U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/20/97 - 03/21/97 ** EVENT NUMBERS ** 31831 31978 31979 31980 31981 31982 31983 31984 31985 31986 31987 31988 31989 31990 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31831 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/21/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:30 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/21/97 | +------------------------------------------------+EVENT TIME: 18:10[EST]| |NRC NOTIFIED BY: JAMES BAUER |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FEEDWATER COOLANT INJECTION SYSTEM DECLARED INOPERABLE DUE TO SLOW STROKE | | TIME OF THE EMERGENCY CONDENSATE TRANSFER PUMP DISCHARGE VALVE DURING | | SURVEILLANCE TESTING | | | | THIS UNIT DOES NOT HAVE A HIGH PRESSURE COOLANT INJECTION SYSTEM. IT | | UTILIZES THE MAIN FEEDWATER SYSTEM WITH A SEPARATE STARTING CIRCUIT FOR | | THIS FEATURE. IF NEEDED, THE CONDENSATE TRANSFER PUMP WOULD START TO PUMP | | WATER FROM THE CONDENSATE STORAGE TANK TO THE FEEDWATER PUMP SUCTION. | | HOWEVER, THE DISCHARGE VALVE ON THE EMERGENCY CONDENSATE TRANSFER PUMP | | (#1MW-96A) DOES NOT STROKE PROPERLY IF AN ACCIDENT WERE TO OCCUR DURING | | SURVEILLANCE TESTING. | | | | THE CONTROL CIRCUIT OF THIS VALVE REQUIRES IT TO STROKE FULLY TO THE CLOSED | | POSITION BEFORE IT CAN STROKE BACK INTO THE OPEN POSITION. IF THE VALVE | | WERE IN THE PROCESS OF GOING CLOSED DURING A SURVEILLANCE TEST AND IF AN | | ACCIDENT OCCURRED WHICH REQUIRED THE VALVE TO GO TO ITS SAFETY POSITION | | (WHICH IS OPEN), THE VALVE WOULD HAVE TO TRAVEL COMPLETELY TO ITS CLOSED | | POSITION BEFORE IT WOULD STROKE OPEN AGAIN. THE PLANT'S DESIGN BASIS | | REQUIRES THE SYSTEM TO BE ABLE TO PROVIDE 3,600 GALLONS PER MINUTE | | INJECTION FLOW WITHIN 20 SECONDS OF THE SYSTEM RECEIVING POWER FROM THE GAS | | TURBINE. THE VALVE IN QUESTION IS A 40 SECOND TRAVEL VALVE. THEREFORE, IT | | TAKES 40 SECONDS FOR THE VALVE TO TRAVEL FROM THE FULLY OPEN POSITION TO | | THE FULLY CLOSED POSITION, AND IT TAKES APPROXIMATELY 17 SECONDS FOR THE | | VALVE TO REOPEN ENOUGH TO OBTAIN THE REQUIRED 3,600 GALLONS PER MINUTE | | INJECTION FLOW. THIS PLACES THE UNIT OUTSIDE ITS DESIGN BASIS. AS A | | RESULT, THE LICENSEE HAS PLACED THE FEEDWATER COOLANT INJECTION SYSTEM IN | | AN INOPERABLE STATUS. THE UNIT IS NOT IN A TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION AS A RESULT OF THIS ISSUE DUE TO THE | | CURRENT MODE OF OPERATION (COLD SHUTDOWN). | | | | THE LICENSEE IDENTIFIED A FEW OTHER VALVES IN THE PLANT THAT HAVE THE SAME | | STROKE CIRCUIT. AT THIS TIME, THE LICENSEE DOES NOT BELIEVE THAT THESE | | ADDITIONAL VALVES ARE OUTSIDE THEIR DESIGN BASIS, BUT INVESTIGATIONS ARE | | CURRENTLY ONGOING. THE LICENSEE PLANS TO PROVIDE AN UPDATE TO THIS REPORT | | IF THIS DETERMINATION CHANGES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL OFFICIALS. | | | | * * RETRACTION ON 03/20/97 @ 1538 EST BY BILL LOWETH TAKEN BY MACKINNON * * | | | | LICENSEE IS RETRACTING THIS EVENT BECAUSE THE AFFECT OF THE TIME DELAY IN | | STROKING OPEN THE EMERGENCY CONDENSATE TRANSFER PUMP DISCHARGE VALVE DOES | | NOT AFFECT/DEGRADE FEEDWATER COOLANT INJECTION (FWCI) IN PERFORMING ITS | | SAFETY FUNCTION. THERE