U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/12/98 - 03/13/98 ** EVENT NUMBERS ** 33713 33876 33877 33878 33884 33885 33886 33887 33888 33889 33890 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33713 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 02/13/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:24 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/13/98 | +------------------------------------------------+EVENT TIME: 12:38[CST]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED AN ACCIDENT SCENARIO INVOLVING USE OF THE POLAR | | CRANE WHICH COULD ADVERSELY AFFECT DECAY HEAT REMOVAL. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE THE FORT CALHOUN STATION HAS AND DOES COMPLY WITH NUREG 0612, | | 'CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS' PHASE ONE GUIDELINES, | | DURING A DESIGN BASIS REVIEW, A DISCREPANCY IN THE UPDATED SAFETY ANALYSIS | | REPORT (USAR) SECTION 14.24, 'HEAVY LOAD INCIDENT,' WAS NOTED. A | | POSTULATED SCENARIO COULD HAVE RESULTED IN THE PLANT NOT MEETING ITS DESIGN | | CRITERIA AS STATED IN THE USAR. THE SCENARIO IS DESCRIBED BELOW:" | | | | "ABOUT 5 DAYS FOLLOWING A REACTOR SHUTDOWN WITH THE PRESSURIZER MANWAY | | REMOVED AND THE REACTOR HEAD INSTALLED, IF THE POLAR CRANE WERE USED TO | | MOVE LOADS INTO CONTAINMENT THROUGH THE EQUIPMENT HATCH AND A LOAD DROP | | WERE TO OCCUR OUTSIDE OF AND ADJACENT TO THE BIO-SHIELD, PIPING DAMAGE | | COULD OCCUR THAT WOULD PREVENT USING SAFETY INJECTION (SI) INJECTION LINES | | FOR DECAY HEAT REMOVAL. BOILING COULD BE DELAYED USING OTHER PLANT SYSTEMS | | BUT COULD NOT BE PREVENTED. BOILING COULD HAVE OCCURRED IN AS LITTLE AS 2 | | HOURS WITHOUT COMPENSATORY MEASURES. EVEN WITH SOME OTHER COOLING, BOILING | | WOULD MOST PROBABLY OCCUR WITHIN THE 8 HOURS POSTULATED BY THE USAR. ONCE | | BOILING BEGINS, CONTAINMENT ENVIRONMENTAL CONDITIONS WOULD RAPIDLY DEGRADE | | TO A POINT WHICH WOULD PRECLUDE REPAIRS. IT IS, THEREFORE, UNLIKELY THAT | | THE USAR REQUIREMENT OF COMPLETING REPAIR WITHIN 8 HOURS WOULD BE | | ACCOMPLISHED." | | | | "SINCE THE POLAR CRANE IS REQUIRED TO BE IMMOBILIZED DURING POWER | | OPERATION, THIS PROBLEM COULD ONLY HAVE OCCURRED WHILE THE REACTOR WAS | | SHUTDOWN. IT IS NORMAL FOR LOADS TO BE MOVED INTO CONTAINMENT THROUGH THE | | EQUIPMENT HATCH ABOUT 5 DAYS INTO A REFUELING OUTAGE." | | | | "THE PLANT IS CURRENTLY AT 100% POWER, AND THE POLAR CRANE IS IMMOBILIZED. | | NO HEAVY LOADS WILL BE MOVED INSIDE CONTAINMENT UNTIL THIS ISSUE IS | | RESOLVED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * *RETRACTION AT 1218 EST ON 03/12/98 FROM ERICK MATZKE TO FANGIE JONES* * | | | | WITH FURTHER EVALUATION, THE LICENSEE CONCLUDED THAT THE EVENT POSTULATED | | (A HEAVY LOAD DROP THAT APPEARED OUTSIDE THE DESIGN BASIS) IS NOT PART OF | | THE LICENSING OR DESIGN BASIS. THE INFORMATION HAD BEEN PLACED IN THE USAR | | AS PART OF THE PHASE 2 RESPONSE TO NUREG-0612. THE USAR DID NOT PROVIDE A | | CLEAR DISTINCTION BETWEEN THE REQUIRED PHASE 1 INFORMATION AND THE PHASE 2 | | INFORMATION, WHICH