U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/29/96 - 04/01/96 ** EVENT NUMBERS ** 29521 29999 30022 30197 30198 30199 30200 30201 30202 30203 30204 30205 30206 30207 30208 30209 30210 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29521 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WHITLOCK DALRYMPLE POSTON & ASSO |NOTIFICATION DATE: 10/29/95 | | CITY: MANASSAS REGION: 2 |NOTIFICATION TIME: 20:36 [ET]| | COUNTY: STATE: VA |EVENT DATE: 10/28/95 | |LICENSE#: 45-19018-01 AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/29/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RONALD BELLAMY, R1 RDO | | |JOHN HICKEY, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CARLIN HALL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |ELOS 39.77(b) THEFT/LOSS OF RAD MAT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TROXLER SOIL MOISTURE DENSITY GAUGE STOLEN FROM WILKES BARRE, PA SITE - | | | | CARLIN HALL OF WHITLOCK, DALRYMPLE, POSTON & ASSOCIATES, A CONSULTANT | | ENGINEERING FIRM LOCATED IN MANASSAS, VA, REPORTED THAT AN UNDAMAGED | | TROXLER SOIL MOISTURE DENSITY GAUGE WAS STOLEN FROM A CONSTRUCTION TRAILER | | AT A PRINTING PLANT CONSTRUCTION SITE NEAR WILKES BARRE, PA, SOMETIME | | BETWEEN FRIDAY EVENING (10/27/95) AND SATURDAY MORNING (10/28/95). | | | | THE 45-POUND, LOCKED, 40"x20"x12", TRANSPORT CASE CONTAINS A 20"x15"x7" | | GAUGE WITH 7.8 æCi CS-137 AND 40 æCi AM-241/BE SEALED SOURCES (MODEL | | #3411B, SERIAL #12329). | | | | LICENSEE NOTIFIED THE PENNSYLVANIA OFFICE OF EMERGENCY MANAGEMENT AND THE | | WILKES BARRE POLICE DEPARTMENT (CASE #J289548), WHO ISSUED A PRESS RELEASE. | | | | R1DO PLANS TO NOTIFY R1PAO AND R2. | | | | SEE HOO LOG FOR TELEPHONE NUMBERS. | | | | ***UPDATE ON 3/29/96 @ 10:24 BY HALL TO GOULD***THE LICENSEE REPORTED THAT | | THE TRANSPORT CASE FOR THE STOLEN TROXLER GAUGE WAS FOUND IN THE | | SUSQUEHANNA RIVER, BY A FISHERMAN, SOUTH OF NANICOKE PA. THE GAUGE WAS NOT | | IN THE CASE. A SURVEY OF THE CASE SHOWED IT TO BE SLIGHTLY ABOVE | | BACKGROUND. NOTIFIED REG 1(NICHOLSON), NMSS EO(COMBS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29999 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/20/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 18:18[EST]| |NRC NOTIFIED BY: BECKER |LAST UPDATE DATE: 03/29/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |BRUCE BOGER EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY AFTER HIGH PRESSURE SAFETY INJECTION | | (HPSI) SYSTEM WAS DECLARED INOPERABLE DUE TO POTENTIAL CLOGGING OF THE HPSI | | THROTTLE VALVES DURING THE CONTAINMENT SUMP RECIRCULATION PHASE (REFER TO | | EVENT #30008 FOR ADDITIONAL INFORMATION.) | | | | DURING REVIEW OF A PACIFIC GAS AND ELECTRIC OPERATIONAL EXPERIENCE REPORT | | CONCERNING POTENTIAL CLOGGING OF THE EMERGENCY CORE COOLING SYSTEM THROTTLE | | VALVES, MILLSTONE DETERMINED THAT ITS UNIT 2 HPSI VALVES 2-SI-616, | | 