IS SUFFICIENT INVENTORY IN THE HOTWELL (60,000 | | gallons) SUCH THAT THE SMALL TIME DELAY IN THE EMERGENCY CONDENSATE | | TRANSFER INITIATION WILL NOT AFFECT FWCI. THE CONDENSATE AND FEEDWATER | | STRING WILL STILL INJECT WATER WITHIN THE PRESCRIBED TIMES FROM THE | | CONDENSER SO THAT THIS FUNCTION IS NOT COMPROMISED. R1DO (RICH BARKLEY) | | NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31978 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 00:40 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 03/19/97 | +------------------------------------------------+EVENT TIME: 22:00[CST]| |NRC NOTIFIED BY: DAVID SCHMIDT |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 79 POWER OPERATION | 79 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED HPCI INOPERABLE FOR 1.25 HOURS DUE TO A SUSPECTED | | DAMAGED POWER CABLE FOR THE HPCI GLAND LEAKOFF BLOWER. HPCI IS A SINGLE | | TRAIN SAFETY SYSTEM. THEY SUBSEQUENTLY DETERMINED THAT THE CABLE WAS | | ABANDONED BUT NOT MARKED. HPCI WAS RETURNED TO OPERABLE STATUS. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31979 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/20/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 02:25 [ET]| |RX TYPE: [3] CE |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 01:03[CST]| |NRC NOTIFIED BY: LYMAN ELLZEY |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BATEMAN EO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |CIBOCH FEMA | | |RICHARD BARRETT AEOD | | |BLANCHARD EPA | | |TANNER DOE | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED AN ALERT AT 0103 CST WHEN THEY RECEIVED NOTIFICATION | | THAT A RELEASE OF TOXIC GASEOUS AMMONIA WAS IN PROGRESS AT A CHEMICAL PLANT | | LESS THAN A MILE FROM THE SITE. THE WIND WAS BLOWING THE GAS AWAY FROM THE | | PLANT. PERSONNEL ON SITE WERE SHELTERED AND THE CONTROL ROOM ENVIRONMENT | | WAS SHIFTED TO THE ISOLATED MODE. | | | | THE RELEASE OCCURRED WHEN A RUNAWAY BARGE STRUCK A PIPE RELEASING A BURST | | OF AMMONIA. THE LEAK WAS ISOLATED AND THE LICENSEE TERMINATED THE ALERT AT | | 0142 CST. THE LICENSEE NOTIFIED STATE AND LOCAL GOVERNMENT AGENCIES THAT | | THEY HAD DECLARED AN ALERT. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | THE US NRC ALSO NOTIFIED HHS (WILSON) AND USDA (GRAHAM). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31980 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/20/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 03:33 [ET]| |RX TYPE: [3] CE |EVENT DATE: 03/19/97 | +------------------------------------------------+EVENT TIME: 23:50[CST]| |NRC NOTIFIED BY: SCHRECKENGAST |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE INFORMED THE US COAST GUARD THAT THREE RUNAWAY BARGES HIT A | | STRUCTURE THAT PROTECTS THE PLANT INTAKE. THE INTAKE WAS NOT DAMAGED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31981 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 10:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 10:34[EST]| |NRC NOTIFIED BY: FRANK PAVLECHKO |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |AL CHAFFEE EO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |CANUPP FEMA | | |BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 DECLARED AN UNUSUAL