U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/22/98 - 04/23/98 ** EVENT NUMBERS ** 33965 34079 34117 34118 34119 34120 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33965 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/26/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 08:15 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/26/98 | +------------------------------------------------+EVENT TIME: 01:41[PST]| |NRC NOTIFIED BY: ROBERT JOHNSON |LAST UPDATE DATE: 04/22/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION DUE TO TURBINE LOW STEAM | | SUPPLY PRESSURE IN LIEU OF STEAM LINE HIGH FLOW (DURING TESTING) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 0141 PST, DURING PERFORMANCE OF SURVEILLANCE TESTING OF THE REACTOR | | CORE ISOLATION COOLING (RCIC) SYSTEM STEAM LINE [HIGH]-FLOW ISOLATION | | INSTRUMENTATION, AN ISOLATION SIGNAL WAS RECEIVED FOR RCIC TURBINE LOW | | STEAM SUPPLY PRESSURE. THIS RESULTED IN AUTOMATIC CLOSURE OF RCIC STEAM | | SUPPLY OUTBOARD ISOLATION VALVE RCIC-V-8. ALTHOUGH THE RCIC TURBINE LOW | | STEAM SUPPLY PRESSURE WAS DOCUMENTED AS AN EXPECTED CONDITION IN THE | | GOVERNING SURVEILLANCE TEST PROCEDURE, THE RCIC STEAM LINE [HIGH]-FLOW | | ISOLATION INSTRUMENTATION WAS EXPECTED TO CAUSE THE ISOLATION." | | | | "THIS IS BEING REPORTED AS A 4-[HOUR] NON-EMERGENCY 10 CFR 50.72(b)(2)(ii) | | [ENGINEERED SAFETY FEATURE (ESF)] ACTUATION. [THE UNIT (WNP-2)] WAS | | OPERATING AT 100% POWER WITH THE RCIC SYSTEM REMOVED FROM SERVICE FOR A | | PLANNED SYSTEM MAINTENANCE OUTAGE AT THE TIME THE ISOLATION OCCURRED. THIS | | EVENT WAS DETERMINED TO BE REPORTABLE AT 0351 PST. THE SURVEILLANCE | | PROCEDURE AND WNP-2 DESIGN BASIS DOCUMENTATION ARE [CURRENTLY] BEING | | REVIEWED TO CONFIRM THE REPORTABILITY OF THIS EVENT AS AN ESF ACTUATION IN | | RESPONSE TO A VALID SIGNAL." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION 1130 4/22/98 FROM JOHN ARBUCKLE TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE RCIC LOW STEAM SUPPLY | | PRESSURE ISOLATION IS NOT AN ENGINEERED SAFETY FEATURE FUNCTION. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R4DO (COLLINS). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34079 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/16/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 00:36 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/15/98 | +------------------------------------------------+EVENT TIME: 21:40[EDT]| |NRC NOTIFIED BY: DONALD E. ROLAND |LAST UPDATE DATE: 04/22/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY DOERFLEIN 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 +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) TURBINE EXHAUST OUTBOARD VACUUM | | BREAKER ISOLATION VALVE CLOSED. | | | | DURING THE RESTORATION FROM A LOCAL LEAK RATE TEST ON AN INSTRUMENT | | PENETRATION OF THE PRIMARY CONTAINMENT, THE HPCI TURBINE EXHAUST OUTBOARD | | VACUUM BREAKER ISOLATION VALVE CLOSED. NO VALID ISOLATION SIGNALS OCCURRED | | NOR WAS THERE ANY PLANT CONDITION WHICH WOULD HAVE REQUIRED A CONTAINMENT | | ISOLATION. HPCI WAS OUT OF SERVICE AND PRIMARY CONTAINMENT RELAXED AT THE | | TIME OF THE