U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/12/97 - 11/13/97 ** EVENT NUMBERS ** 32806 32890 33251 33252 33253 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32806 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/22/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 19:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/22/97 | +------------------------------------------------+EVENT TIME: 18:56[EDT]| |NRC NOTIFIED BY: CHERBA |LAST UPDATE DATE: 11/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |ACNC 50.72(b)(1)(ii)(C) COND OUTSIDE EOPS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INSTRUMENTATION INDICATIONS USED TO DETERMINE WHEN RWST TO CONTAINMENT | | SWITCH OVER IS REQUIRED MAY NOT HAVE BEEN CORRECT TO PREVENT VORTEXING IN | | THE CONTAINMENT RECIRCULATION SUMP. | | | | DURING THE EVALUATION OF A PROPOSED PROCEDURE CHANGE THAT AFFECTS SWITCH | | OVER FROM THE RWST TO THE CONTAINMENT SUMP DURING A LOCA, IT WAS DETERMINED | | THAT THE INSTRUMENTATION INDICATIONS USED TO DETERMINE WHEN THE SWITCH OVER | | IS REQUIRED MAY NOT HAVE BEEN CORRECT TO PREVENT VORTEXING IN THE | | CONTAINMENT RECIRCULATION SUMP. | | | | TO ADDRESS THIS SITUATION, PROCEDURES ASSOCIATED WITH THE SWITCH OVER (ON | | BOTH UNITS) HAVE BEEN CONSERVATIVELY CHANGED TO ACCOMMODATE THE RELATED | | INSTRUMENT INACCURACIES. THESE CHANGES ASSURE ADEQUATE RWST WATER IS IN | | CONTAINMENT BEFORE SWITCH OVER TO ELIMINATE CONCERNS THAT VORTEXING WOULD | | OCCUR IN THE CONTAINMENT SUMP AFTER SWITCH OVER. | | | | THE PROBLEM IS THAT THE RWST WATER LEVEL INDICATORS ARE CONNECTED TO THE | | SUCTION LINE THAT GOES TO THE RHR PUMPS. DUE TO THE FLOW IN THESE LINES, | | THE INDICATED WATER LEVEL AT WHICH THE SWITCH OVER WOULD BE INITIATED WOULD | | BE LESS THAN THE ACTUAL WATER LEVEL OF THE RWST (THE LICENSEE WOULD BE | | PUTTING LESS WATER INTO THE CONTAINMENT THAN EXPECTED). ALSO, THE LICENSEE | | SAID THAT THEY HAD SOME INACCURACIES ASSOCIATED WITH THEIR CONTAINMENT SUMP | | INSTRUMENTATION. THE LICENSEE ADJUSTED THE CONTAINMENT SUMP INDICATION TO | | ASSURE THAT THEY HAVE AN ADEQUATE VOLUME IN THE CONTAINMENT TO PREVENT | | VORTEXING. THE LICENSEE RELIES UPON TWO INDICATIONS FOR SWITCH OVER; RWST | | WATER LEVEL AND CONTAINMENT WATER LEVEL. | | | | THIS SITUATION WAS DETERMINED TO BE POTENTIALLY REPORTABLE AFTER DISCUSSION | | WITH LICENSING PERSONNEL. THE SITUATION WILL BE FURTHER REEVALUATED AND | | UPDATES MAY BE FORTHCOMING. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 0835EST ON 11/12/97 FROM MARK ACKERMAN TO S.SANDIN * * * | | | | SEE TEXT IN EVENT #32890 UPDATE 0835EST. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32890 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/08/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 20:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/97 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: SAM PARTIN/MARY DePUYDT |LAST UPDATE DATE: 11/12/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CECIL THOMAS, NRR EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |SULLIVAN FEMA | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |RICHARD BARRETT IRD | |NLCO TECH SPEC LCO A/S | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 57 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 85 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UE DECLARED & TS REQD S/D ON BOTH UNITS DUE TO INOPERABLE CONTAINMENTS - | | | | AS A RESULT OF ISSUES RAISED DURING THE ONGOING ARCHITECT/ENGINEER DESIGN | | INSPECTION, THE LICENSEE WAS REVIEWING THE DESIGN ASPECTS OF THE | | CONTAINMENTS (BOTH UNITS HAVE SIMILAR CONTAINMENTS). AFTER CONSULTING WITH | | THE NUCLEAR STEAM SUPPLY SYSTEM SUPPLIER (WESTINGHOUSE) THE LICENSEE | | DETERMINED THAT CONCERNS EXISTED ABOUT WHETHER ADEQUATE COMMUNICATION (FLOW | | PATHS) EXISTS BETWEEN THE ACTIVE AND INACTIVE PORTIONS OF THE CONTAINMENT | | SUMP. | | | | DURING CERTAIN SCENARIOS, THE VOLUME OF WATER FLOW BACK TO THE CONTAINMENT | | RECIRCULATION SUMP MAY NOT BE ADEQUATE TO SUPPORT LONG-TERM EMERGENCY CORE | | COOLING (ECC) SYSTEMS (RHR SYSTEM, SAFETY INJECTION SYSTEM, CHARGING | | SYSTEM) OR CONTAINMENT SPRAY PUMP OPERATION DURING THE RECIRCULATION PHASE | | OF A LARGE OR SMALL BREAK LOCA. THE CONTAINMENT DRAINAGE SYSTEM IS | | DESIGNED TO ENSURE THAT WATER ENTERING THE CONTAINMENT FROM THE BREACH IN | | THE REACTOR COOLANT SYSTEM, ECC SYSTEMS INJECTION, AND ICE CONDENSER MELT | | FLOWS BACK INTO THE CONTAINMENT RECIRCULATION SUMP VIA DRAINS. LICENSEE | | ANALYSIS WAS UNABLE TO CONFIRM THAT SUFFICIENT COMMUNICATION EXISTED | | BETWEEN INACTIVE AND ACTIVE VOLUMES OF THE CONTAINMENT TO ENSURE ADEQUATE | | DRAINAGE TO THE RECIRCULATION SUMP. WITHOUT ADEQUATE DRAINAGE INTO THE | | SUMP, A LOW SUMP LEVEL WILL RESULT, WHICH JEOPARDIZES LONG TERM OPERATION | | OF THE ECC SYSTEMS AND CONTAINMENT SPRAY PUMPS DUE TO VORTEXING AND AIR | | ENTRAINMENT. | | | | AS A CONSERVATIVE MEASURE BECAUSE OF THESE CONCERNS, THE LICENSEE DECLARED | | BOTH TRAINS OF THE ECC SYSTEMS AND THE CONTAINMENT SPRAY SYSTEM INOPERABLE | | FOR BOTH UNITS AND ENTERED TECH SPEC LCO A/S 3.0.3 TO SHUT DOWN BOTH UNITS. | | THE LICENSEE COMMENCED SHUTTING UNIT 1 DOWN FROM 100% POWER AT 1655 AND | | UNIT 2 DOWN FROM 100% POWER AT 1728. | | | | AT 2000, THE LICENSEE DECLARED AN UNUSUAL EVENT ON BOTH UNITS DUE TO THE | | POTENTIAL LOSS OF CONTAINMENT BARRIER ON BOTH UNITS. | | | | THE LICENSEE PLANS TO PERFORM FURTHER ANALYSIS TO DETERMINE THE EXTENT OF | | THE EXISTING COMMUNICATION BETWEEN THE PORTIONS OF THE SUMPS AND WHETHER | | PLANT MODIFICATIONS WILL BE NECESSARY. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE DECLARATION OF THE UNUSUAL EVENT. | | | | ***UPDATE @ 0311 EDT ON 09/10/97 BY TILLY TAKEN BY MACKINNON*** | | | | THE UNUSUAL EVENT WAS TERMINATED AND EXITED AT 0303 EDT WHEN UNIT 1 ENTERED | | MODE 5 (COLD SHUTDOWN). UNIT 2 ENTERED MODE 5 AT 0015 EDT (COLD SHUTDOWN). | | | | THE R3DO (RING), NRR EO (BATEMAN), AND FEMA (RISHE) WERE NOTIFIED BY THE | | NRC OPERATIONS CENTER. THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS | | UPDATE BY THE LICENSEE. | | | | * * * UPDATE 0835EST ON 11/12/97 FROM MARK ACKERMAN TO S.SANDIN * * * | | | | THE LICENSEE IS PROVIDING THE FOLLOWING INFORMATION AS AN UPDATE TO THE | | SAFETY SIGNIFICANCE OF EVENT REPORTS #32806 AND #32890: | | | | "CALCULATIONS HAVE BEEN COMPLETED FOR UNIT 1, CYCLE 16 AND UNIT 2, CYCLE 11 | | (THE OPERATING CYCLES AT THE TIME OF THE SHUTDOWN) TO ASSESS THE SAFETY | | SIGNIFICANCE OF THE EMERGENCY CORE COOLING SYSTEM PERFORMANCE DESCRIBED IN | | THE PREVIOUS REPORTS. THIS ASSESSMENT EVALUATED THE ADEQUACY OF THE WATER | | LEVEL IN THE CONTAINMENT RECIRCULATION SUMP TO SUPPORT OPERATION OF THE RHR | | AND CTS PUMPS DURING THE RECIRCULATION PHASE OF A POSTULATED LOSS OF | | COOLANT ACCIDENT. IN ADDITION, ACCIDENT ANALYSIS CRITERIA REGARDING COLD | | AND HOT LEG RECRITICALITY AND CONTAINMENT OVERPRESSURIZATION WERE | | CONSIDERED. THESE CALCULATIONS HAVE CONSIDERED A SPECTRUM OF BREAK SIZES | | RANGING FROM A .5 INCH DIAMETER BREAK TO A DOUBLE ENDED GUILLOTINE BREAK, | | THE USABLE WATER VOLUME CONTAINED IN THE REFUELING WATER STORAGE TANK | | (RWST), THE WATER AVAILABLE FROM ICE THAT MELTS DURING THE PROGRESSION OF | | THE ACCIDENT, THE DIVERSION OF SPRAY FLOW INTO THE INACTIVE SUMP, THE BREAK | | FLOW BEING DIRECTED INTO THE ACTIVE SUMP OR THE REACTOR CAVITY, AS | | APPROPRIATE, AND THE IMPACT OF PENETRATIONS IN THE CRANE WALL AND | | BIOLOGICAL SHIELD WHICH ALLOW THE SUMP TO COMMUNICATE WITH ADJACENT | | DEPARTMENTS. THE ESTIMATE OF THE USABLE RWST WATER HAS CONSIDERED ERRORS | | IN THE INSTRUMENTATION PROVIDING THE INDICATION OF RWST WATER LEVEL, | | INCLUDING THE ERRORS RESULTING FROM FLOW PAST THE INSTRUMENTATION TAP. THE | | ICE MASS PRESENT IN THE ICE CONDENSER WAS DETERMINED FROM ICE SURVEILLANCE | | RECORDS. | | | | "THE LIMITING CASE FOR SUMP INVENTORY HAS BEEN DETERMINED TO BE A BREAK OF | | A .61 INCH DIAMETER INSTRUMENT LINE INSIDE THE REACTOR CAVITY. BASED ON | | THE ASSUMPTION THAT THERE IS NO COMMUNICATION BETWEEN THE REACTOR CAVITY | | AND THE RECIRCULATION SUMP UNTIL WATER SPILLS OVER THE WALL SEPARATING THE | | TWO REGIONS, THE MINIMUM WATER LEVEL IN THE RECIRCULATION SUMP WOULD HAVE | | BEEN AT THE 602.2 FOOT LEVEL. FOR THIS BREAK, THE LOCA ANALYSES SHOW THAT | | THE REQUIRED