EVENT WHEN TOXIC GAS (AMMONIA) WAS | | DETECTED IN THE TURBINE BUILDING. ACCESS TO THE TURBINE BUILDING HAS BEEN | | RESTRICTED. A SEARCH FOR THE AMMONIA SOURCE IS UNDERWAY BY PERSONNEL USING | | SELF CONTAINED BREATHING DEVICES. IT HAS NOT BEEN NECESSARY TO ISOLATE THE | | CONTROL ROOM ENVIRONMENT. THE LICENSEE THINKS THAT THE SOURCE OF THE TOXIC | | GAS MAY BE A LEAKING SECONDARY CHEMISTRY PUMP. THE LICENSEE WILL TERMINATE | | THE EVENT WHEN THE TOXIC GAS IS NO LONGER A THREAT. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR'S OFFICE AND STATE GOVERNMENT. | | | | * * * UPDATE AT 1118 EST FROM PAULECHKO TAKEN BY KARSCH * * * | | THE LEAK SOURCE HAS BEEN LOCATED AND ISOLATED. THE LEAK IS FROM A VALVE ON | | AMMONIUM HYDROXIDE TANK, "0TANK14-SST". VENTING THE TURBINE BUILDING IS | | UNDERWAY. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1233 EST FROM PAULECHKO TAKEN BY MACKINNON * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1227 EST AFTER UNRESTRICTED ACCESS TO | | THE TURBINE BUILDING WAS RESTORED. THE LICENSEE NOTIFIED THE NRC RESIDENT | | INSPECTOR, STATE, AND LOCAL COUNTIES OF THE TERMINATION OF THE UNUSUAL | | EVENT. R2DO (BRUNO URYC), NRR EO (CHAFFEE), & FEMA (CANUPP) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31982 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/20/97 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 11:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 09:12[EST]| |NRC NOTIFIED BY: TOM STEVENS |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 73 POWER OPERATION | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIPPED DURING TESTING OF REACTOR PROTECTION SYSTEM BREAKER. | | | | FOLLOWING TESTING OF REACTOR PROTECTIVE SYSTEM (RPS) CONTROL ROD DRIVE | | (CRD) SYSTEM CHANNEL "A" (CRD BREAKER NUMBER 10), RPS CHANNEL "B" WAS | | PLACED IN MANUAL BYPASS FOR TESTING, IN ACCORDANCE WITH PROCEDURES. AFTER | | PLACING CHANNEL "B" IN MANUAL BYPASS, CRD BREAKER NUMBER 11 WAS TRIPPED | | (ALSO IN ACCORDANCE WITH PROCEDURES). SUBSEQUENTLY A REACTOR TRIP OCCURRED | | (CRD BREAKER NUMBER 10 OPENED WHEN CRD BREAKER NUMBER 11 WAS TRIPPED, | | CAUSING THE REACTOR TO TRIP). ALL CONTROL RODS FULLY INSERTED INTO THE | | CORE. POST TRIP RESPONSE WAS NORMAL (MAIN STEAM LINE CODE SAFETY VALVES | | OPENED/CLOSED AS EXPECTED) WITH THE EXCEPTION OF THE LOSS OF 3X1 AND 3X3 | | (600V AC NON-SAFETY RELATED SWITCHGEAR). INVESTIGATION INTO THE CAUSE OF | | THE LOSS OF 3X1 AND 3X3 REVEALED THAT AN UNDERVOLTAGE RELAY HAD ACTUATED | | CAUSING THE LOSS OF THE SWITCHGEAR. THE FEEDER BREAKERS WERE RECLOSED AND | | POWER WAS VERIFIED AT THE LOAD CENTERS FED FROM 3X1 AND 3X3. INVESTIGATION | | IS IN PROGRESS TO DETERMINE THE CAUSE OF THE UNIT TRIP. UNIT 3 IS STABLE AT | | HOT SHUTDOWN (Tave IS 532øF AND REACTOR COOLANT SYSTEM PRESSURE IS 2150 | | psig) WITH STEAM GENERATORS PROVIDING DECAY HEAT REMOVAL. ALL EMERGENCY | | CORE COOLING SYSTEMS ARE FULLY OPERABLE AND THE ELECTRICAL GRID IS STABLE. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31983 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 13:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/19/97 | +------------------------------------------------+EVENT TIME: 15:20[CST]| |NRC NOTIFIED BY: HESSLING |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |NLTR LICENSEE 24 HR REPORT | | |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 | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO INPUT RELAYS TO THE EMERGENCY DIESEL GENERATOR LOAD SEQUENCER WERE NOT | | PROPERLY TESTED. THE RELAYS PROVIDE ONE INPUT SIGNAL TO THE EMERGENCY | | DIESEL GENERATOR LOAD SEQUENCER (TAKES 2 OUT OF 4 SIGNALS TO START). | | | | ON 03/19/97 AT 1520 CST UNIT 1 AND UNIT 2 ENTERED TECHNICAL SPECIFICATION | | 3.0.3 DUE TO A DISCOVERY OF AN INADEQUATE SURVEILLANCE AND INVOKED THE | | REQUIREMENTS OF TECHNICAL SPECIFICATION 4.0.3. DURING A REVIEW OF TECHNICAL | | SPECIFICATION REQUIREMENTS AS PER GENERIC LETTER 96-01, IT WAS DISCOVERED | | THAT THE SURVEILLANCE TESTING FOR THE 4160 VOLT BUSSES SUSTAINED A DEGRADED | | VOLTAGE CONDITION, AND THE DEGRADED VOLTAGE COINCIDENT WITH SAFETY | | INJECTION DID NOT ADEQUATELY TEST ALL LOGIC CONTACTS TO FULLY MEET THE | | SURVEILLANCE REQUIREMENTS. TECHNICAL SPECIFICATION 4.0.3 WAS INVOKED TO | | ALLOW TESTING OF THE LOGIC CONTACTS ASSOCIATED WITH BOTH DEGRADED VOLTAGE | | ACTUATION SCHEMES. | | | | THE SUSTAINED DEGRADED VOLTAGE ACTUATION SCHEME IS IN PARALLEL WITH THE | | DEGRADED VOLTAGE COINCIDENT WITH SAFETY INJECTION ACTUATION SCHEME. DURING | | THE SURVEILLANCE, TESTS ARE PROVIDED TO ENSURE BOTH SCHEMES ARE FUNCTIONAL, | | BUT DO NOT PROVIDE ASSURANCES THAT A FAILURE IN ONE ACTUATION SCHEME WILL | | NOT MASK A FAILURE IN THE OTHER ACTUATION SCHEME. AS SUCH, THIS CONDITION | | IS BEING REPORTED AS NOT FULLY MEETING THE TRIP ACTUATING DEVICE | | OPERATIONAL TEST SURVEILLANCE REQUIREMENTS OF TECHNICAL SPECIFICATION | | 4.3.2.1 TABLE 4.3-2 ITEMS 8.b AND 8.C. | | | | AT 1157 CST ON 03/20/97, BOTH UNITS EXITED TECHNICAL SPECIFICATION 3.0.3 | | AND TECHNICAL SPECIFICATION 4.0.3, AS THESE RELAYS HAVE BEEN SUCCESSFULLY | | TESTED. | | | | NOTE: UNIT 2 BEFORE/AFTER POWER LEVELS AND MODES ARE DIFFERENT DUE TO A | | REACTOR TRIP FROM A DIFFERENT EVENT OCCURRING AT 1554 CST ON 03/19/97 (SEE | | EVENT # 31976). | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31984 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/20/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:06 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 07:15[EST]| |NRC NOTIFIED BY: BALLETTA |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A CONSOLIDATED EDISON SUPERVISOR TESTED POSITIVE FOR ALCOHOL | | | | A CONSOLIDATED EDISON SUPERVISOR ASSIGNED TO THE NUCLEAR POWER PLANT WAS | | SELECTED FOR A RANDOM DRUG TEST. THE RANDOM DRUG TEST WAS PERFORMED ON | | INDIVIDUALS OUTSIDE THE PROTECTED AREA AS THEY WERE COMING TO WORK. THE | | CONSOLIDATED EDISON SUPERVISOR IS NOT A LICENSED OPERATOR AND HE DOES NOT | | SUPERVISE LICENSED OPERATORS. HE WAS CONFIRMED POSITIVE FOR ALCOHOL ON HIS | | SECOND DRUG TEST AT 0715 EST. HIS UNESCORTED ACCESS WAS SUSPENDED AND HE | | WAS REFERRED TO THE CONSOLIDATED EDISON MEDICAL DEPARTMENT FOR EVALUATION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31985 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/20/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:43 