HAS NEVER BEEN A PART OF THE PLANT DESIGN OR LICENSING | | BASIS. THEREFORE, EVENT NOTIFICATION #33713 IS BEING RETRACTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC HEADQUARTERS | | OPERATIONS OFFICER INFORMED THE R4DO (BLAINE MURRAY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33876 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 03/11/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:47 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/11/98 | +------------------------------------------------+EVENT TIME: 00:58[CST]| |NRC NOTIFIED BY: DAVID FLOWERS |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |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 Y 29 POWER OPERATION | 29 POWER OPERATION | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE CONTROL ROOM VENTILATION MAKEUP SUPPLY FAN AUTOMATIC | | START FEATURE IS INHIBITED WHILE SWAPPING CONTROL ROOM VENTILATION TRAINS | | (REFER TO EVENT #33877 FOR THE SAME ISSUE AT BRAIDWOOD.) | | | | A CONDITION WAS DISCOVERED THAT WOULD INHIBIT THE AUTOMATIC START FEATURE | | OF THE CONTROL ROOM VENTILATION MAKEUP SUPPLY FAN FOR BOTH CONTROL ROOM | | VENTILATION TRAINS, AND THIS WOULD ONLY OCCUR WHILE THE CONTROL ROOM | | VENTILATION TRAINS ARE BEING SWAPPED. THE LICENSEE STATED THAT BOTH TRAINS | | ARE STILL OPERABLE AND CAN BE MANUALLY STARTED. HOWEVER, THE AUTOMATIC | | START FEATURE IS REQUIRED BY THE TECHNICAL SPECIFICATIONS. THE LICENSEE | | PLANS TO HAVE ENGINEERING PERSONNEL INVESTIGATE THIS DESIGN ISSUE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * *RETRACTION AT 1658 EST ON 03/12/98 FROM EDWARD LAMKEN TO FANGIE JONES* * | | | | AFTER FURTHER REVIEW, THE SWITCHING BETWEEN TRAINS OF VENTILATION IS A | | ROUTINE OPERATION THAT, BY DESIGN, REQUIRES MANUAL ACTION. THE CONTROL | | ROOM VENTILATION SYSTEM OPERATION IS IN ACCORDANCE WITH THE SYSTEM DESIGN | | AND IS BOUNDED BY THE HABITABILITY ANALYSIS. THEREFORE, EVENT NOTIFICATION | | #33876 IS BEING RETRACTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC HEADQUARTERS | | OPERATIONS OFFICER INFORMED THE R3DO (GARY SHEAR). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33877 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/11/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 06:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/11/98 | +------------------------------------------------+EVENT TIME: 01:20[CST]| |NRC NOTIFIED BY: EDWARD STEFAN |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE CONTROL ROOM VENTILATION MAKEUP SUPPLY FAN AUTOMATIC | | START FEATURE IS INHIBITED WHILE SWAPPING CONTROL ROOM VENTILATION TRAINS | | (REFER TO EVENT #33876 FOR THE SAME EVENT AT BYRON.) | | | | A CONDITION WAS DISCOVERED AT BYRON THAT ALSO APPLIES TO BRAIDWOOD BECAUSE | | BOTH FACILITIES HAVE SIMILAR CONTROL ROOM VENTILATION DESIGNS. THIS | | CONDITION WOULD INHIBIT THE AUTOMATIC START FEATURE OF THE CONTROL ROOM | | VENTILATION MAKEUP SUPPLY FAN FOR BOTH CONTROL ROOM VENTILATION TRAINS, AND | | IT WOULD ONLY OCCUR WHILE THE CONTROL ROOM