OCCURRENCE. THE UNIT IS CURRENTLY IN A REFUELING OUTAGE. THE | | CAUSE APPEARS TO BE THE FAILURE OF TECHNICIANS TO COMPLETELY DEPRESSURIZE | | THE TEST VOLUME PRIOR TO ITS RE-ALIGNMENT FOR ADDITIONAL TESTING. THE | | RE-ALIGNMENT OF THE PRESSURIZED VOLUME ACTUATED A PRESSURE SWITCH ON THE | | COMMON HEADER CAUSING THE ISOLATION OF THE VALVE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * RETRACTION 1111 4/22/1998 FROM ROBERT PEAL TAKEN BY STRANSKY * * * | | | | AFTER FURTHER REVIEW, THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE | | LICENSEE STATED THAT THE RETRACTION IS BASED UPON: (1) THE ISOLATION VALVE | | CLOSURE WAS AN INVALID ESF ACTUATION, (2) BOTH THE HPCI SYSTEM AND THE | | PRIMARY CONTAINMENT WERE PROPERLY REMOVED FROM SERVICE IN ACCORDANCE WITH | | PLANT PROCEDURES, AND (3) THE ISOLATION WAS NOT REQUIRED AND DID NOT | | INTERFERE WITH ANY SYSTEM OPERATION. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. NOTIFIED R1DO (ROGGE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34117 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: APPLIED RADIANT ENERGY CORP |NOTIFICATION DATE: 04/22/98 | | CITY: LYNCHBURG REGION: 2 |NOTIFICATION TIME: 10:08 [ET]| | COUNTY: CAMPBELL STATE: VA |EVENT DATE: 04/21/98 | |LICENSE#: 45-11496-01 AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/22/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WALT ROGERS RDO | | |DON COOL, NMSS EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: JAMES MYRON | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |MAAC 36.83(a)(3) DAMAGED SOURCE RACKS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A COBALT-60 SOURCE PENCIL WAS FOUND IN THE BOTTOM OF AN IRRADIATOR POOL. | | | | APPLIED RADIANT ENERGY CORPORATION HAS AN UNDERWATER IRRADIATOR WITH SOME | | CO-60 SOURCES STORED IN IT BENEATH THE FLOOR OF THE UNDERWATER POOL. THE | | LICENSEE WAS IN THE COURSE OF MAKING PREPARATIONS FOR EXAMINING THE CO-60 | | SOURCES ON 4/21 WHEN THEY FOUND A CO-60 SOURCE 22 FEET UNDERWATER ON THE | | FLOOR UNDERNEATH THE TRACK THAT THE IRRADIATOR RACK TRAVERSES. (THERE | | SHOULD NOT HAVE BEEN COBALT-60 SOURCE LYING ON THE BOTTOM OF THE IRRADIATOR | | POOL.) A CO-60 SOURCE PENCIL HAD DROPPED OUT OF ONE OF THE SOURCE | | PRODUCTION RACKS AND HAD FALLEN A COUPLE OF FEET TO THE BOTTOM OF THE | | IRRADIATOR. THE LICENSEE'S BEST GUESS ESTIMATE WHEN THE CO-60 SOURCE HAD | | FALLEN OUT OF ITS PRODUCTION RACK IS BETWEEN JANUARY 1998 AND APRIL 21, | | 1998. THE LICENSEE SAID THAT THE CO-60 SOURCE PENCIL STRENGTH IS PROBABLY | | LESS THAN 200 CURIES. SINCE THE CO-60 SOURCE PENCIL IS BENEATH 22 FEET OF | | WATER, NOBODY WAS ENDANGERED IN RECEIVING AN UNMONITORED RADIATION DOSE | | FROM THE DROPPED SOURCE. | | | | CORRECTIVE ACTIONS: 1) SINCE THE CO-60 SOURCE IS CONSIDERED A WEAK SOURCE | | AND IT WILL NOT BE NEEDED FOR PRODUCTION, IT WILL BE PLACED 13 FEET BELOW | | THE FLOOR OF THE POOL IN A STORAGE BASKET; AND 2) THE LICENSEE WILL REPAIR | | THE SOURCE RACK SO THAT NO FURTHER SOURCES CAN FALL FROM THE RACK. THE RACK | | HAS A SHROUD (LIKE A BOOK COVER) AROUND IT, AND THE ENDS OF THE SHROUD ARE | | HELD TOGETHER WITH PINS. SOME OF THE PINS