U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/12/97 - 09/15/97 ** EVENT NUMBERS ** 32650 32803 32914 32917 32918 32919 32920 32921 32922 32923 32924 32925 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32650 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 07/18/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 18:55 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 07/18/97 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: MIKE JACOBS |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - RHR SYSTEM FLOW RATE IN OPERATING PROCEDURE DIFFERENT THAN DBA ANALYSIS - | | | | DURING AN NRC REGION I INSPECTION OF PILGRIM, THE LICENSEE DISCOVERED THAT | | THE PLANT OPERATING PROCEDURE FOR THE RESIDUAL HEAT REMOVAL (RHR) SYSTEM | | SPECIFIES OPERATION IN THE EMERGENCY MODE THAT IS DIFFERENT THAN | | ASSUMPTIONS MADE IN THE DESIGN BASIS ACCIDENT (DBA) ANALYSIS. THE ASSUMED | | FLOW RATE FOR THE CONTAINMENT HEAT REMOVAL FUNCTION OF THE RHR SYSTEM IN | | THE DBA ANALYSIS IS 5,100 GPM. THE RHR SYSTEM PLANT OPERATING PROCEDURE | | SPECIFIES A RANGE OF 4,800 TO 5,100 GPM WHEN PERFORMING THE CONTAINMENT | | HEAT REMOVAL FUNCTION. OPERATION AT THE LOWER END OF THIS RANGE, COUPLED | | WITH INSTRUMENT INACCURACIES, WOULD RESULT IN LESS HEAT TRANSFER THAN | | ASSUMED IN THE DBA ANALYSIS. | | | | THE LICENSEE HAS PERFORMED AN OPERABILITY EVALUATION AND CONSIDERS THE | | SYSTEM OPERABLE. THE LICENSEE IS IMPLEMENTING A PROCEDURE CHANGE TO ALLOW | | OPERATION UP TO 5,600 GPM TO ENSURE RATED HEAT REMOVAL DURING A DBA. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1120 ON 09/12/97 FROM MIKE JACOBS RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. FURTHER ENGINEERING | | EVALUATIONS INCORPORATING INSTRUMENT INACCURACIES CONCLUDED THAT THE RHR | | SYSTEM WOULD HAVE BEEN CAPABLE OF PERFORMING ITS DESIGN BASIS FUNCTION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (ROGGE). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32803 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/22/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:13 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 08/22/97 | +------------------------------------------------+EVENT TIME: 13:51[EDT]| |NRC NOTIFIED BY: BRAIN SULLIVAN |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM DECLARED INOPERABLE DUE TO | | ERRATIC INDICATIONS FROM THE RCIC PUMP DISCHARGE FLOW TRANSMITTER | | | | DURING ROUTINE CONTROL ROOM OBSERVATIONS, REACTOR OPERATORS NOTICED THAT | | THE RCIC PUMP DISCHARGE FLOW INDICATION INTERMITTENTLY JUMPED FROM 0 gpm TO | | 100 gpm. THE LICENSEE DECLARED RCIC INOPERABLE AND ENTERED TECHNICAL | | SPECIFICATION 3.5 (14 DAYS TO RESTORE RCIC TO SERVICE OR SHUT DOWN). THE | | LICENSEE THINKS THAT AIR IN THE SENSING LINES TO FT-1360-4 IS CAUSING THE | | INTERMITTENT INDICATIONS. THE LICENSEE HAS A WORK REQUEST TO CORRECT THIS | | PROBLEM. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1112 ON 08/23/97 FROM SULLIVAN TAKEN BY WEAVER * * * | | | | RCIC SYSTEM RESTORED AT 1110. THE LICENSEE PLANS TO INFORM THE NRC | | RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (BILL | | RULAND). | | | | * * * UPDATE AT 1120 ON 09/12/97 FROM MIKE JACOBS RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. FURTHER ENGINEERING | | EVALUATIONS DETERMINED THAT THE AMOUNT OF AIR FOUND IN THE REFERENCE LEG OF | | THE FLOW TRANSMITTER WOULD NOT HAVE PREVENTED RCIC FROM PERFORMING ITS | | INTENDED FUNCTION. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE | | NRC OPERATIONS CENTER NOTIFIED THE R1DO (ROGGE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32914 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 19:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 16:15[EDT]| |NRC NOTIFIED BY: MARY BETH DePUYDT |LAST UPDATE DATE: 09/13/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED THAT BOTH UNITS HAD OPERATED THEIR RHR SYSTEM CONTRARY | | TO THE DESCRIPTION IN THE FSAR. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1615 EDT, WITH UNITS 1 AND 2 SHUTDOWN IN MODE 5, IT WAS DETERMINED THAT | | BOTH UNITS HAVE OPERATED CONTRARY TO THE DESIGN BASIS FOR THE RESIDUAL HEAT | | REMOVAL (RHR) SYSTEM AS DESCRIBED IN THE FSAR. FSAR CHAPTER 9, SECTION | | 9.3, DESCRIBES THE INTERLOCKS ASSOCIATED WITH THE RHR SUCTION VALVES FROM | | THE REACTOR COOLANT SYSTEM (RCS). THE SUCTION LINE VALVES ARE INTERLOCKED | | THROUGH SEPARATE CHANNELS OF THE RCS SYSTEM PRESSURE SIGNALS TO PROVIDE | | AUTOMATIC CLOSURE OF BOTH VALVES WHENEVER RCS PRESSURE EXCEEDS RHR DESIGN | | PRESSURE. THE FSAR STATES THAT THE INTERLOCK MAY BE DEFEATED WHEN THE RCS | | IS OPEN TO ATMOSPHERE. HOWEVER, FOR A NUMBER OF YEARS THIS INTERLOCK HAS | | BEEN PROCEDURALLY DEFEATED ON BOTH UNITS TO PREVENT INADVERTENT CLOSURE AND | | LOSS OF RHR SUCTION DURING SHUTDOWN COOLING OPERATION BY OPENING THE VALVES | | AND RACKING OUT THEIR BREAKERS IN MODE 4. | | | | THE OVER PRESSURE PROTECTION AFFORDED BY THE AUTOMATIC CLOSURE FUNCTION | | DESCRIBED IN THE FSAR WAS DEFEATED WITHOUT A SAFETY EVALUATION BEING | | PERFORMED. THIS LOSS OF AUTOMATIC CLOSURE FUNCTION REPRESENTS AN | | UNANALYZED CONDITION AND IS, THEREFORE, REPORTABLE. | | | | PLANS ARE TO DEGAS, DEPRESSURIZE, AND OPEN THE RCS ON BOTH UNITS TO | | ATMOSPHERE. DEGAS WILL START ON UNIT 1, AND WHEN COMPLETED, THE UNIT WILL | | PROCEED TO DEPRESSURIZE WHILE UNIT 2 STARTS DEGAS PROCEDURES. WHEN THE RCS | | IS OPEN TO ATMOSPHERE ON BOTH UNITS, THE PLANT WILL BE IN COMPLIANCE WITH | | THE FSAR." | | | | THIS CONDITION WAS IDENTIFIED BY THE LICENSEE DURING AN ONGOING NRC | | ARCHITECT/ENGINEER INSPECTION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2130 EDT ON 9/13/97 FROM ROBERT BLYTH TO S. SANDIN * * * | | | | THE LICENSEE HAS COMPLETED ITS SAFETY EVALUATION FOR MODE 5 OPERATION AND | | CONCLUDED THAT THERE WAS NO UNREVIEWED SAFETY QUESTION OR CHANGE OF | | OPERATION AS DESCRIBED IN THE FSAR. CONSEQUENTLY, DEGAS OF UNIT 1 HAS BEEN | | TERMINATED, AND NEITHER UNIT WILL BE VENTED TO ATMOSPHERE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (RING). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32917 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/12/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 11:13 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/12/97 | +------------------------------------------------+EVENT TIME: 10:25[EDT]| |NRC NOTIFIED BY: GLEN LONG |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 88 POWER OPERATION | 88 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SINGLE FAILURE CAN PREVENT THE FUNCTION OF THE PRESSURE SUPPRESSION | | FUNCTION OF CONTAINMENT. | | | | DURING REVIEW OF PLANT PROCEDURES AND DESIGN OF SYSTEMS UTILIZED TO INERT | | AND DE-INERT PRIMARY CONTAINMENT, IT WAS DETERMINED THAT A SINGLE