VENTILATION TRAINS ARE BEING | | SWAPPED. THE LICENSEE STATED THAT BOTH TRAINS ARE STILL OPERABLE AND CAN | | BE MANUALLY STARTED. HOWEVER, THE AUTOMATIC START FEATURE IS REQUIRED BY | | THE TECHNICAL SPECIFICATIONS. THE LICENSEE PLANS TO HAVE ENGINEERING | | PERSONNEL INVESTIGATE THIS DESIGN ISSUE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * *RETRACTION AT 1720 EST ON 03/12/98 FROM HAROLD ANDREWS TO FANGIE JONES* | | | | AFTER FURTHER REVIEW, THE SWITCHING BETWEEN TRAINS OF VENTILATION IS A | | ROUTINE OPERATION THAT, BY DESIGN, REQUIRES MANUAL ACTION. THE CONTROL | | ROOM VENTILATION SYSTEM OPERATION IS IN ACCORDANCE WITH THE SYSTEM DESIGN | | AND IS BOUNDED BY THE HABITABILITY ANALYSIS. THEREFORE, EVENT NOTIFICATION | | #33877 IS BEING RETRACTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC HEADQUARTERS | | OPERATIONS OFFICER INFORMED THE R3DO (GARY SHEAR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33878 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/11/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 09:11 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/11/98 | +------------------------------------------------+EVENT TIME: 05:16[PST]| |NRC NOTIFIED BY: JUSTIN McBRIDE |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |CHET POSLUSNY, NRR PM | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM DUE TO A MAIN GENERATOR TRIP FOR UNKNOWN REASONS | | AND SECOND AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR VESSEL WATER LEVEL | | | | AT 0507 PST, AN AUTOMATIC REACTOR SCRAM OCCURRED DUE TO A MAIN GENERATOR | | TRIP FOR UNKNOWN REASONS. ALL RODS FULLY INSERTED, AND THE RECIRCULATION | | PUMPS TRIPPED. ALL THREE EMERGENCY DIESEL GENERATORS AUTOMATICALLY STARTED | | DUE TO HIGH DRYWELL PRESSURE (1.65 PSIG) BUT DID NOT LOAD. THE HIGH | | DRYWELL PRESSURE WAS CAUSED BY A LOSS OF REACTOR CLOSED COOLING WATER DUE | | TO A LOSS OF POWER. THERE WAS ALSO A BUS LOCKOUT WHICH CAUSED A TEMPORARY | | POWER LOSS TO CERTAIN NON-VITAL BUSSES. REACTOR CORE ISOLATION COOLING WAS | | MANUALLY INITIATED. THERE WERE NO AUTOMATIC EMERGENCY CORE COOLING SYSTEM | | ACTUATIONS, AND THERE WAS NO LOSS OF OFFSITE POWER. ALL SYSTEMS FUNCTIONED | | AS REQUIRED, AND THERE WAS NOTHING THAT WAS UNUSUAL OR NOT UNDERSTOOD OTHER | | THAN THE CAUSE OF THE MAIN GENERATOR TRIP. | | | | THE PLANT IS CURRENTLY STABLE IN CONDITION 3 (HOT SHUTDOWN). WATER IS | | BEING SUPPLIED TO THE REACTOR VESSEL VIA THE CONTROL ROD DRIVES AND THE | | REACTOR CORE ISOLATION COOLING SYSTEM, AND STEAM IS BEING DUMPED TO THE | | SUPPRESSION POOL. THE PLANT IS CURRENTLY IN NATURAL CIRCULATION, AND THE | | LICENSEE IS IN THE PROCESS OF TRYING TO RESTORE THE RECIRCULATION PUMPS. | | THE DIVISION 3, HIGH PRESSURE CORE SPRAY DIESEL HAS BEEN SECURED, AND THE | | REMAINING TWO EMERGENCY DIESEL GENERATORS ARE STILL RUNNING AND HAVE | | REMAINED UNLOADED. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE MAIN GENERATOR | | TRIP. THERE WERE NO RELATED MAINTENANCE OR SURVEILLANCE ACTIVITIES ONGOING | | AT THE TIME OF THIS EVENT. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1228 EST ON 03/11/98 FROM GARDES ENTERED BY JOLLIFFE * * | | | | THE LICENSEE DETERMINED THAT AT 0531 PST, FOLLOWING THE ABOVE REPORTED | | REACTOR SCRAM, A SECOND AUTOMATIC REACTOR SCRAM OCCURRED DUE TO LOW REACTOR | | VESSEL WATER LEVEL (13 INCHES). NORMAL LEVEL IS 36 INCHES. | | | | FOLLOWING THE INITIAL AUTOMATIC REACTOR SCRAM, THE PLANT ALSO EXPERIENCED | | VARIOUS ENGINEERED SAFETY FEATURE (ESF) ACTUATIONS ASSOCIATED WITH THE HIGH | | DRYWELL PRESSURE SETPOINT (1.65 PSIG) DUE TO THE LOSS OF REACTOR CLOSED | | COOLING WATER (INCLUDING THE AUTOMATIC START OF THE HIGH PRESSURE CORE | | SPRAY PUMP) AND VARIOUS ESF ACTUATIONS ASSOCIATED WITH THE LOW-LOW REACTOR | | VESSEL WATER LEVEL SETPOINT (-50 INCHES) DUE TO THE CLOSURE OF THE MAIN | | STEAM ISOLATION VALVES. THE LICENSEE IS CURRENTLY VERIFYING THAT ALL OF | | THESE VARIOUS ESF ACTUATIONS OPERATED CORRECTLY. | | | | THE PLANT IS CURRENTLY STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE PLANS TO SUBMIT A WRITTEN LICENSEE EVENT REPORT ON THIS EVENT | | TO THE NRC. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R4DO (BLAINE MURRAY). | | | | * * * UPDATE AT 2342 EST ON 03/12/98 FROM PERINO RECEIVED BY TROCINE * * * | | | | THIS EVENT UPDATE REPORT WAS MADE TO PROVIDE SUPPLEMENTAL AND CORRECTED | | INFORMATION TO THE EMERGENCY NOTIFICATION SYSTEM NOTIFICATIONS MADE BY THE | | LICENSEE ON 03/11/98 PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.72(b)(2)(ii) | | AND 10 CFR 50.72(b)(1)(iv). CHANGES PROVIDED BY THIS EVENT UPDATE INCLUDED | | THE ADDITION OF EMERGENCY CORE COOLING SYSTEM (ECCS) INJECTION TO THE | | REPORTING CRITERIA, REVISION OF THE EVENT TIME FROM 0507 PST TO 0516 PST, | | CORRECTIONS TO THE EVENT DESCRIPTION, AND ADDITION OF A PRESS RELEASE TO | | THE LICENSEE'S NOTIFICATIONS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | " AT 0516 [PST] ON 03/11/98, [THE UNIT] EXPERIENCED A PLANT TRANSIENT AND | | SCRAM DUE TO THE FOLLOWING SEQUENCE OF EVENTS:" | | | | "THE INITIATING EVENT WAS A CONTAINMENT INSTRUMENT AIR (CIA) SYSTEM LEAK | | INSIDE THE DRYWELL WHICH CAUSED CLOSURE OF A SINGLE [MAIN STEAM ISOLATION | | VALVE (MSIV)]. DUE TO THE RESULTING VOID COLLAPSE, THE REACTOR SCRAMMED ON | | HIGH NEUTRON FLUX, AND THE REMAINING MSIVs ISOLATED DUE TO HIGH STEAM LINE | | FLOW (140%). REACTOR PRESSURE IMMEDIATELY PEAKED AT 1,085 PSIG, [AND] | | VESSEL LEVEL DECREASED TO LEVEL 2 (-50 [INCHES])[. THIS CAUSED] INITIATION | | AND INJECTION OF THE [REACTOR CORE ISOLATION COOLING (RCIC)] AND [HIGH | | PRESSURE CORE SPRAY (HPCS)] SYSTEMS AND [CAUSED] TRIPPING OF THE [REACTOR | | CLOSED COOLING WATER] PUMPS WHICH PROVIDE COOLING TO THE DRYWELL | | ATMOSPHERE. WITHIN 60 SECONDS, REACTOR LEVEL RECOVERED TO ABOVE LEVEL 8 | | (+54 [INCHES])[. THIS CAUSED] THE RCIC STEAM SUPPLY VALVE AND HPCS | | INJECTION VALVE TO AUTOMATICALLY CLOSE, [THUS] TERMINATING THE INJECTION. | | RCIC WAS SUBSEQUENTLY MANUALLY RESTARTED FOR LEVEL CONTROL, AND PRESSURE | | CONTROL WAS ACCOMPLISHED BY INTERMITTENT