2-SI-626, 2-SI-636, 2-SI-646, 2-SI-617, 2-SI-627, 2-SI-637, AND 2-SI-647 | | ARE SUSCEPTIBLE TO SIMILAR CLOGGING. THIS IS BASED ON THE FOLLOWING: 1) | | THE CONTAINMENT SUMP SCREEN OPENING IS 0.187" AND 2) THE HPSI INJECTION | | VALVES' OPENINGS ARE 0.125" AT THE SEAT-TO-PLUG INTERFACE AND HAVE 4 | | ISOSCELES TRIANGLE SHAPED OPENINGS WITH A MAXIMUM DIMENSION OF 0.187". | | THUS, THE VALVE WILL NOT ALLOW FOREIGN MATERIAL PARTICLES OF 0.187" | | DIAMETER TO PASS. THIS POTENTIAL CLOGGING COULD RESULT IN A PARTIAL OR | | COMPLETE LOSS OF POST-ACCIDENT HPSI CORE COOLING FLOW. | | | | BASED ON THIS POTENTIAL PLUGGING, TECHNICAL SUPPORT PERSONNEL DETERMINED | | THAT THE HPSI THROTTLE VALVES ARE SUBJECT TO A COMMON MODE FAILURE | | (PLUGGING AND LOSS OF CORE COOLING FLOW) AND SHOULD BE CONSIDERED | | INOPERABLE PENDING COMPLETION OF FURTHER STUDIES AND/OR REPAIRS. THE | | LICENSEE DECLARED THE HPSI PUMPS INOPERABLE AND ENTERED TECHNICAL | | SPECIFICATION 3.0.3 WHICH REQUIRES THE UNIT TO BE IN A HOT SHUTDOWN | | CONDITION WITHIN 6 HOURS AND A COLD SHUTDOWN CONDITION WITHIN THE FOLLOWING | | 24 HOURS. UNIT 2 SHOULD BE SHUT DOWN BY 2300. ALL OTHER EMERGENCY CORE | | COOLING SYSTEMS ARE FULLY OPERABLE, THE EMERGENCY DIESEL GENERATORS ARE | | OPERABLE, AND THE ELECTRICAL GRID IS STABLE. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND PLANS TO MAKE A PRESS | | RELEASE. THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1524 ON FEBRUARY 22, 1996, FROM BAKER TAKEN BY WEAVER * * * | | | | THE LICENSEE CONFIRMED THAT THE SUMP SCREEN MESH SIZE IS OUTSIDE OF THE | | DESIGN BASIS. THE SCREEN HAS HOLES 0.187" SQUARE AND 0.240" SQUARE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE APPROPRIATE STATE | | AND LOCAL OFFICIALS. THE HOO NOTIFIED THE R1DO (MEYER). | | | | NOTE: SEE EVENT #30022 FOR A RELATED EVENT. | | | | * * * UPDATE AT 1713 EST ON 03/29/96 FROM BERGIN TAKEN BY KARSCH * * * | | | | THE LICENSEE HAS DETERMINED THE FOLLOWING: 1. THE ORIGINAL DESIGN OF THE | | CONTAINMENT SUMP SCREEN IS SUFFICIENT TO ENSURE THERE IS NO PLUGGING OF THE | | HPSI VALVES, AND IS WITHIN THE DESIGN BASIS. 2. THE SCREENS AS INSTALLED | | DO NOT MEET THE DESIGN REQUIREMENTS. OPENINGS IN THE MESH EXCEEDING 0.25" | | SQUARE EXIST AND THERE ARE OTHER LARGER GAPS. 3. THESE GAPS WOULD ALSO | | RENDER THE CONTAINMENT SPRAY SYSTEM INOPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R1DO | | NICHOLSON. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30022 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/23/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 17:35 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/23/96 | +------------------------------------------------+EVENT TIME: 17:19[EST]| |NRC NOTIFIED BY: TED DUBAY |LAST UPDATE DATE: 03/29/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DEGRADED RHR CAPABILITY | | | | THE LICENSEE DISCOVERED THAT THE RWST WOULD EMPTY