULATION SYSTEM. | | OTHER CONTAINMENT PARAMETERS SUCH AS PRESSURE AND TEMPERATURE HAVE REMAINED | | STABLE. | | | | ON 09/16/97 EVENING, THE TOTAL UNIDENTIFIED LEAKAGE WAS APPROXIMATELY | | 2.14 GPM. NO TECH SPEC LIMITS (LESS THAN 5 GPM UNIDENTIFIED LEAKAGE | | AND/OR NO MORE THAN A 2-GPM INCREASE IN UNIDENTIFIED LEAKAGE OVER A | | 24-HOUR PERIOD; LESS THAN 25 GPM IDENTIFIED LEAKAGE) HAVE BEEN IMPACTED. | | | | THE LICENSEE IS PERFORMING AN ORDERLY SHUTDOWN TO INVESTIGATE AND REPAIR | | THE SOURCE OF THE UNIDENTIFIED LEAKAGE. | | | | THIS PLANT SHUTDOWN IS NOT REQUIRED BY PLANT TECH SPECS. THE LICENSEE IS | | MAKING THIS NOTIFICATION AS A COURTESY CALL TO THE NRC. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+