U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/23/97 - 05/27/97 ** EVENT NUMBERS ** 32351 32381 32382 32383 32384 32385 32386 32387 32388 32389 32390 32391 32392 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32351 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 05/19/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 22:07 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/19/97 | +------------------------------------------------+EVENT TIME: 21:30[EDT]| |NRC NOTIFIED BY: GARY KILBY |LAST UPDATE DATE: 05/26/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND |AL CHAFFEE, NRR EO | | |VERN HODGE, RVIB NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAINMENT RECIRC FAN COOLER HEPA FILTERS CONTAIN ALUMINUM MATERIALS - | | | | WESTINGHOUSE INFO-GRAM #IG96005 ALERTED LICENSEES TO THE POSSIBILITY THAT | | PLANT PROCURED HEPA FILTERS FOR THE CONTAINMENT FAN COOLERS MAY CONTAIN | | ALUMINUM MATERIALS. HYDROGEN GAS COULD BE GENERATED BY THE CORROSION OF | | ALUMINUM IN THESE FILTERS DUE TO CONTAINMENT SPRAY IN A POST-LOCA | | ENVIRONMENT. | | | | THE LICENSEE DETERMINED THAT NINE HEPA PREFILTERS IN THE SEABROOK #CAH-F-8 | | CONTAINMENT STRUCTURE RECIRCULATION FAN COOLER UNITS CONTAINED ALUMINUM, | | AND THIS ALUMINUM WAS NOT ORIGINALLY CONSIDERED IN THE POST-ACCIDENT | | HYDROGEN REMOVAL SYSTEM SIZING ANALYSIS. SEABROOK UPDATED FINAL SAFETY | | ANALYSIS REPORT (UFSAR) TABLE 6.2-87 AND CALCULATION #4.3.16-13F DO NOT | | INCLUDE ANY ALUMINUM ALLOTMENT. | | | | THE LICENSEE PLANS TO REPLACE THE NINE 24-INCH BY 24-INCH BY 12-INCH | | PREFILTERS CONTAINING ALUMINUM PRIOR TO RESTARTING SEABROOK. | | | | THE LICENSEE ALSO PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 1204 MAY 26, 1997, UPDATE FROM LANCE FRITZ RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. IT WAS REPORTED THAT | | THE CONTAINMENT RECIRCULATION PREFILTERS CONTAINED APPROXIMATELY 1,576 | | SQUARE FEET OF ALUMINUM WHICH WAS NOT INCLUDED IN THE DESIGN BASIS ANALYSIS | | FOR THE COMBUSTIBLE GAS CONTROL SYSTEM AND WHICH EXCEEDED THE ALLOWABLE | | ALUMINUM CONTINGENCY SPECIFIED IN THE UFSAR BY 447.7 SQUARE FEET. THE | | LICENSEE HAS NOW DETERMINED THAT THE ACTUAL QUANTITY OF ALUMINUM ASSOCIATED | | WITH THE CONTAINMENT RECIRCULATION UNIT PREFILTERS IS WITHIN THE DESIGN | | BASIS FOR THE COMBUSTIBLE GAS CONTROL SYSTEM AND THE ALUMINUM CONTINGENCY | | SPECIFIED IN THE UFSAR. THE PREVIOUS REPORT WAS BASED ON ERRONEOUS | | INFORMATION THAT THE CONTAINMENT RECIRCULATION UNIT CONTAINED NINE | | PREFILTERS. THE ACTUAL NUMBER OF PREFILTERS IS THREE, AND THE ALUMINUM | | CONTENT ASSOCIATED WITH THE THREE PREFILTERS IS WITHIN THE ALUMINUM | | CONTINGENCY VALUE SPECIFIED IN THE UFSAR. | | | | THE LICENSEE PLANS TO REPLACE THE THREE PREFILTERS DURING THE ONGOING | | REFUELING OUTAGE. | | | | THE LICENSEE ALSO PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (BORES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32381 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/23/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 07:46 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/22/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/23/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE JORGENSEN RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: L.D. BOSHELL | | |HQ OPS OFFICER: HENRY BAILEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALARM AUDIBILITY OF THE C-310 BUILDING CRITICALITY ALARM SYSTEM WAS LOST | | FOR APPROXIMATELY 1 HOUR AND 20 MINUTES ON 5/18/97. | | | | ON 5/22/97 AT 1730, IT WAS DISCOVERED THAT ALARM AUDIBILITY OF THE C-310 | | (PURGE AND PRODUCT) BUILDING CRITICALITY ALARM SYSTEM (CAAS) WAS LOST FOR | | APPROXIMATELY 1 HOUR AND 20 MINUTES ON 5/18/97. THE DC POWER TRANSFER | | SWITCH IN C-310 FAILED ON 5/18/97. THE SWITCH PROVIDES THROW-OVER | | CAPABILITY WHICH ENABLES CRITICAL ALARM AND CONTROL CIRCUITS TO REMAIN IN | | SERVICE WHEN PRIMARY DC POWER IS LOST. BACK-UP POWER IS PROVIDED BY BANKS | | OF BATTERIES. AT THE TIME THE SWITCH FAILED, IT WAS NOT RECOGNIZED THAT | | POWER WAS LOST TO THE SOLENOID VALVES WHICH OPERATE THE CAAS ALARM HORNS. | | THE TSR REQUIRES THE CAAS TO BE OPERABLE, BOTH FOR DETECTION AND | | AUDIBILITY. WHILE POWER WAS LOST, THE AUDIBILITY FUNCTION WAS INOPERABLE. | | THE DETECTION FUNCTION WAS NOT AFFECTED. A REVIEW OF THE INCIDENT AND | | APPLICABLE DESIGN DOCUMENTS BY ENGINEERING PERSONNEL DETERMINED THAT THE | | CAAS FUNCTION WAS INOPERABLE FOR APPROXIMATELY 1 HOUR AND 20 MINUTES. | | | | PADUCAH PERSONNEL NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32382 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/23/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:07 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/23/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:25[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/23/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 | | +------------------------------------------------+ | |NRC NOTIFIED BY: RON CRABTREE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE # 5 ISOLATED DUE TO HIGH PRESSURE | | | | AT 0125 HOURS, AND 0130 HOURS, OPERATIONS PERSONNEL IN THE X-343 FEED AND | | SAMPLING FACILITY RECEIVED A URANIUM HEXAFLUORIDE CYLINDER HIGH PRESSURE | | ALARM ON AUTOCLAVE # 5. THE INITIAL ALARM AT 0125 HOURS ACTUATED (CLOSED) | | THE STEAM SUPPLY VALVE ON AUTOCLAVE # 5 AS REQUIRED BY TSR. THE CYLINDER | | WAS "BURPED" TO THE CASCADE TO RELIEVE THE EXCESS PRESSURE. WHEN THE | | CYLINDER WAS ISOLATED FROM THE EVACUATION HEADER, THE CYLINDER PRESSURE | | INCREASED A SECOND TIME, CAUSING THE SECOND ALARM AT 0130 HOURS EVEN THOUGH | | THE STEAM SUPPLY TO AUTOCLAVE # 5 WAS STILL ISOLATED FROM THE INITIAL ALARM | | ACTUATION. OPERATIONS PERSONNEL PERFORMED ANOTHER CYLINDER "BURP" TO THE | | CASCADE TO RELIEVE THE EXCESS PRESSURE FROM THE CYLINDER. CYLINDER PRESSURE | | STABILIZED AT 20 PSIA. AUTOCLAVE # 5 AND THE URANIUM HEXAFLUORIDE CYLINDER | | WERE DECLARED INOPERABLE, PENDING ENGINEERING EVALUATIONS TO ASSURE | | INTEGRITY OF THE AUTOCLAVE AND TO EVALUATE URANIUM HEXAFLUORIDE CYLINDER | | CONTENTS. THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL | | EXPOSURE ASSOCIATED WITH THIS "Q" SAFETY SYSTEM ACTUATION. | | | | THIS EVENT IS BEING REPORTED PER NUCLEAR REGULATORY EVENT REPORTING | | PROCEDURE UE2-RA-RE1030, APPENDIX D, SECTION J, SAFETY EQUIPMENT | | FAILURE/ACTUATION. | | | | THE CYLINDER HIGH PRESSURE ALARM IS CALIBRATED TO ACTUATE AT 115 PSIA (+ 5 | | PSIA FOR INSTRUMENT DRIFT). THE HIGHEST PRESSURE OBSERVED DURING THIS EVENT | | WAS 130 PSIA. THE MAXIMUM ALLOWABLE WORKING PRESSURE OF THE CYLINDER | | INVOLVED IS 200 PSIG. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32383 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 05/23/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/23/97 | +------------------------------------------------+EVENT TIME: 16:20[CDT]| |NRC NOTIFIED BY: EDWARD R. LAMKEN |LAST UPDATE DATE: 05/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |LEE SPESSARD EO | |NLCO TECH SPEC LCO A/S |RICHARD BARRETT IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED SHUTDOWN COMMENCED AFTER DECLARING BOTH HIGH HEAD | | INJECTION PUMPS INOPERABLE. | | | | UNIT 1 ENTERED A 24 HOUR TS 4.0.3 GRACE PERIOD AT 1900CDT ON 5/22/97 FOR A | | MISSED SURVEILLANCE ON BOTH HIGH HEAD (CV) INJECTION PUMPS. A RECENT NRC | | INSPECTION FINDING NOTED THAT THESE PUMPS WERE NOT VENTED BY SURVEILLANCE | | 1BOS5.2.B-1 (ECCS VENTING) AS REQUIRED PER TS LCO 3.5.2. SINCE THESE PUMPS | | OPERATE AT 2600 PSI AND ARE DIFFICULT TO VENT, THE LICENSEE ANTICIPATES | | COMPLETING A UNIT 1 SHUTDOWN AND ENTERING MODE 5 PENDING LONG TERM | | CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1829EDT 5/23/97 FROM LAMKEN TO S.SANDIN * * * | | | | AT 1740EDT BOTH BYRON UNITS 1 AND 2 AND BRAIDWOOD UNIT 2 WERE GRANTED | | ENFORCEMENT DISCRETION (NOED) FOR THE MISSED SURVEILLANCE TO VENT THE HIGH | | HEAD INJECTION PUMPS. BYRON UNIT 1 HAS TERMINATED THEIR SHUTDOWN AND WILL | | BEGIN RAMPING UP TO 97% POWER. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. NOTIFIED R3DO(JORGENSEN) AND EO(SPESSARD). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32384 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 05/23/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:50 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/23/97 | +------------------------------------------------+EVENT TIME: 10:40[CDT]| |NRC NOTIFIED BY: TOM MATTHEWS |LAST UPDATE DATE: 05/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE (VIA FAX) NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 IS MAKING A PART 21 NOTIFICATION REGARDING DEFECTIVE RAW WATER | | PUMP IMPELLERS. | | | | THE LICENSEE IDENTIFIED THAT THE REPLACEMENT IMPELLERS FOR BYRON JACKSON | | RAW WATER PUMPS HAD BLADE DIMENSIONS OUT OF TOLERANCE. AN ENGINEERING | | EVALUATION OF THE DIMENSIONAL INACCURACIES DETERMINED THAT PUMP DISCHARGE | | FLOWS USING THESE IMPELLERS WOULD NOT SATISFY ACCEPTANCE CRITERIA AND COULD | | POSE A SUBSTANTIAL SAFETY HAZARD UNDER CERTAIN CIRCUMSTANCES. THIS PROBLEM | | WAS INITIALLY IDENTIFIED ON 4/8/97. ONE OF THE IMPELLERS WAS INSTALLED AND | | SUBSEQUENTLY REMOVED FROM RAW WATER PUMP ASSEMBLY AC-10D WHICH FAILED POST | | MAINTENANCE TESTING. BOTH DEFECTIVE IMPELLERS WERE RETURNED TO THE | | SUPPLIER. THE LICENSEE DOES NOT KNOW IF OTHER FACILITIES ARE AFFECTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32385 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/23/97 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 19:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/23/97 | +------------------------------------------------+EVENT TIME: 15:03[CDT]| |NRC NOTIFIED BY: TIM CLOUSER |LAST UPDATE DATE: 05/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE TEXAS NATURAL RESOURCE CONSERVATION COUNCIL | | (TNRCC) OF A POSSIBLE UNDERGROUND LUBE OIL LINE LEAK. | | | | "SITE ENVIRONMENTAL PERSONNEL HAVE CONTACTED THE TNRCC AT 1503 TODAY | | REGARDING A POSSIBLE LEAK IN A SMALL UNDERGROUND LUBE OIL STORAGE TANK | | ASSOCIATED WITH UNIT ONE. THE LEAK IS VERY SMALL AND EFFORTS TO POSITIVELY | | IDENTIFY THE SOURCE AND CAUSE ARE ONGOING." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32386 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/24/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/23/97 | +------------------------------------------------+EVENT TIME: 23:49[CDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 05/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSEN RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MINIMUM SECURITY PERSONNEL STAFFING REQUIREMENTS NOT MET DUE TO FITNESS FOR | | DUTY ISSUE WITH ONE MEMBER OF THE SECURITY STAFF. A REPLACEMENT SECURITY | | STAFF MEMBER HAS BEEN CONTACTED, AND IS EN ROUTE TO THE SITE. REFER TO HOO | | LOG FOR ADDITIONAL DETAILS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32387 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/25/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 00:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/24/97 | +------------------------------------------------+EVENT TIME: 23:46[CDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 05/25/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DURING UNIT STARTUP DUE TO ROD SEQUENCING ERROR | | | | WHILE WITHDRAWING CONTROL RODS IN PREPARATION FOR DILUTION TO CRITICALITY, | | UNIT 1 WAS MANUALLY TRIPPED DUE TO A ROD SEQUENCING ERROR BETWEEN CONTROL | | BANKS 'C' AND 'D'. THE REACTOR WAS SUBCRITICAL AT THE TIME OF THE EVENT, | | AND ALL CONTROL RODS INSERTED FOLLOWING THE TRIP. THE LICENSEE REPORTED | | THAT RODS IN BANK 'C' STOPPED WITHDRAWING AT 218 STEPS (FULLY WITHDRAWN IS | | 228 STEPS), WHILE RODS IN BANK 'D' CONTINUED TO WITHDRAW. THE LICENSEE | | SUSPECTS A BANK OVERLAP PROBLEM. | | | | AT THE TIME OF THE EVENT, PROCEDURE BWVS 500-4, "INITIAL CRITICALITY AFTER | | REFUELING OUTAGE AND NUCLEAR HEATING LEVEL," WAS IN PROGRESS. THE NRC | | RESIDENT INSPECTOR WAS IN THE CONTROL ROOM DURING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32388 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 05/25/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 07:37 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/25/97 | +------------------------------------------------+EVENT TIME: 04:55[EDT]| |NRC NOTIFIED BY: ABBOTT |LAST UPDATE DATE: 05/25/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 70 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM TO ENTER OUTAGE AND REPAIR FAILED #3 TURBINE CONTROL | | VALVE | | | | AT 1327 ON 5/24/97, TURBINE CONTROL VALVE #3 FAILED FULLY OPEN. THE | | LICENSEE INVESTIGATED, AND DETERMINED THAT THE LINKAGE BETWEEN THE VALVE | | AND ITS ACTUATOR HAD BEEN DAMAGED. ATTEMPTS TO CLOSE THE VALVE WERE | | UNSUCCESSFUL, AND THE LICENSEE BEGAN MAKING PLANS TO SHUT DOWN THE UNIT TO | | MAKE REPAIRS. IN ORDER MAINTAIN PRESSURE CONTROL DURING THE SHUTDOWN, THE | | LICENSEE DECIDED TO SCRAM THE REACTOR AND IMMEDIATELY TRIP THE MAIN | | TURBINE. | | | | AT O455 EDT, OPERATORS MANUALLY SCRAMMED THE REACTOR FROM 70% POWER, AND | | INITIATED A TURBINE TRIP. ALL CONTROL RODS INSERTED PROPERLY, AND ALL | | SYSTEMS FUNCTIONED AS EXPECTED. FOLLOWING THE SCRAM, REACTOR VESSEL WATER | | LEVEL MOMENTARILY DECREASED TO LESS THAN 177" ABOVE THE TOP OF ACTIVE FUEL, | | CAUSING A PCIS GROUP 2 ISOLATION. THIS CAUSED THE REACTOR WATER CLEANUP AND | | CONTAINMENT SAMPLING SYSTEMS TO ISOLATE, AND STARTED THE STANDBY GAS | | TREATMENT SYSTEM. REACTOR VESSEL WATER LEVEL WAS IMMEDIATELY RECOVERED. AT | | 0502, THE SCRAM SIGNAL WAS RESET, AND BY 0543, ALL CONTAINMENT ISOLATION | | SIGNALS AND VALVES WERE RESTORED TO NORMAL. | | | | THE LICENSEE PLANS TO TAKE THE UNIT TO COLD SHUTDOWN TO REPAIR THE #3 | | TURBINE CONTROL VALVE, AS WELL AS TO PERFORM OTHER ASSORTED MAINTENANCE. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32389 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. STEEL |NOTIFICATION DATE: 05/25/97 | | CITY: GARY REGION: 3 |NOTIFICATION TIME: 10:50 [ET]| | COUNTY: LAKE STATE: IN |EVENT DATE: 05/24/97 | |LICENSE#: GA 458-3G AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/25/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JORGENSEN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BRIAN KUNKLE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |FFFF 20.402 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED INDUSTRIAL THICKNESS GAUGE | | | | ON 5/24/97, AN NDS MODEL 200 THICKNESS GAUGE, CONTAINING 2.001 Ci OF | | Am-241, WAS DAMAGED WHEN IT WAS STRUCK. THE GAUGE IS USED TO MEASURE THE | | THICKNESS OF A GALVANIZED COATING APPLIED TO ROLLED STEEL. THE STRIP OF | | METAL IN THE PROCESS LINE BUCKLED AND STRUCK THE GAUGE, KNOCKING IT FROM | | ITS SUPPORT, AND DAMAGING THE MYLAR WINDOW ON THE HOUSING THAT COVERS THE | | SHUTTER MECHANISM. | | | | THE MILL WAS SHUT DOWN AND PERSONNEL WERE EVACUATED FROM THE AREA WHILE THE | | GAUGE WAS SURVEYED AND THEN REMOVED TO A SECURE SHIELDED STORAGE AREA. THE | | LICENSEE PLANS TO CONTACT NRC REGION 3 REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32390 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 05/25/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 14:34 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/25/97 | +------------------------------------------------+EVENT TIME: 13:25[CDT]| |NRC NOTIFIED BY: MIKE GALLE |LAST UPDATE DATE: 05/25/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS DECKER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 IDENTIFIED SEVERAL MOV CONTROL POWER WIRING DISCREPANCIES WHICH | | COULD POTENTIALLY AFFECT THEIR ABILITY TO REMOTELY OPERATE THESE VALVES | | FROM THE HOT SHUTDOWN PANEL. | | | | "WHILE UNIT 2 WAS AT 100% POWER, AT 1325CDT ON 5/25/97, THE EXISTENCE OF A | | CONDITION THAT IS OUTSIDE THE DESIGN BASIS OF THE PLANT WAS IDENTIFIED IN | | THAT THE CONTROL CIRCUIT FOR MOV-8000A (PORV BLOCK VALVE) IS WIRED WITH THE | | CONTROL POWER FUSES FOR LOCAL AND REMOTE OPERATION CONNECTED IN SERIES. | | WITH THIS ARRANGEMENT, FAILURE OF THE FUSE FOR REMOTE (MAIN CONTROL BOARD) | | OPERATION WOULD PREVENT LOCAL (HOT SHUTDOWN PANEL) OPERATION. THIS | | CONDITION POTENTIALLY EXISTS FOR FOUR OTHER MOV's." | | | | THE CAUSE IS ATTRIBUTED TO PERSONNEL ERROR WHILE IMPLEMENTING A DESIGN | | CHANGE IN 1995. THE CONTROL CIRCUIT WAS NOT WIRED PER DESIGN. CORRECTIVE | | ACTIONS INCLUDE REWIRING THE CONTROL CIRCUIT TO CONFORM WITH PLANT DESIGN | | (IN PROGRESS) AND INSPECTING/REPAIRING FOUR OTHER POTENTIALLY AFFECTED | | MOV's, i.e., MOV-8000B (PORV BLOCK VALVE), LCV-115-B, D (RWST-CHARGING PUMP | | SUCTION VALVES) AND T1P17-MOV-3047 (CCW-MISCELLANEOUS HEADER ISOLATION | | VALVE). | | | | UNIT 2 HAS DECLARED MOV-8000A INOPERABLE AND ENTERED TECH SPEC 3.4.5 ACTION | | STATEMENT D WHICH REQUIRES THAT WITH ONE BLOCK VALVE INOPERABLE WITHIN 1 | | HOUR RESTORE THE BLOCK VALVE TO OPERABLE STATUS OR PLACE ITS ASSOCIATED | | PORV IN