WERE FOUND MISSING, AND THIS IS | | WHY THE CO-60 SOURCE PENCIL HAD FALLEN OUT OF THE PRODUCTION RACK. THE PINS | | WILL BE REPLACED. | | | | NRC REGION 2 (WADE LOO) WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34118 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/22/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 11:55 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/22/98 | +------------------------------------------------+EVENT TIME: 11:15[EDT]| |NRC NOTIFIED BY: JOHN THOMAS |LAST UPDATE DATE: 04/22/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - INADEQUATE DESIGN AND INSTALLATION OF BACKUP NITROGEN SUPPLY FOR PORVs - | | | | UNIT 1 IS IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE. | | | | WHILE PERFORMING A WALKDOWN OF THE UNIT 1 INSTALLATION OF THE BACKUP | | NITROGEN SUPPLY FOR POWER OPERATED RELIEF VALVE (PORV) #PCV-456, IN | | ACCORDANCE WITH THE CORRECTIVE ACTION DELINEATED IN LER #I-98-011-00, | | "PORV TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS," THE LICENSEE | | DISCOVERED THAT THE ORIGINAL DESIGN AND INSTALLATION OF THE BACKUP NITROGEN | | SUPPLIES FOR PORVs #PCV-455C&D WERE INADEQUATE TO MEET SEISMIC TRANSIENTS | | AND DID NOT TAKE INTO ACCOUNT THERMAL EXPANSION AND CONTRACTION SYSTEM | | CONSIDERATIONS ASSOCIATED WITH PORV ACTUATION AT POWER OR DURING MODE 4. | | | | SPECIFICALLY, THE LICENSEE DISCOVERED THE FOLLOWING: 1) THE INSTALLATION OF | | THE EXISTING TUBING TO THE AIR REGULATORS ASSOCIATED WITH PORVs #PCV-455C&D | | WAS TOO RIGID IN THAT IT DID NOT ALLOW FOR SUFFICIENT THERMAL EXPANSION AND | | CONTRACTION AND SEISMIC MOVEMENT ASSOCIATED WITH STROKING THE PORV UNDER | | ALL DESIGN CONDITIONS; 2) THE MOUNTING PLATE FOR THE SOLENOID-OPERATED | | VALVES (SOV) ON THE PORVs WAS INADEQUATELY DESIGNED; 3) THE SOVs WERE NOT | | SPECIFICALLY QUALIFIED FOR EXCITATION RESULTING FROM PORV DISCHARGE; 4) THE | | EXISTING NITROGEN TUBING WAS FIELD ROUTED AND REQUIRES A LEVEL OF REWORK TO | | CONFIRM SEISMIC ADEQUACY; AND 5) THE PORV ACTUATORS WERE NOT ADEQUATELY | | PROTECTED FROM A FAILURE OF THE INSTRUMENT PRESSURE REGULATORS IN THAT THE | | PORVs COULD FAIL IN A NON-CONSERVATIVE MANNER BY OPENING IN A FASTER TIME | | THAN WHAT WAS EVALUATED IN THE SYSTEM TRANSIENT PIPE LOADING ANALYSIS WHEN | | THE REACTOR COOLANT SYSTEM IS AT OPERATING TEMPERATURE AND PRESSURE. | | | | AS RESPONDED TO IN NRC GENERIC LETTER 90-06 AND AS IDENTIFIED IN THE | | UPDATED FINAL SAFETY ANALYSIS REPORT SECTION 7.7.1.5, A SEISMIC SAFETY | | GRADE BACKUP NITROGEN SUPPLY WAS TO BE DESIGNED AND INSTALLED TO ENSURE | | PORV ACTUATION UNDER VARYING OPERATING CONDITIONS. ACTUATION OF THE | | PORV UNDER VARYING PLANT CONDITIONS WILL ENSURE THE MITIGATION OF LOW | | TEMPERATURE OVERPRESSURE PROTECTION AND STEAM GENERATOR TUBE RUPTURE. | | THE NITROGEN BACKUP SUPPLY DESIGN AND INSTALLATION FAILS TO MEET SEISMIC | | AND THERMAL LOADINGS DURING PORV ACTUATION AT POWER AND DURING MODE 4. | | THIS IS A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT AND AN UNANALYZED | | CONDITION THAT COMPROMISES PLANT SAFETY. | | | | THE LICENSEE INITIATED PLANT CONDITION REPORTS #980596 AND #980740 TO | | ADDRESS THESE CONCERNS. THE LICENSEE REVISED DESIGN CHANGE PACKAGE | | #DCP-2313 TO INCLUDE ADDITIONAL MODIFICATIONS TO ADDRESS THE CONDITIONS | | IDENTIFIED. THE LICENSEE PLANS TO COMPLETE ALL ASSOCIATED PLANT | | MODIFICATIONS AND TESTING PRIOR TO UNIT 1 ENTERING MODE 4. | | | | THE LICENSEE DETERMINED THAT THIS CONDITION DOES NOT APPLY TO UNIT 2. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34119 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SIEMENS POWER CORP-NUCLEAR DIVISION |NOTIFICATION DATE: 04/22/98 | | CITY: RICHLAND REGION: 4 |NOTIFICATION TIME: 12:40 [ET]| | COUNTY: BENTON STATE: WA |EVENT DATE: 04/21/98 | |LICENSE#: SNM-1227 AGREEMENT: Y |EVENT TIME: 12:00[PDT]| | DOCKET: |LAST UPDATE DATE: 04/22/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ELMO COLLINS, R4 RDO | | | | +------------------------------------------------+JIM GAVULA, R3 RDO | |NRC NOTIFIED BY: DON CURET |VERN HODGE NRR | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - NONCONSERVATIVE PREDICTION OF MONITORED CORE MCPR - | | | | SIEMENS POWER CORPORATION (SPC) PERSONNEL DETERMINED THAT ADDITIVE | | CONSTANTS USED IN THE MINIMUM CRITICAL POWER RATIO (MCPR) DETERMINATION FOR | | SIEMENS ATRIUM-9B FUEL BY THE CORE MONITORING SYSTEM WERE FOUND TO BE | | NON-CONSERVATIVE (UP TO 7.6% BASED ON THE ORIGINAL ADDITIVE CONSTANTS). IN | | ADDITION, SPC PERSONNEL DETERMINED THAT THE UNCERTAINLY IN THE ADDITIVE | | CONSTANT FOR THIS FUEL DESIGN WAS LARGER THAN PREVIOUSLY ESTIMATED. THE | | REVISED UNCERTAINTY HAS THE POTENTIAL TO AFFECT THE MCPR SAFETY LIMIT. | | | | SPC PERSONNEL NOTIFIED ALL SPC CUSTOMERS WITH ATRIUM-9B LEAD TEST | | ASSEMBLIES OR RELOAD QUANTITIES OF THE FUEL OF THE POSSIBLE NONCONSERVATIVE | | PREDICTION OF THE MONITORED MCPR AT CONDITIONS WHERE A SEVERELY UP-SKEWED | | AXIAL POWER SHAPE COULD OCCUR. | | | | PLANTS AFFECTED ARE DRESDEN UNIT 3 (CYCLE 15), QUAD CITIES UNIT 2 | | (CYCLE 15), AND KUOSHENG UNITS 1 AND 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34120 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 04/22/98 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/98 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: RICK OREAR |LAST UPDATE DATE: 04/22/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER RODGERS RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - CONTAINMENT POST-ACCIDENT HYDROGEN ANALYZER INOPERABLE SINCE JULY 97 - | | | | AFTER REVIEWING TEST DATA FOLLOWING MAINTENANCE ACTIVITIES, THE LICENSEE | | DETERMINED THAT THE 'B' TRAIN CONTAINMENT POST-ACCIDENT HYDROGEN ANALYZER | | HAS BEEN INOPERABLE SINCE JULY 1997 DUE TO A FAULTY CONTROL MODULE. TECH | | SPEC 3.3.3.A REQUIRES THE LICENSEE TO RESTORE THE ANALYZER TO OPERABLE | | STATUS WITHIN 30 DAYS OR SUBMIT A WRITTEN REPORT TO NRC REGION 4 WITHIN THE | | FOLLOWING 14 DAYS IN ACCORDANCE WITH THE REQUIREMENTS OF TECH SPEC 5.9.8. | | THE 'A' TRAIN CONTAINMENT POST-ACCIDENT HYDROGEN ANALYZER REMAINS OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THIS SITUATION, REPLACING THE FAULTY ANALYZER | | CONTROL MODULE, AND PREPARING A WRITTEN REPORT OF THIS SITUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+