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/19/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:45[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/20/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |PAT HILAND RDO | | DOCKET: 0707001 |FRED COMBS (NMSS) EO | +------------------------------------------------+WALT SCHWINK NMSS | |NRC NOTIFIED BY: A. M. CARVER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A DEFICIENT CRITICALITY SAFETY ANALYSIS WAS DISCOVERED DURING WALKDOWN OF | | THE METALLURGY LABORATORY (BUILDING C-710). | | | | THE EVENT IS BEING REPORTED AS A 24 HOUR REPORT PER NRC BULLETIN 91-01. | | | | DURING A NUCLEAR CRITICALITY SAFETY (NCS) WALKDOWN, PERFORMED ON MARCH 19, | | 1997, OF THE C-710 METALLURGY LABORATORY, OPERATIONS WERE FOUND TO INVOLVE | | POTENTIALLY FISSILE MATERIALS FOR WHICH NO NCS EVALUATION EXISTED. THE | | ACTIVITIES ARE ASSOCIATED WITH CUTTING AND GRINDING OPERATIONS WHICH CREATE | | THE POTENTIAL FOR MATERIAL ACCUMULATION IN EQUIPMENT RESERVOIRS. AS A | | RESULT OF PRELIMINARY NCS REVIEW, THE TOTAL AMOUNT OF MATERIAL WAS | | DETERMINED TO BE MUCH LESS THAN 700 GRAMS (< 2 wt% U-235). PENDING FURTHER | | EVALUATION, THE ACCUMULATED MATERIALS ARE CONSIDERED POTENTIALLY FISSILE | | (THIS IS A CONSERVATIVE CALL AND IT HAS YET TO BE DETERMINED IF THE | | MATERIAL IS FISSILE MATERIAL). | | | | BASED ON THE RESULTS OF THIS WALKDOWN AND UNTIL FURTHER EVALUATION IS | | COMPLETED, THE LICENSEE IS CONSERVATIVELY FILING THIS REPORT TO PROVIDE | | INFORMATION CONCERNING THIS DISCOVERY. IMMEDIATE ACTIONS WERE TAKEN TO | | SECURE AFFECTED C-710 OPERATIONS AND CONTROL ACCESS TO THESE AREAS. | | | | INITIAL NCS REVIEW OF THESE OPERATIONS HAS DETERMINED THAT NO SIGNIFICANT | | ACCUMULATION OF MATERIAL, i.e. UNSAFE MASS OF FISSILE MATERIAL, COULD | | OCCUR. THEREFORE, NO IMMEDIATE SAFETY CONCERN EXISTS. NO NCS EVALUATION | | CURRENTLY EXISTS FOR THIS OPERATION. THE NRC RESIDENT INSPECTOR WILL BE | | NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31986 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/20/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:29 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/20/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:48[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/20/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |PAT HILAND RDO | | DOCKET: 0707002 |FRED COMBS (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JOE HALCOMB | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |HHHH OFFSITE NOTIFICATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE OHIO ENVIRONMENTAL PROTECTION AGENCY (EPA) THAT | | THE FACILITY EXCEEDED ITS PERMIT LIMIT FOR SUSPENDED SOLIDS DISCHARGE FROM | | THEIR LIME SLUDGE LAGOON. | | | | RESULTS FROM SAMPLES TAKEN ON MARCH 19, 1997 AT THE X-611B LIME SLUDGE | | LAGOON (NPDES OUTFALL # 005) INDICATED THAT THE TOTAL SUSPENDED SOLIDS | | (TSS) EXCEEDED PERMIT LIMITS DUE TO RECENT INCREASED PRECIPITATION AND A | | MALFUNCTIONING PUMP WHICH WON'T ALLOW THE LAGOON LEVEL TO BE DECREASED | | RESULTING IN OVERFLOW. PARTS FOR THE PUMP HAVE BEEN ORDERED. THE MEASURED | | VALUE WAS 16.3 MILLIGRAMS PER LITER AND THE NPDES LIMIT IS 15.0 MILLIGRAMS | | PER LITER. | | | | OVERFLOW FROM THE LAGOON