MANUAL CONTROL AND RESTORE THE INOPERABLE BLOCK VALVE TO OPERABLE | | STATUS WITHIN 72 HOURS OR BE WITHIN AT LEAST HOT STANDBY WITHIN THE NEXT 6 | | HOURS AND HOT SHUTDOWN WITHIN THE FOLLOWING 6 HOURS. THE LICENSEE IS | | MAKING REPAIRS WITH MOV-8000A IN THE OPEN POSITION AND WILL CONTINUE | | OPERATING AT 100% POWER. AT LEAST ONE VALVE WAS IDENTIFIED ON UNIT 1 IN A | | SIMILAR CONDITION; HOWEVER, SINCE UNIT 1 IS CURRENTLY IN MODE 5, THIS | | CONDITION IS NOT REPORTABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32391 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/26/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:17 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/26/97 | +------------------------------------------------+EVENT TIME: 09:46[CDT]| |NRC NOTIFIED BY: KEVIN CRAVENS |LAST UPDATE DATE: 05/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED OPENING OF THE DRYWELL VACUUM BREAKERS WHEN A DRYWELL/TORUS | | PURGE FAN WAS STARTED (THIS EVENT IS SIMILAR TO AN EVENT THAT OCCURRED ON | | MAY 22, 1997. REFER TO EVENT #32376 FOR ADDITIONAL INFORMATION.) | | | | WHEN THE 2A DRYWELL/TORUS PURGE FAN WAS STARTED IN ORDER TO INITIATE | | DRYWELL PURGING AND VENTING, THE TORUS TO DRYWELL VACUUM BREAKERS OPENED. | | DRYWELL PRESSURE DROPPED SLIGHTLY (0.1 TO 0.2 PSIG) WHILE THE PURGE FAN WAS | | RUNNING. (THE DRYWELL-TORUS VACUUM BREAKERS ARE DESIGNED TO OPEN ON A | | TORUS PRESSURE 0.5 PSIG GREATER THAN DRYWELL PRESSURE.) THE LICENSEE | | IMMEDIATELY SHUT DOWN THE DRYWELL/TORUS PURGE FAN, AND THE VACUUM BREAKERS | | RECLOSED. | | | | AN INVESTIGATION REGARDING THE SETPOINT OF THE TORUS TO DRYWELL VACUUM | | BREAKERS IS CURRENTLY IN PROGRESS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32392 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/26/97 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 15:57 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/26/97 | +------------------------------------------------+EVENT TIME: 13:46[CDT]| |NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 05/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FULL SCRAM SIGNAL RECEIVED DUE TO PERSONNEL ERROR DURING REACTOR PROTECTION | | SYSTEM (RPS) LOGIC TESTING | | | | WITH THE UNIT IN A REFUELING OUTAGE AND THE RPS ENERGIZED, A FULL SCRAM | | SIGNAL WAS RECEIVED WHILE INSTRUMENT MAINTENANCE DEPARTMENT PERSONNEL WERE | | PERFORMING AN RPS LOGIC SYSTEM FUNCTIONAL TEST. ONE OF THE TECHNICIANS | | PERFORMING THE SURVEILLANCE INADVERTENTLY PLACED THE AVERAGE POWER RANGE | | MONITOR (APRM) #1 MODE SWITCH IN THE 'POWER' POSITION (MODE SWITCH OUT OF | | OPERATE) INSTEAD OF THE APRM #5 MODE SWITCH. A HALF SCRAM ALREADY EXISTED | | IN CHANNEL 'B' AS PART OF THE SURVEILLANCE. BY TAKING THE MODE SWITCH OUT | | OF OPERATE ON APRM #1, RPS CHANNEL 'A' TRIPPED CAUSING A FULL SCRAM WHEN | | THE THE ONE-OUT-OF-TWO-TAKEN-TWICE LOGIC WAS SATISFIED. | | | | THE LICENSEE ATTRIBUTED THIS EVENT TO PERSONNEL ERROR. ALL SYSTEMS | | FUNCTION AS REQUIRED. THERE WAS NO ROD MOTION BECAUSE THE CONTROL RODS | | WERE ALREADY INSERTED. THERE WERE NO ENGINEERED SAFETY FEATURE ACTUATIONS, | | AND THE UNIT DID NOT ENTER ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS | | FOR OPERATION AS A RESULT OF THIS EVENT. CORE RELOAD ACTIVITIES, WHICH | | WERE IN PROGRESS AT THE TIME OF THIS EVENT, HAVE BEEN SUSPENDED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+