FAILURE | | CAN PREVENT THE FUNCTION OF THE PRESSURE SUPPRESSION FUNCTION OF | | CONTAINMENT. SPECIFICALLY, THE INBOARD ISOLATION VALVES FOR THE CONTAINMENT | | ATMOSPHERIC CONTROL INERTING SYSTEM FOR THE TORUS AND DRYWELL UTILIZE A | | COMMON RELAY. A CREDIBLE SINGLE FAILURE EXISTS WHICH COULD PREVENT BOTH | | VALVES FROM CLOSING DURING A LOCA WHILE INERTING. BOTH VALVES ARE NORMALLY | | SHUT AT POWER. FAILURE OF THESE VALVES TO CLOSE WITH A GROUP 6 ISOLATION | | SIGNAL ON HIGH DRYWELL PRESSURE WOULD ALLOW BYPASS OF STEAM FROM A LOCA | | INTO THE AIR SPACE OF THE TORUS PREVENTING COMPLETE QUENCHING AND PRESSURE | | SUPPRESSION. A POTENTIAL TO OVER PRESSURIZE THE DRYWELL EXISTS. THIS IS | | ONLY APPLICABLE TO A SMALL BREAK LOCA WHICH HAS A SLOW PRESSURE RISE IN | | CONTAINMENT DURING INERTING OR DE-INERTING ACTIVITIES. FOR THIS CONDITION | | TO OCCUR, THE FOLLOWING HAS TO HAPPEN: 1) SIMULTANEOUSLY INERTING OR | | PURGING THE DRYWELL AND SUPPRESSION POOL, 2) A SMALL BREAK LOCA OCCURS, AND | | 3) A SINGLE FAILURE OF A CONTACT TO OPEN IN THE GROUP 6 LOGIC; THE | | SUPPRESSION FUNCTION OF THE SUPPRESSION POOL WOULD BE BYPASSED. | | | | THIS ACCIDENT IS ONLY APPLICABLE WITH THE PLANT IN HOT SHUTDOWN OR AT POWER | | WITH THE ABOVE INFREQUENT PLANT CONFIGURATION. THE TIME SPENT INERTING OR | | PURGING IS STRICTLY LIMITED BY TECHNICAL SPECIFICATION WHILE AT POWER. IN | | ORDER TO EXCEED DESIGN BASIS PRESSURE REQUIREMENTS, A SMALL BREAK LOCA MUST | | OCCUR IN CONJUNCTION WITH SIMULTANEOUS INERTING OR PURGING OF THE DRYWELL | | AND SUPPRESSION POOL. A SENSITIVITY ANALYSIS HAS BEEN INCLUDED AS PART OF | | THE UFSAR WHICH INDICATES THAT THE PRESSURE SUPPRESSION FUNCTION WILL NOT | | FAIL IN THIS EVENT WITH THE SUPPRESSION POOL BYPASS AREA EQUIVALENT TO A | | SIX-INCH PIPE. THIS SINGLE FAILURE CONFIGURATION ALLOWS BYPASS FLOW ACROSS | | AN 18-INCH BUTTERFLY VALVE THROTTLED TO 45 DEGREES. | | | | CORRECTIVE ACTION: ALL APPLICABLE PROCEDURES HAVE BEEN ADMINISTRATIVELY | | PLACED ON HOLD UNTIL PROVISIONS WHICH ALLOW SIMULTANEOUS INERTING OR | | DE-INERTING OF THE DRYWELL AND TORUS HAVE BEEN REMOVED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32918 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/12/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/12/97 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE CONTACTED THE OHIO EPA AFTER IDENTIFYING A POTENTIAL RELEASE | | OF CHLORINATED WATER TO THE STORM SEWER SYSTEM. | | | | THE FOLLOWING INFORMATION WAS RECEIVED FROM THE LICENSEE VIA FAX: | | | | "PROBLEM ISSUE FORM 97-1270 WAS WRITTEN ON A BROKEN PIPE ON THE SERVICE | | WATER SYSTEM. THIS PIPE CONTAINED STAGNANT WATER (RAW LAKE ERIE) WHICH IS | | DESIGNED TO DRAIN TO STORM DRAINS. NO REPORTABLE RELEASE OCCURRED DUE TO | | THIS EVENT, HOWEVER, THE DESIGN OF THE STRAINER/BACKWASH SYSTEM ALLOWS FOR | | AUTO BACKWASH TO STORM DRAINS PERIODICALLY (APPROXIMATELY EVERY 24 HOURS). | | THIS IS POTENTIALLY A VIOLATION OF NPDES PERMIT. HISTORICAL PERMIT | | APPLICATION DATA SHOULD BE REVIEWED ALONG WITH OTHER DOCUMENTS TO DETERMINE | | COMPLIANCE." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32919 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 09/12/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:46 [ET]| |RX TYPE: [1] CE |EVENT DATE: 09/12/97 | +------------------------------------------------+EVENT TIME: 14:20[EDT]| |NRC NOTIFIED BY: CHARLIE KOZUP |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A 'HOT SHORT' SCENARIO WHICH COULD RESULT IN THE LOSS OF THE | | COMPONENT COOLING WATER SYSTEM | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AN APPENDIX 'R' REVIEW OF THE COMPONENT COOLING WATER SYSTEM AND THE | | SERVICE WATER SYSTEM DETERMINED A NEW 'HOT SHORT' SCENARIO WHICH COULD | | RESULT IN THE LOSS OF [THE] COMPONENT COOLING WATER SYSTEM. THE 'HOT | | SHORT' COULD OPEN [VALVES] CV-0951, CV-0880, OR CV-0879 WHICH COULD DRAIN | | THE COMPONENT COOLING WATER TO THE SERVICE WATER SYSTEM RESULTING IN THE | | LOSS OF [THE] COMPONENT COOLING WATER SYSTEM. THE COMPONENT COOLING WATER | | SYSTEM IS REQUIRED TO COOL THE SEALS OF THE ENGINEERED SAFETY FEATURE PUMPS | | REQUIRED FOR POST FIRE SAFE SHUTDOWN. APPENDIX 'R' REQUIRES THAT A SINGLE | | 'HOT SHORT' SHOULD NOT RESULT IN A LOSS OF REQUIRED SYSTEMS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32920 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING COMPANY |NOTIFICATION DATE: 09/12/97 | | CITY: MILLS REGION: 4 |NOTIFICATION TIME: 15:23 [ET]| | COUNTY: JOHNSON STATE: WY |EVENT DATE: 09/12/97 | |LICENSE#: SUA1341 AGREEMENT: N |EVENT TIME: 15:00[MDT]| | DOCKET: |LAST UPDATE DATE: 09/12/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BLAIR SPITZBERG RDO | | |SUSAN SHANKMAN EO | +------------------------------------------------+JOE HOLONICH NMSS | |NRC NOTIFIED BY: JOHN VASELINE | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT WELL SSM#41 (IRIGARAY) LOCATED APPROXIMATELY 100 | | MILES NORTH NORTHEAST OF CASPER, WY. WAS IN EXCURSION FOR 2 OF THE 3 | | MONITORED PARAMETERS. THE MONITORED PARAMETERS WITH UPPER CONTROL LIMITS | | (UCL) ARE: | | | | CHLORIDES (UCL) 24.9 MG/L, SAMPLES (9/10) 31.4, (9/11) 30.5 | | CONDUCTIVITY (UCL) 2566 UMHO/CM, SAMPLES (9/10) 2378, (9/11) 2361 | | ALKALINITY (UCL) 126.8 MG/L, SAMPLES (9/10) 128.5, (9/11) 127.1 | | | | THE LICENSEE HAS INCREASED THE FREQUENCY OF SAMPLING FROM MONTHLY TO WEEKLY | | AND IS ALSO MONITORING FOR URANIUM. THIS PARTICULAR WELL IS A SHALLOW | | MONITORING WELL ABOVE THE AQUIFER TO MONITOR THE OUT-OF-PRODUCTION WELL | | UNDERGOING RESTORATION. THE LICENSEE WILL SUBMIT A WRITTEN REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32921 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/12/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/12/97 | +------------------------------------------------+EVENT TIME: 15:19[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED THAT BOTH RHR PUMPS HAD BEEN OPERATED WHEN THE RCS | | WAS DEPRESSURIZED, WHICH IS CONTRARY TO THE DESCRIPTION IN THE FSAR. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "CHAPTER 9 OF THE FSAR STATES: 'ONLY ONE RESIDUAL HEAT REMOVAL (RHR) PUMP | | WILL BE OPERATED WHEN THE REACTOR COOLANT SYSTEM IS OPEN TO ATMOSPHERE TO | | PREVENT DAMAGING BOTH PUMPS IN THE UNLIKELY EVENT THAT SUCTION SHOULD BE | | LOST.' OPERATING PROCEDURES FOR THE RHR SYSTEM DO NOT PREVENT OPERATION OF | | BOTH RHR PUMPS WHEN THE RCS IS OPEN TO ATMOSPHERE, AND IN THE PAST, BOTH | | RHR PUMPS HAVE BEEN RUN WHEN THE RCS WAS VENTED TO ATMOSPHERE. | | | | PLANT OPERATING PROCEDURES ARE BEING REVIEWED TO DETERMINE THE IMPACT. | | PROCEDURE CHANGES WILL BE IMPLEMENTED AS NECESSARY TO ADDRESS THE FSAR | | REQUIREMENT. A CONDITION REPORT HAS BEEN INITIATED TO INVESTIGATE AND | | DETERMINE APPROPRIATE