SUCTION FLOW FROM THE SUMP IS NEVER GREATER THAN 700 GPM, AND | | THE MINIMUM REQUIRED WATER LEVEL AT THIS FLOW IS WELL BELOW 602.2 FEET. FOR | | THE OTHER BREAKS CONSIDERED, THE WATER LEVEL EXCEEDS THE MINIMUM REQUIRED | | LEVEL OF 602 FEET 10 INCHES BASED ON RUNOUT OPERATION OF THE PUMPS. | | | | "THE ANALYSES HAVE DEMONSTRATED THAT FOR ALL BREAK SIZES AND LOCATIONS, | | THERE WILL BE SUFFICIENT WATER IN THE SUMP TO PREVENT VORTEX FORMATION WHEN | | THE ECCS AND CTS PUMPS ARE OPERATED IN THE RECIRCULATION MODE. IN | | ADDITION, THESE ANALYSES FOUND THAT RECRITICALITY AND CONTAINMENT | | OVERPRESSURIZATION CRITERIA CONTINUED TO BE SATISFIED. | | | | "ANALYSES FOR OTHER CYCLES IS PRESENTLY IN PROGRESS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(LEACH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33251 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/12/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 08:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/11/97 | +------------------------------------------------+EVENT TIME: 16:24[CDT]| |NRC NOTIFIED BY: KEN TAPLETT |LAST UPDATE DATE: 11/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT. | | | | "SOUTH TEXAS PROJECT UNIT 1 AND UNIT 2 ARE MAKING THE FOLLOWING | | NOTIFICATION PER NPF 076 AND NPF 080 SECTION 2G: | | | | "EVALUATION OF THE TESTING METHODOLOGY USING A ROTAMETER FLOW MEASUREMENT | | INSTRUMENT FOR MEASURING CONTAINMENT LEAKAGE RATE DETERMINED THAT TEST | | RESULTS COULD HAVE BEEN NONCONSERVATIVE. SPECIFICALLY, THE METHODOLOGY OF | | CALIBRATING THE ROTAMETER WAS NOT CORRECTLY FACTORED INTO THE CALCULATION | | OF THE FIELD TESTING RESULTS. THEREFORE, THE POTENTIAL EXISTED FOR TECH | | SPEC SURVEILLANCE LEAKAGE LIMITS NOT BEING MET WHEN LEAKAGE TESTING HAD | | BEEN CONDUCTED. | | | | "CURRENTLY ALL PENETRATIONS ARE OPERABLE BECAUSE SUFFICIENT MARGIN EXISTS | | WHEN APPLYING AN APPROPRIATE CORRECTION FACTOR TO TEST RESULTS OR RETESTING | | USING REVISED METHODOLOGY VERIFIED LEAKAGE RATES ARE WITHIN TECH SPEC | | LIMITS. | | | | "SOUTH TEXAS PROJECT IS CURRENTLY IN COMPLIANCE. | | | | "FURTHER EVALUATION IS ONGOING." | | | | THE LICENSEE IDENTIFIED ON 10/30 THAT THE ROTAMETERS WERE CALIBRATED AT | | ATMOSPHERIC PRESSURE WHICH DID NOT TAKE INTO ACCOUNT THE CONTAINMENT | | BACKPRESSURE DURING A DESIGN BASIS ACCIDENT. THE LICENSEE DETERMINED THAT | | WITH UNCERTAINTIES A CORRECTION FACTOR OF TWO TIMES THE VALUE MEASURED IN | | THE FIELD IS REQUIRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 11/12/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/12/97 | +------------------------------------------------+EVENT TIME: 10:30[EDT]| |NRC NOTIFIED BY: BILL WEBSTER |LAST UPDATE DATE: 11/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES OGLE 