MANUAL [MAIN STEAM RELIEF VALVE] | | OPENING. APPROXIMATELY 11 MINUTES INTO THE EVENT, DRYWELL PRESSURE PEAKED | | AT ABOUT 1.60 PSIG AND THEN BEGAN TO DECREASE BECAUSE DRYWELL COOLING HAD | | BEEN RE-ESTABLISHED AND [BECAUSE] VENTING THROUGH STAND-BY GAS TREATMENT | | [HAD BEEN] STARTED. THE DRYWELL PRESSURE PEAK OF APPROXIMATELY 1.60 PSIG | | WAS SUFFICIENT TO SATISFY ECCS LOGIC WHICH AUTO[MATICALLY] STARTED THE | | DIVISION I AND II [EMERGENCY DIESEL GENERATORS,] AND [IT WAS] ALSO | | SUFFICIENT FOR PARTIAL MAKEUP OF LOW PRESSURE ECCS PUMP START LOGIC. DUE | | TO THE CLOSE PROXIMITY OF ACTUAL DRYWELL PRESSURE ACHIEVED DURING THIS | | EVENT AND ECCS PUMP START LOGIC (1.65 PSIG), SOME ELEMENTS IN THE LOW | | PRESSURE ECCS PUMP START LOGIC REMAINED UNSATISFIED (BECAUSE ACTUAL DRYWELL | | PRESSURE DID NOT REACH THE 1.68 PSIG SETPOINT)[.] THEREFORE, NO LOW | | PRESSURE ECCS PUMP LOGIC WAS SATISFIED DURING THE EVENT." | | | | UPON FURTHER INVESTIGATION, THE LICENSEE CONCLUDED THAT ALL SYSTEMS | | FUNCTIONED AS REQUIRED AND THAT THERE WAS NOTHING THAT WAS UNUSUAL OR NOT | | UNDERSTOOD. THE UNIT IS CURRENTLY IN CONDITION 4 (COLD SHUTDOWN), AND A | | UNIT RESTART DATE IS UNKNOWN AT THIS TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND ISSUED A PRESS | | RELEASE. THE NRC OPERATIONS CENTER NOTIFIED THE R4DO (MURRAY), NRR EO | | (MARSH AND DENNIG), AND AEOD IRD (RUBIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33884 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/12/98 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:48 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/11/98 | +------------------------------------------------+EVENT TIME: 23:16[CST]| |NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM SIGNAL WITH NO ROD MOTION DUE TO A HIGH SCRAM | | INSTRUMENT VOLUME LEVEL WHILE THE UNIT WAS IN MODE 5 (REFUELING) | | | | WITH UNIT 2 IN MODE 5 PREPARING FOR FUEL OFFLOAD, A REACTOR SCRAM SIGNAL | | WAS RECEIVED FROM A HIGH SCRAM INSTRUMENT VOLUME LEVEL. THERE WAS NO | | CONTROL ROD MOVEMENT BECAUSE ALL RODS WERE ALREADY FULLY INSERTED WITH ALL | | CONTROL ROD DRIVES OUT OF SERVICE. THE SCRAM DISCHARGE VOLUME VENTS AND | | DRAINS WERE TAKEN OUT OF SERVICE PRIOR TO THE EVENT (EARLIER THIS SHIFT). | | THERE WERE NO EMERGENCY CORE COOLING SYSTEM OR ENGINEERED SAFETY FEATURE | | ACTUATIONS, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THERE WAS NOTHING THAT | | WAS UNUSUAL OR NOT UNDERSTOOD OTHER THAT THE SOURCE OF WATER TO THE SCRAM | | INSTRUMENT VOLUME. THE LICENSEE IS CURRENTLY PERFORMING A REVIEW OF THE | | WORK IN PROGRESS AT THE TIME OF THE EVENT IN ORDER TO DETERMINE THE INPUT | | (SOURCE OF WATER) TO THE VOLUME. | | | | AT THIS TIME, THE UNIT IS IN ITS NORMAL REFUELING ALIGNMENT FOR FEED AND | | BLEED OF THE REACTOR. CORE SPRAY KEEP FILL IS BEING UTILIZED TO SUPPLY | | WATER TO THE REACTOR VESSEL, AND BLEED IS THROUGH FUEL POOL REJECT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33885 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 03/12/98 