FLOWS TO LITTLE BEAVER CREEK AND EVENTUALLY TO THE | | SCIOTO RIVER. THERE ARE NO HAZARDOUS MATERIALS OR RADIOACTIVE CONTAMINATION | | THREATS ASSOCIATED WITH THIS INCIDENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31987 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 17:41 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/13/96 | +------------------------------------------------+EVENT TIME: 00:00[MST]| |NRC NOTIFIED BY: STROUD |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING AN NRC SECURITY INSPECTION PERFORMED TODAY (03/20/97), IT WAS | | DETERMINED THAT A LOGGABLE EVENT ON 09/13/96, SHOULD HAVE BEEN | | CALLED/REPORTED TO THE NRC OPERATION CENTER. | | | | IT WAS DISCOVERED THAT A DOCUMENT CONTAINING SAFEGUARDS INFORMATION WAS NOT | | CONTROLLED IN ACCORDANCE WITH 10 CFR 73.71. THE INFORMATION IS POTENTIALLY | | SIGNIFICANT AND WAS DISCOVERED OUTSIDE THE PROTECTED AREA. THIS EVENT | | OCCURRED ON 09/13/96 AND WAS ENTERED AS A LOGGABLE EVENT REPORT. AN ONGOING | | INVESTIGATION BY THE REGION IV SECURITY INSPECTOR DETERMINED THAT THIS | | REPORT SHOULD HAVE BEEN CALLED INTO THE NRC OPERATION CENTER. THE NRC | | REGION IV SECURITY INSPECTOR WAS PROVIDED WITH DETAILS OF THE EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31988 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: THOMPSON |LAST UPDATE DATE: 03/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 28 POWER OPERATION | 28 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE TECHNICAL SPECIFICATION FOR MAXIMUM POWER LEVEL SETPOINT WITH | | INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION IS IN ERROR. | | | | THE PERCENT OF RATED THERMAL POWER LISTED IN TECHNICAL SPECIFICATION TABLE | | 3.7-1, "MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH | | INOPERABLE STEAM LINE SAFETY VALVES WHILE IN FOUR LOOP OPERATION", IS | | NON-CONSERVATIVE WHEN APPLIED TO THREE INOPERABLE MAIN STEAM SAFETY VALVES | | (MSSV) ON THE SAME LOOP. THE SUBJECT TECHNICAL SPECIFICATION ALLOWS | | CONTINUED OPERATION IN THIS CONDITION PROVIDED RATED THERMAL POWER IS | | REDUCED TO 43%. CALCULATIONS PREPARED IN SUPPORT OF AN ASSOCIATED PROPOSED | | AMENDMENT INDICATE THAT THE UNIT SHOULD BE SHUTDOWN WITH THREE MSSVs | | INOPERABLE ON THE SAME LOOP TO PREVENT OVERPRESSURIZATION OF THE MAIN STEAM | | SYSTEM. | | | | A LICENSEE EVENT REPORT WILL BE SENT TO THE NRC IN ACCORDANCE WITH | | 10CFR50.73 (a)(2)(ii). | | | | LICENSEE SAID THAT CATAWBA UNIT 1 AND 2 HAVE TECHNICAL SPECIFICATIONS WHICH | | ARE SIMILAR TO THE MCGUIRE TECHNICAL SPECIFICATIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31989 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/20/97 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 21:33 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 17:40[PST]| |NRC NOTIFIED BY: JOHN SIMS |LAST UPDATE DATE: 03/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BILL BATEMAN (NRR) EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |CEGIELSKI FEMA | |NLCO TECH SPEC LCO A/S |RICH BARRETT (IRD) AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 72 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENTERED TECHNICAL SPECIFICATION 3.0.3 AND TECHNICAL SPECIFICATION FOR PLANT | | SHUTDOWN AFTER PLANT STAFF CONCLUDED THAT SEVERAL SYSTEMS WERE NOT | | DEMONSTRATED TO MEET THEIR RESPONSE TIME REQUIREMENTS. | | | | ON MARCH 20, 1997 THE NRC INFORMED THE SUPPLY SYSTEM BY LETTER THAT WNP-2 | | TECHNICAL SPECIFICATION SURVEILLANCE RESPONSE TIME REQUIREMENTS WERE NOT | | BEING MET FOR CERTAIN INSTRUMENTATION. IT WAS CONCLUDED BY THE STAFF THAT | | THE REACTOR PROTECTION SYSTEM, PRIMARY CONTAINMENT ISOLATION SYSTEM AND | | EMERGENCY CORE COOLING SYSTEM INSTRUMENT TECHNICAL SPECIFICATION | | SURVEILLANCES WERE NOT DEMONSTRATED TO MEET RESPONSE TIME REQUIREMENTS. | | | | RESPONSE TIME LIMITS WERE NOT DEMONSTRATED BECAUSE SENSOR RESPONSE WAS NOT | | INCLUDED IN THE RESPONSE TIME MEASUREMENTS FOR ALL REQUIRED INSTRUMENT | | FUNCTIONS, OR PORTIONS OF THE INSTRUMENTATION WERE ONLY QUALITATIVELY | | VERIFIED TO RESPOND TO AN INPUT. | | | | THIS DETERMINATION WAS MADE FOLLOWING NRC REVIEW OF SUPPLY SYSTEM | | IMPLEMENTATION OF BWROG LICENSING TOPICAL REPORT NEDO-32291, "SYSTEM | | ANALYSIS FOR ELIMINATION OF SELECTED RESPONSE TIME TESTING REQUIREMENTS," | | AND ASSOCIATED 10 CFR50.59 IMPLEMENTATION. | | | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 AND TECHNICAL | | SPECIFICATION PLANT SHUTDOWN. ENTERING TECHNICAL SPECIFICATION PLANT | | SHUTDOWN AUTOMATICALLY PLACES THE LICENSEE IN AN UNUSUAL EVENT. | | | | THE STAFF'S DETERMINATION OF THE FAILURE TO PERFORM RESPONSE TIME TESTING | | RESULTED IN A SITUATION WHERE THE FUNCTIONAL CAPABILITY OF THE REACTOR | | PROTECTION SYSTEM, PRIMARY CONTAINMENT ISOLATION SYSTEM AND EMERGENCY CORE | | COOLING SYSTEM CANNOT BE ASSURED TO BE IN COMPLIANCE WITH THE REQUIRED | | TESTING METHODOLOGY. | | | | HOWEVER, THIS CONDITION IS LIMITED TO A PROCESS IMPLEMENTATION PROBLEM AND | | THE LICENSEE BELIEVES IT IS NOT A SAFETY CONCERN. QUALITATIVE TESTING HAS | | DEMONSTRATED COMPONENT FUNCTIONAL AND RESPONSE CAPABILITIES. A NOTICE OF | | ENFORCEMENT DISCRETION IS BEING REQUESTED. | | | | THE LICENSEE HAS NOTIFIED STATE AND COUNTY GOVERNMENT OF THEIR UNUSUAL | | EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 0142 EST FROM SIMS TAKEN BY KARSCH * * * | | THE LICENSEE TERMINATED THEIR UNUSUAL EVENT AT 2200 PST. THE LICENSEE WAS | | GRANTED ENFORCEMENT DISCRETION AND PLANT SHUTDOWN TERMINATED. THE LOWEST | | POWER REACHED WAS 40%. POWER WILL BE INCREASED TO 55%. A PRESS RELEASE | | WILL BE ISSUED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31990 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/21/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 03:23 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/21/97 | +------------------------------------------------+EVENT TIME: 03:00[EST]| |NRC NOTIFIED BY: RUTKOSKE |LAST UPDATE DATE: 03/21/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE BOUNDARY DOOR BETWEEN THE PIPING PENETRATION ROOM AND THE ELECTRICAL | | PENETRATION ROOM WAS FOUND IN THE OPEN POSITION. THE DOOR MAY HAVE BEEN | | LEFT OPEN FOR 20 MINUTES. WITH THE DOOR IN THE OPEN POSITION A HIGH ENERGY | | LINE BREAK IN THE PIPING PENETRATION ROOM WOULD SUBMIT THE ELECTRICAL | | PENETRATION ROOM TO A HARSH ENVIRONMENT, WHICH IS OUTSIDE ITS DESIGN BASIS. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+