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ATWS BLOCKING SETPOINT SET NONCONSERVATIVELY | | | | "THE INTERLOCK SETPOINT FOR ATWS MITIGATING SYSTEM ACTUATION CIRCUITRY | | (AMSAC) IS SET FOR 37 PERCENT TURBINE FIRST STAGE IMPULSE PRESSURE. IT HAS | | BEEN DETERMINED THAT THIS SETPOINT CORRESPONDS TO GREATER THAN 40 PERCENT | | REACTOR THERMAL POWER WHICH IS OUTSIDE THE DESIGN BASIS. BOTH UNITS ARE | | CURRENTLY OPERATING AT FULL POWER, THEREFORE AMSAC IS FULLY OPERABLE. | | CORRECTIVE ACTIONS ARE BEING REVIEWED TO ENSURE AMSAC IS OPERABLE AT 40 | | PERCENT THERMAL REACTOR POWER IN ACCORDANCE WITH THE DESIGN BASIS. | | | | "THIS EVENT IS BEING REPORTED IN ACCORDANCE WITH 10 CFR 50.72(b)(1)(ii)B." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE RELATED EVENTS #33132, 33205, 33217, 33225 AND 33235. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33253 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 11/12/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/12/97 | +------------------------------------------------+EVENT TIME: 16:46[EDT]| |NRC NOTIFIED BY: FERNSLER |LAST UPDATE DATE: 11/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESS RELEASE MADE TO THE NEWS MEDIA THAT FIXED CONTAMINATION WAS FOUND ON | | A BOOTIE THAT AN EMPLOYEE WAS WEARING DURING THE PERFORMANCE OF THEIR | | DRILL. | | | | | | PP&L MADE A PRESS RELEASE ON 11/12/97 AT 1646 EST WHICH IS SUBSTANTIALLY AS | | FOLLOWS: | | | | | | "A TRACE AMOUNT OF RADIOACTIVE CONTAMINATION WAS DETECTED IN THE CLOTHING | | WORN BY AN EMPLOYEE OF THE SUSQUEHANNA NUCLEAR PLANT DURING A ROUTINE DRILL | | ON 11/12/97. | | | | "THE CONTAMINATION WAS FOUND DURING A CHECK PERFORMED BY PP&L PERSONNEL AT | | BERWICK HOSPITAL. ONE OF THE EMPLOYEE'S PROTECTIVE 'BOOTIES' WAS FOUND TO | | HAVE TRACE AMOUNTS OF 'FIXED' CONTAMINATION (LICENSEE DID NOT KNOW WHAT THE | | RADIOACTIVE CONTAMINATION WAS)- WHICH DOES NOT RUB OFF OR TRANSFER TO | | PEOPLE. | | | | "THERE WAS NO INJURIES, AND NO PLANT EMPLOYEES, EMERGENCY WORKERS OR | | MEMBERS OF THE PUBLIC WERE CONTAMINATED. THE BOOTIE WAS RETURNED TO THE | | PLANT FOR PROCESSING. | | | | "EVEN THOUGH THIS IS AN EXTREMELY SMALL AMOUNT OF FIXED CONTAMINATION WHICH | | IN NO WAY AFFECTED ANYONE INVOLVED, PP&L WILL INVESTIGATE AND MAKE ANY | | NECESSARY CHANGES IN PROCEDURES TO ENSURE THAT PROTECTIVE CLOTHING WITH | | FIXED CONTAMINATION DOES NOT INADVERTENTLY LEAVE THE PLANT SITE. | | | | "THE BOOTIE WAS SURVEYED AND WAS FOUND TO HAVE A CONTAMINATION LEVEL OF 500 | | CPM (DID NOT KNOW WHAT TYPE OF DETECTOR AND FRISKER WERE USED), CORRECTED. | | ALL APPAREL WORN BY THE INDIVIDUALS WHO WERE TRANSPORTED OFF-SITE AS PART | | OF THE DRILL WAS SURVEYED AND NO OTHER CONTAMINATION WAS IDENTIFIED." | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+