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 06:20 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 03/12/98 | +------------------------------------------------+EVENT TIME: 03:54[EST]| |NRC NOTIFIED BY: JOE HORON |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | |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 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS ASSESSMENT CAPABILITY WITH THE NORMAL AND HIGH RANGE NOBLE GAS | | MONITORS AS A RESULT OF REMOVAL THE HIGH RANGE CONTAINMENT GAMMA MONITORS | | FROM SERVICE | | | | AT 2213 ON 03/11/98, THE HIGH RANGE CONTAINMENT GAMMA MONITORS WERE REMOVED | | FROM SERVICE; AND WHEN THE LICENSEE OPENED THE BREAKER, THE NORMAL AND HIGH | | RANGE NOBLE GAS MONITORS FOR THE PLANT STACK WERE ALSO LOST. THIS WAS | | DISCOVERED AND CORRECTED AT 0354 ON 03/12/98. THE ALARM PANEL HAD BEEN OUT | | OF SERVICE FOR SEVERAL WEEKS DUE TO POTENTIAL GROUND PROBLEMS DURING | | WASHING OF THE RECIRCULATION PUMP ROOM WITH HIGH PRESSURE WATER. OTHER | | MEANS OF MONITORING STACK EFFLUENT RELEASES FOR IODINE AND PARTICULATES | | WERE AVAILABLE, AND THERE WERE NO INDICATIONS OF ANY RELEASE WHILE THE | | NORMAL AND HIGH RANGE MONITORS WERE OUT OF SERVICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33886 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LEXALITE INTERNATIONAL CORPORATION |NOTIFICATION DATE: 03/12/98 | | CITY: CHARLEVOIX REGION: 3 |NOTIFICATION TIME: 15:40 [ET]| | COUNTY: CHARLEVOIX STATE: MI |EVENT DATE: 02/16/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 10:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/12/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GARY SHEAR RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SCOTT WALKER | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST STATIC ELIMINATOR WITH POLONIUM-210 SEALED SOURCE | | | | DURING AN ANNUAL AUDIT OF 16 PERMANENTLY MOUNTED STATIC ELIMINATOR DEVICES | | WHICH ARE USED CONTINUOUSLY IN PLASTIC MOLDING OPERATION, 1 WAS FOUND TO BE | | MISSING. THE DEVICE IS LEASED FROM NRD CORPORATION AND IS A MODEL P-2051 | | WITH A SERIAL NUMBER OF 91902 ON LEASE NUMBER 059571. IT CONTAINS A SMALL | | SEALED POLONIUM (Po-210) SOURCE (PROBABLY 10 mCi). THE DEVICE IS REMOVABLE | | AND IS THOUGHT TO HAVE LOOSENED AND FALLEN OFF, AND IT WAS NOT NOTICED TO | | BE MISSING. THERE WERE SEARCHES PERFORMED BY TECHNICIANS WITH APPROPRIATE | | EQUIPMENT TO LOCATE THE SOURCE. IT IS THOUGHT TO HAVE BEEN SWEPT UP DOING | | CLEANING AND DUMPED IN THE TRASH. | | | | THE COMPANY HAS INSTITUTED MEASURES TO PREVENT RECURRENCE OF THIS EVENT. | | INCLUDED IS A CHECK LOG (ATTACHED TO EACH PAINTING WORK STATION WITH THE | | DEVICES PERMANENTLY MOUNTED) FOR EACH OPERATOR TO SIGN ACKNOWLEDGING THAT | | THE DEVICE IS IN PLACE AND IN GOOD CONDITION. THE DEVICES IN THE MOLDING | | AREAS WILL BE REMOVED FROM THE WORK STATIONS AND WILL BE LOGGED OUT AS | | NEEDED. THEY ARE THEN TO BE RETURNED AS THE JOB IS COMPLETED AND LOGGED | | IN. | | | | REGION 3 DNMS (JAMES CAMERON) HAS BEEN NOTIFIED BY LEXALITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33887 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/12/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:21 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/12/98 | +------------------------------------------------+EVENT TIME: 15:32[EST]| |NRC NOTIFIED BY: JOHN APRIL |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A POTENTIAL CONDITION EXISTS THAT COULD CREATE A DIRECT VENT PATH FROM THE | | CONTAINMENT TO ATMOSPHERE. | | | | DURING REVIEW OF A VERMONT YANKEE EVENT NOTIFICATION (#33789), CONCERNING | | THE VENTING OF THE PRIMARY CONTAINMENT VIA THE STANDBY GAS TREATMENT SYSTEM | | (RBEVS AT NINE MILE POINT), IT HAS PRELIMINARILY BEEN DETERMINED THAT A | | SIMILAR CONDITION COULD OCCUR AT NINE MILE POINT UNIT 1. SPECIFICALLY, | | WHILE VENTING THE PRIMARY CONTAINMENT VIA THE RBEVS CONCURRENT WITH A LOSS | | OF COOLANT ACCIDENT (LOCA), THE DESIGN PRESSURE OF THE DUCT WORK COULD BE | | EXCEEDED, AND A DIRECT RELEASE PATH COULD BE OPENED FROM THE PRIMARY | | CONTAINMENT. THE ACTION OF VENTING THE CONTAINMENT AT POWER USING THE | | RBEVS HAS PREVIOUSLY BEEN PERFORMED. ADMINISTRATIVE CONTROLS HAVE BEEN | | PLACED TO PREVENT THIS ACTION PENDING FURTHER REVIEW. THIS IS BEING | | CONSIDERED A CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF | | THE SAFETY FUNCTION OF THE RBEVS (POST-LOCA) IN LIMITING THE RELEASE OF | | RADIOACTIVE MATERIAL DUE TO FILTER HOUSING FAILURE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33888 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 03/12/98 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/12/98 | +------------------------------------------------+EVENT TIME: 01:01[EST]| |NRC NOTIFIED BY: LARRY WHITE |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 +------------------------------------------------------------------------------+ | POTENTIAL PROGRAMMATIC WEAKNESS IN THE IMPLEMENTATION OF FIRE WATCHES | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON THREE SEPARATE OCCASIONS, REQUIRED FIRE WATCHES WERE MISSED OR | | PERFORMED LATE CONTRARY TO THE REQUIREMENTS OF THE FIRE PROTECTION PROGRAM | | COMMITMENTS. THESE EVENTS INDICATE A POTENTIAL PROGRAMMATIC WEAKNESS IN | | THE IMPLEMENTATION OF THE FIRE PROTECTION PROGRAM." | | | | "DUKE ENERGY CORPORATION IS REQUIRED TO IMPLEMENT AND MAINTAIN IN EFFECT | | ALL PROVISIONS OF THE APPROVED FIRE PROTECTION PROGRAM AS DESCRIBED IN THE | | CATAWBA UPDATED FINAL SAFETY ANALYSIS REPORT, AS AMENDED VIA LICENSE | | CONDITION 2.C(8) FOR UNIT 1. IT HAS BEEN DETERMINED THAT THIS EVENT IS A | | VIOLATION OF THIS LICENSE CONDITION AND IS REPORTABLE VIA EMERGENCY | | NOTIFICATION SYSTEM WITHIN 24 HOURS PER LICENSE CONDITION 2.F." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33889 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/12/98 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 20:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/12/98 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: STEVE CHERBA |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SOFTWARE CODE MAY HAVE UNDERESTIMATED ICE BASKET WEIGHT. | | | | DURING A REVIEW OF RAW DATA USED BY THE SOFTWARE (NSLICE) TO DETERMINE THE | | RADIAL ROW AVERAGE ICE WEIGHT IN THE CONTAINMENT, IT WAS NOTED THAT | | INDIVIDUAL BASKET WEIGHTS OF LESS THAN 800 POUNDS (LBS) WERE IGNORED. | | NSLICE IS USED TO PERFORM A STATISTICAL ANALYSIS OF TOTAL ICE BASKET WEIGHT | | USING A SAMPLING OF INDIVIDUAL BASKETS THROUGHOUT THE CONTAINMENT. | | TECHNICAL SPECIFICATION (TS) 3.6.5.1 REQUIRES THAT THE ICE CONDENSER BE | | DIVIDED INTO 3 GROUPS OF BASKETS AND THAT THE AVERAGE ICE WEIGHT OF BASKETS | | FOR THE SAMPLES IN EACH GROUP CONTAIN AT LEAST 1333 LBS/BASKET AT A 95% | | CONFIDENCE LEVEL. | | | | THE UNIT 1 AS-FOUND WEIGHING PROGRAM RECORDS (IN 1995 AND 1997) AND THE | | UNIT 2 AS-FOUND WEIGHING PROGRAM RECORDS (IN 1996) INDICATE THE PRESENCE OF | | ICE BASKETS WITH WEIGHTS BELOW THE 800 LB LIMIT. THE APPARENT EXCLUSION OF | | THESE VALUES BY NSLICE MAY HAVE CAUSED A VIOLATION OF TSs WITH REGARD TO | | THE RADIAL ROW AVERAGE ICE WEIGHT REQUIREMENT. IN ADDITION, THE LOW WEIGHT | | BASKETS (ABOUT 300 LBS) MAY HAVE PLACED THE ICE CONDENSER IN AN UNANALYZED | | CONDITION WITH RESPECT TO ICE MALDISTRIBUTION ANALYSES, WHICH DOES NOT | | ADDRESS MINIMUM ICE BASKET WEIGHTS BELOW 400 LBS. | | | | BOTH UNITS' ICE CONDENSERS ARE PRESENTLY INOPERABLE DUE TO ONGOING | | MAINTENANCE WITH BOTH UNITS IN COLD SHUTDOWN. EVALUATION OF ICE BASKET | | WEIGHT COMPLIANCE WILL CONTINUE, AND THE PLANTS WILL REMAIN IN COLD | | SHUTDOWN UNTIL THE PROBLEM IS CORRECTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33890 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/12/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:24 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/12/98 | +------------------------------------------------+EVENT TIME: 19:00[CST]| |NRC NOTIFIED BY: BART CROW |LAST UPDATE DATE: 03/12/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A PROCEDURAL DEFICIENCY POTENTIALLY DEFEATS THE ABILITY OF CORE SPRAY TO | | FULFILL ITS SAFETY FUNCTION. | | | | WHILE RESEARCHING AN UNRELATED 10 CFR 50.59 REVIEW, A COOPER ENGINEER | | IDENTIFIED GUIDANCE THAT COULD HAVE PREVENTED THE CORE SPRAY SYSTEM FROM | | FULFILLING ITS SAFETY FUNCTION DURING A DESIGN BASIS LOSS OF COOLANT | | ACCIDENT (DBLOCA). THE GUIDANCE WAS TO LIMIT CORE SPRAY FLOW TO 9,500 GPM | | (4,750 GPM PER PUMP). FULL RATED FLOW IS 12,200 GPM AT 0 PSID. IN THE | | EVENT OF A DBLOCA, THE RELOAD ANALYSIS ASSUMES FULL CORE SPRAY AFTER | | BLOWDOWN TO REFLOOD THE REACTOR PRESSURE VESSEL. PRELIMINARY | | INVESTIGATIONS HAVE REVEALED THAT IN THE UNLIKELY EVENT AN OPERATOR | | PREMATURELY THROTTLED CORE SPRAY FLOW, PEAK CLADDING TEMPERATURE COULD BE | | EXCEEDED. | | | | IMMEDIATE CORRECTIVE ACTIONS INCLUDE REVISION OF THE AFFECTED PROCEDURES TO | | ENSURE THAT CORE SPRAY FLOW IS NOT THROTTLED UNTIL THE REACTOR PRESSURE | | VESSEL HAS BEEN REFLOODED AND CORE COOLING IS MAINTAINED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+