PREVENTATIVE ACTIONS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32922 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/12/97 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 18:50 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/12/97 | +------------------------------------------------+EVENT TIME: 15:22[CDT]| |NRC NOTIFIED BY: KURT RATHGABER |LAST UPDATE DATE: 09/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 +------------------------------------------------------------------------------+ | UNEXPECTED TRIP OF ONE OF THE OPERATING CHARGING PUMPS DURING SOLID PLANT | | OPERATION POSSIBLY DUE TO MAINTENANCE ACTIVITIES. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1522 CDT, WHILE MAINTAINING UNIT 2 IN COLD SHUTDOWN IN SOLID PLANT | | OPERATIONS, ONE OF TWO OPERATING CHARGING PUMPS BEING USED TO MAINTAIN | | REACTOR COOLANT SYSTEM INVENTORY AND PRESSURE TRIPPED. PRESSURE CONTROL | | WAS MAINTAINED BY INCREASING FLOW FROM THE REMAINING CHARGING PUMP AND | | REDUCING RCS LETDOWN FLOW. THE CAUSE OF THIS EVENT APPEARS TO BE ACTUATION | | OF AN 'A' TRAIN SAFEGUARDS 480 VOLT BUS UNDERVOLTAGE PROTECTION FOLLOWER | | RELAY. ACTUATION OF THIS RELAY WOULD TRIP THE OPERATING CHARGING PUMP, | | THREE BANKS OF PRESSURIZER HEATERS AND THE 'A' TRAIN RHR PUMP IF IT WERE | | OPERATING. THE RHR PUMP AND PRESSURIZER HEATERS WERE NOT OPERATING AT THE | | TIME. ANOTHER CHARGING PUMP THAT WOULD HAVE TRIPPED FOLLOWING THE RELAY | | ACTUATION DID NOT START WHEN ATTEMPTED. TAKING THE CONTROL SWITCH TO OFF | | AND BACK TO START ALLOWED THE PUMP TO START. ACTUATION OF THE FOLLOWER | | RELAY IS CONSIDERED TO BE A PARTIAL ACTUATION OF AN ENGINEERED SAFEGUARDS | | FEATURE. | | | | THE FOLLOWER RELAY ACTUATION IS BELIEVED TO HAVE BEEN CAUSED BY WORK | | ACTIVITIES ASSOCIATED WITH A MODIFICATION INSTALLATION. AN INADVERTENT | | BUMP OF THE RELAY WOULD CAUSE THE OBSERVED EQUIPMENT TRIPS. THIS | | INADVERTENT BUMP HAS NOT BEEN CONFIRMED AND IS STILL BEING INVESTIGATED. | | THERE WAS NO INDICATION OF AN UNDERVOLTAGE CONDITION AND THE ACTUATION | | LOGIC WAS NOT SATISFIED. | | | | CURRENTLY ACTIVITIES IN THE CABINET HAVE STOPPED. PRESSURE AND INVENTORY | | CONTROL ARE RETURNED TO NORMAL AND ALL RELATED EQUIPMENT HAS BEEN RETURNED | | TO A NORMAL STATUS. INVESTIGATION OF THE CAUSE IN CONTINUING. | | | | WE ARE REPORTING THIS EVENT UNDER 10CFR50.72(b)(2)(ii) ESF ACTUATION. THE | | ESF DEVICE THAT ACTUATED US AN UNDERVOLTAGE LOAD SHEDDING FOLLOWER RELAY | | DESIGNED TO STRIP LOAD ON THE SAFEGUARDS 480 VOLT BUSES PRIOR TO DIESEL | | START AND LOAD. THIS PARTIAL ESF ACTUATION WAS NOT THE RESULT OF A VALID | | ACTUATION SIGNAL." | | | | UNIT 2 HAS THREE CHARGING PUMPS; THE "A" AND "B" PUMPS ASSOCIATED WITH THE | | "A" TRAIN AND THE REMAINING "C" PUMP ASSOCIATED WITH THE "B" TRAIN. AT THE | | TIME OF THE EVENT, BOTH THE "B" AND "C" CHARGING PUMPS WERE OPERATING. | | AFTER THE "B" CHARGING PUMP TRIPPED, OPERATORS STARTED THE "A" CHARGING | | PUMP TO RESTORE PRESSURE. PRESSURE DECREASED TO A MINIMUM OF 260 PSIG | | DURING THE TRANSIENT PRIOR TO BEING RETURNED TO THE OPERATING BAND OF 350 | | TO 400 PSIG. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32923 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 07:47 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/13/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:12[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/14/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |SUSAN SHANKMAN EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RON CRABTREE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-CFR REQUIRED 24-HOUR REPORT | | | | THE FOLLOWING IS TEXT FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 0812 HOURS ON 9/13/97, SMOKE DETECTORS S-68 AND S-85 OF THE CASCADE | | AUTOMATIC DATA PROCESSING (CADP) SYSTEMS ACTUATED. TWO PREVIOUS ACTUATIONS | | OF THESE SAME SMOKE DETECTORS OCCURRED ON 9/12/97 AND 9/13/97. ON THE FIRST | | ACTUATION OF THESE CADP SMOKE DETECTORS, THE CELL WAS TAKEN OFFSTREAM. | | RADIOLOGICAL MONITORING (AIRBORNE AND WIPE SAMPLING) BY HEALTH PHYSICS | | PERSONNEL COULD NOT SUPPORT AN OUTGASSING OF UF6 AT THAT LOCATION AS ALL | | SAMPLE RESULTS WERE LESS THAN DETECTION LIMITS. WHILE INVESTIGATING THE | | 9/13/97 0812 HOURS ACTUATION, OPERATIONS PERSONNEL DISCOVERED A POTENTIAL | | SOURCE OF UF6 FROM A KINKED 1/4" INSTRUMENT LINE. THE KINKED INSTRUMENT | | LINE WAS ISOLATED FROM THE PROCESS SYSTEM AND APPEARS TO HAVE RESOLVED THE | | CADP SMOKEHEAD ACTUATIONS. THIS EVENT IS BEING PROCESSED AS A Q SAFETY | | SYSTEM ACTUATION DUE TO VALID SIGNAL, AS THE CADP SMOKE DETECTION SYSTEM IS | | DESIGNED TO ACTUATE IN THE PRESENCE OF UF6 GAS (SMOKE). THIS EVENT IS | | REPORTABLE TO THE NRC PER EVENT REPORTING PROCEDURE UE2-RA-RE1030, APPENDIX | | D, SECTION J, PARAGRAPH #2 (24-HOUR REPORT). THERE WAS NO RELEASE OF | | HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURES ASSOCIATED WITH | | THE Q SYSTEM ALARM ACTUATION. THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED | | OF THIS EVENT." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32924 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/14/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:49 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/14/97 | +------------------------------------------------+EVENT TIME: 07:11[EDT]| |NRC NOTIFIED BY: DEVIN PRICE |LAST UPDATE DATE: 09/14/97 | |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 +------------------------------------------------------------------------------+ | AUTOMATIC START OF SACS PUMP DUE TO IMPROPERLY PERFORMED PROCEDURE | | | | THE 'A' SAFETY AUXILIARIES COOLING SYSTEM (SACS) PUMP AUTOMATICALLY STARTED | | DUE TO AN INTERLOCK WITH ITS ASSOCIATED TSC CHILL WATER CIRCULATING PUMP. | | THE LICENSEE WAS IN THE PROCESS OF SWAPPING OVER TO THE 'C' SACS PUMP AT | | THE TIME OF THE EVENT. THE INTERLOCK IS DESIGNED TO PROVIDE SACS COOLING | | WATER TO THE TSC CHILLER IF IT IS RUNNING. THE LICENSEE REPORTED THAT THE | | EVENT WAS CAUSED BY AN IMPROPERLY PERFORMED PUMP SWAP. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32925 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/14/97 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 12:39 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/14/97 | +------------------------------------------------+EVENT TIME: 09:11[MST]| |NRC NOTIFIED BY: JEAN-MARC L'EPLATTENIER |LAST UPDATE DATE: 09/14/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ART HOWELL RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY REPORT. | | | | DISCOVERY OF AN UNATTENDED SECURITY WEAPON. IMMEDIATE COMPENSATORY | | MEASURES WERE TAKEN ON DISCOVERY. THE LICENSEE PLANS TO INFORM THE NRC | | RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+