U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/03/97 - 09/04/97 ** EVENT NUMBERS ** 32862 32863 32864 32865 32866 32867 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32862 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/03/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:52 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/02/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:45[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/03/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE #2 SHELL HIGH STEAM PRESSURE SHUTDOWN (24-HOUR REPORT) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "ON 9/2/97 AT 1345 HOURS, THE OPERATORS AT [THE] X-342A FEED VAPORIZATION | | AND FLUORINE GENERATION FACILITY RECEIVED AN AUDIBLE AND VISUAL ALARM | | INDICATING STEAM SHUTDOWN OF AUTOCLAVE #2. THE INITIAL INVESTIGATION | | REVEALED THAT THE AUTOCLAVE SHELL HIGH STEAM PRESSURE SHUTDOWN HAD | | ACTIVATED WITH A 22.0 PSIA READING FOR INTERNAL AUTOCLAVE HIGH PRESSURE. | | THE LIMITING CONTROL SETTING FOR AUTOCLAVE SHELL HIGH STEAM SHUTDOWN IS | | 22.45 ñ 2.0 PSIA. THE AUTOCLAVE CONTAINED A UF6 CYLINDER AND WAS IN MODE | | II (HEATING)." | | | | "AUTOCLAVE #2 WAS IMMEDIATELY SHUTDOWN AND DECLARED INOPERABLE AT 1345 | | HOURS. THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL | | EXPOSURES ASSOCIATED WITH THIS ACTUATION." | | | | "THE AUTOCLAVE SHELL HIGH PRESSURE STEAM SHUTDOWN IS A 'DEFENSE-IN-DEPTH' | | SYSTEM THAT SUPPORTS THE UF6 CYLINDER HIGH TEMPERATURE AUTOCLAVE STEAM | | SHUTDOWN SYSTEM. THE HIGH STEAM PRESSURE SHUTDOWN SYSTEM CONSISTS OF | | PRESSURE SENSING CHANNELS AND TWO CHANNELS OF ISOLATION VALVES." | | | | PORTSMOUTH NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT OF ENERGY | | SITE MANAGER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32863 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/03/97 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 10:37 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/02/97 | +------------------------------------------------+EVENT TIME: 16:40[CDT]| |NRC NOTIFIED BY: KEN TAPLETT |LAST UPDATE DATE: 09/03/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE LIFT SETPOINTS FOR TWO MAIN STEAM SAFETY VALVES WERE OUT | | OF TOLERANCE | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ASME CODE INSERVICE TESTING OF UNIT 1 MAIN STEAM SAFETY VALVES IS BEING | | CONDUCTED PURSUANT TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT | | 4.7.1.1. THE FOLLOWING MAIN STEAM SAFETY VALVES HAVE TESTED HIGH OUT OF | | TOLERANCE OF TECHNICAL SPECIFICATION 3.7.1.1 REQUIREMENTS. | | | | VALVE SETTING AS-FOUND LIFT RESULT PERCENT ERROR | | PSV-7430A 1,295 PSIG 1,362.62 PSIG 5.22% | | PSV-7430B 1,305 PSIG 1,358.86 PSIG 4.13% | | | | THE VALVES WERE TESTED ONE AT A TIME AND HAVE BEEN ADJUSTED AND TESTED TO | | WITHIN 1% OF TECHNICAL SPECIFICATION 3.7.1.1 [REQUIREMENTS]. TESTING WILL | | CONTINUE FOR ALL 20 MAIN STEAM SAFETY VALVES. | | | | (1) THE PROBABLE CAUSE OF THE HIGH OUT OF TOLERANCE LIFT IS THE PROMOTION | | OF OXIDE LOCKING AND GALLING WITH SUBSEQUENT BONDING BETWEEN THE VALVE | | NOZZLE AND DISC AS REPORTED IN SOUTH TEXAS PROJECT UNIT LICENSEE EVENT | | REPORT 97-005. INVESTIGATION IS ONGOING." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32864 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/03/97 | |UNIT: [1] [2] [ ] STATE: AR |NOTIFICATION TIME: 14:06 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 09/03/97 | +------------------------------------------------+EVENT TIME: 12:29[CDT]| |NRC NOTIFIED BY: SAULSBERRY |LAST UPDATE DATE: 09/03/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM (SPDS) OUT OF SERVICE FOR MORE THAN ONE | | HOUR | | | | AT 1229 CDT ON 09/03/97, SPDS WAS DETERMINED TO BE INOPERABLE FOR GREATER | | THAN ONE HOUR IN THE TECHNICAL SUPPORT CENTER (TSC) ONLY. THE SYSTEM WAS | | RENDERED INOPERABLE DUE TO EXTENDED MAINTENANCE. GUIDANCE CONTAINED WITHIN | | PROCEDURES 1105.014 (UNIT 1) AND 2105.014 (UNIT 2) REQUIRES A ONE-HOUR | | REPORT PER THE CODE OF FEDERAL REGULATIONS. THE LICENSEE IS CONTINUING TO | | WORK ON THE PROBLEM, AND IT IS NOT KNOWN AT THIS TIME WHEN THE SPDS IN THE | | TSC WILL BE RETURNED TO SERVICE. DATA TRANSMISSION IN THE EMERGENCY | | OPERATIONS FACILITY AND CONTROL ROOM IS UNAFFECTED BY THIS PROBLEM. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32865 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/03/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 14:10 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/03/97 | +------------------------------------------------+EVENT TIME: 13:10[CDT]| |NRC NOTIFIED BY: KURT RATHGABER |LAST UPDATE DATE: 09/03/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM CREED RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRAIN "A" SAFETY-RELATED BUSES COULD DEVELOP AN UNDERVOLTAGE CONDITION | | DURING CERTAIN ACCIDENT SEQUENCES. | | | | A COMPUTER MODEL SHOWS THAT UNDER CERTAIN ACCIDENT SEQUENCES, THERE COULD | | BE AN UNDERVOLTAGE CONDITION ON THE "A"-TRAIN 480-VOLT SAFEGUARDS BUSES | | THAT WOULD CAUSE THEM TO DEENERGIZE AND THEN RESEQUENCE LOADS. THIS COULD | | POSSIBLY OCCUR IF THE FOLLOWING CONDITIONS WERE MET: SIMULTANEOUS LOSS OF | | COOLANT ACCIDENT OR MAIN STEAM LINE BREAK AND LOSS OF OFFSITE POWER | | CONDITIONS, A SINGLE EMERGENCY DIESEL GENERATOR (EDG) AVAILABLE FOR THE | | UNIT 1 AND UNIT 2 "A"-TRAIN SAFETY-RELATED BUSES, AND SIMULTANEOUS STARTING | | OF A CONTAINMENT SPRAY PUMP AND A THIRD SERVICE WATER PUMP DURING | | SAFEGUARDS SEQUENCING. THE 480-VOLT "A"-TRAIN BUS WOULD RECEIVE AN | | UNDERVOLTAGE TRIP DUE TO THE SIMULTANEOUS STARTING OF THE THIRD SERVICE | | WATER PUMP AND THE CONTAINMENT SPRAY PUMP. THIS TRANSIENT WOULD DROP THE | | BUS VOLTAGE TO LESS THAN THE UNDERVOLTAGE TRIP RELAY SETPOINT FOR A PERIOD | | LONG ENOUGH TO CAUSE THE RELAY TO ENERGIZE AND STRIP THE BUS. THIS BUS | | LOSS AND SUBSEQUENT AUTOMATIC RESEQUENCING ARE CONSIDERED BY THE LICENSEE | | TO BE AN UNANALYZED CONDITION. | | | | THIS ISSUE IS BEING REPORTED UNDER 10 CFR 50.72(b)(1)(ii)(A) FOR UNIT 2 AND | | UNDER 10 CFR 50.72(b)(2)(i) FOR UNIT 1. | | | | THE LICENSEE HAS ENTERED THE LIMITING CONDITIONS FOR OPERATION (LCO) FOR A | | LOSS OF "A"-TRAIN STANDBY EMERGENCY POWER FOR UNIT 2 AND THE TECHNICAL | | SPECIFICATIONS ACTION STATEMENTS FOR UNIT 1. THE EDGs ARE AVAILABLE AND | | LINED UP TO SUPPLY ELECTRICAL POWER TO THE BUSES IF NEEDED. THE LICENSEE | | IS REVIEWING THE POSSIBILITY OF ENTERING SPECIFIC EQUIPMENT LCOs IN ORDER | | TO CLEAR THE STANDBY EMERGENCY POWER LCO. THE MOST LIMITING LCO HAS A | | 7-DAY ACTION STATEMENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32866 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 09/03/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:14 [ET]| |RX TYPE: [1] CE |EVENT DATE: 09/03/97 | +------------------------------------------------+EVENT TIME: 13:25[EDT]| |NRC NOTIFIED BY: VINCENT |LAST UPDATE DATE: 09/03/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM CREED 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 +------------------------------------------------------------------------------+ | FAILURE TO TEST HYDROGEN RECOMBINERS FOR BORON CONCENTRATIONS ABOVE 2,500 | | ppm | | | | DURING A CONSERVATIVE ASSESSMENT OF BORON CONCENTRATION LIMITS IN VARIOUS | | TANKS, IT WAS DISCOVERED THAT THE POST LOSS OF COOLANT ACCIDENT BORON | | CONCENTRATION IN THE CONTAINMENT SUMP AND CONTAINMENT SPRAY COULD BE AS | | HIGH AS 2,937 ppm. THE ENVIRONMENTAL QUALIFICATION TEST OF THE HYDROGEN | | RECOMBINERS, HOWEVER, WAS PERFORMED AT ONLY 2,500 ppm. CONTAINMENT SPRAY | | BORON CONCENTRATION IS NOT A CRITICAL PARAMETER THAT SHOULD IMPAIR HYDROGEN | | RECOMBINER OPERABILITY; SO THIS DISCREPANCY APPEARS TO ONLY BE A | | DOCUMENTATION ISSUE. THE HYDROGEN RECOMBINERS ARE JUDGED CAPABLE OF | | WITHSTANDING ANY BORON CONCENTRATIONS THAT COULD BE EXPERIENCED. HYDROGEN | | RECOMBINERS REMAIN OPERABLE BECAUSE ACTUAL BORON CONCENTRATIONS NOW PRESENT | | IN THE TANKS THAT DUMP INTO THE SUMP WOULD NOT RAISE CONCENTRATION ABOVE | | 2,500 ppm. IN ADDITION, EVEN IF TANK CONCENTRATIONS WERE AT THEIR | | TECHNICAL SPECIFICATION LIMITS, THE LICENSEE DOES NOT BELIEVE THE HYDROGEN | | RECOMBINER FUNCTION WOULD BE DEGRADED. ANALYSES ARE IN PROGRESS TO | | DOCUMENT THAT THE RECOMBINER QUALIFICATION TEST REMAINS VALID UP TO MAXIMUM | | SPRAY BORON CONCENTRATION THAT COULD BE EXPERIENCED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32867 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MACON OFFICE OF GEOSCIENCES |NOTIFICATION DATE: 09/03/97 | | CITY: MACON REGION: 2 |NOTIFICATION TIME: 16:10 [ET]| | COUNTY: STATE: GA |EVENT DATE: 09/01/97 | |LICENSE#: GA 1211-1 AGREEMENT: Y |EVENT TIME: 10:15[EDT]| | DOCKET: |LAST UPDATE DATE: 09/03/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL RANKIN RDO | | |ROBERT PIERSON, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: THOMAS HILL | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE GEORGIA DEPARTMENT OF NATURAL RESOURCES REPORTED THAT A TROXLER | | MOISTURE DENSITY GAUGE WAS STOLEN FROM THE BACK OF A PICK UP TRUCK AND | | RECOVERED A FEW DAYS LATER. | | | | AT APPROXIMATELY 1015 EDT ON SEPTEMBER 1, 1997, TECHNICIANS IN THE MACON | | OFFICE OF GEOSCIENCES REPORTED TO THE CORPORATE RADIATION SAFETY OFFICER | | (CRSO) THAT A TROXLER 3440 MOISTURE DENSITY GAUGE [9 mCi OF CESIUM-137 AND | | 44 mCi OF AMERICIUM-241/BERYLLIUM] WAS STOLEN FROM THE BACK OF A PICK UP | | TRUCK. THE CHAIN SECURING THE GAUGE TO THE TRUCK HAD BEEN CUT. AT | | APPROXIMATELY 1115 EDT, THE CRSO NOTIFIED THE RADIOACTIVE MATERIALS PROGRAM | | OF THE THEFT. AT 1400 HOURS, THE CRSO FILED A POLICE REPORT INDICATING | | THAT THE TROXLER 3440 MOISTURE DENSITY GAUGE SERIAL NUMBER 24341 WAS STOLEN | | FROM THE BACK OF A PICK UP TRUCK ON SEPTEMBER 1, 1997. CRSO INDICATED THAT | | HE ALSO NOTIFIED TROXLER ELECTRONICS OF THIS EVENT. AT NOON ON SEPTEMBER | | 3, 1997, THE CRSO NOTIFIED THE RADIOACTIVE MATERIALS PROGRAM THAT THE GAUGE | | WAS FOUND AND THAT HE WOULD FOLLOW-UP WITH A WRITTEN REPORT TO THE STATE OF | | GEORGIA. THE STATE OF GEORGIA EVENT NUMBER ASSIGNED TO THIS EVENT IS | | GA-97-18. | | | | (REFER TO THE HOO LOG BOOK FOR CONTACT TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+