SOONER THAN PREVIOUSLY | | THOUGHT. THE DISCOVERY WAS MADE AS PART OF THE REVIEW INITIATED BY | | EVENT #29999. DURING A LARGE BREAK LOCA, THE RWST WOULD EMPTY IN 24 VERSUS | | 36 MINUTES. THE LOW HEAD SAFETY INJECTION PUMPS WOULD BE SECURED AT THIS | | TIME. THE SHORTER TIME FRAME RESULTS IN THE NECESSITY TO SWITCH OVER TO | | THE RECIRCULATION MODE SOONER WHEN DECAY HEAT IS HIGHER. | | | | POSTULATING A SINGLE FAILURE OF A HIGH HEAD SAFETY INJECTION PUMP, THE | | LICENSEE IS REVIEWING THE ADEQUACY OF THE REMAINING HIGH HEAD PUMP TO | | PROVIDE CORE COOLING. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. APPROPRIATE STATE AND | | LOCAL OFFICIALS HAVE BEEN NOTIFIED. | | | | * * * UPDATE AT 1713 EST ON 3/29/96 FROM BERGIN TAKEN BY KARSCH * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THEY HAVE DETERMINED THAT | | SUFFICIENT HEAT REMOVAL EXISTS TO MEET THE DESIGN REQUIREMENTS FOR SUMP | | RECIRCULATION. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R1DO | | (NICHOLSON) NOTIFIED BY THE HOO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 30197 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 03/29/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 09:03 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 03/28/96 | | LEU FABRICATION |EVENT TIME: 11:30[EST]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 03/29/96 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |GEORGE AL BELISLE RDO | | DOCKET: 07001113 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LON E. PAULSON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 24-HOUR REPORT REGARDING A LOSS OF GEOMETRY CONTROL (UO2 | | POWDER SPILL) RESULTING FROM A BLENDER INSPECTION PORT LOCKING PIN FAILURE. | | | | AT APPROXIMATELY 1130 ON MARCH 28, 1996, THERE WAS A POWDER SPILL AT THE | | HIGH ENRICHMENT ROTARY SLAB BLENDER. A BLENDER INSPECTION PORT DOOR | | LOCKING PIN FAILED RESULTING IN POWDER SPILLING ONTO THE FLOOR. A BLENDING | | OPERATION AT 4.9% ENRICHMENT HAD JUST BEEN COMPLETED, AND MATERIAL | | DISCHARGE OPERATIONS WERE UNDERWAY WHEN THE PIN FAILURE OCCURRED. THE | | TOTAL AMOUNT OF SPILLAGE WAS DETERMINED TO BE 103.4 KGS UO2 POWDER, AND THE | | TOTAL BATCH SIZE WAS 531 KGS UO2 AT 4.9% ENRICHMENT. ALL POWDER CONTAINED | | LESS THAN 1,000 PPM WATER EQUIVALENT, AND THE LIMIT WAS 50,000 PPM WATER | | EQUIVALENT. | | | | GEOMETRY CONTROL (ó5-1/8" THICK SLAB) ON THE BLENDER WAS TEMPORARILY LOST | | WHEN THE UO2 POWDER SPILLED ONTO THE FLOOR. THE SECOND CONTROL ON | | MASS/MODERATION (ó565 KGS UO2 AT ó50,000 PPM WATER EQUIVALENT) REMAINED | | INTACT, AND THE POWDER WAS CONFIRMED TO BE 'DRY'. MULTIPLE FAILURE MODES | | WOULD BE REQUIRED BEFORE A CRITICALITY EXCURSION WAS POSSIBLE. THEREFORE, | | NO UNSAFE CONDITION EXISTED. | | | | OPERATORS PROMPTLY REMOVED AND VACUUMED THE MATERIAL INTO SAFE GEOMETRY | | CONTAINERS ACCORDING TO PROCEDURE, AND THE TWO CONTROLS OF GEOMETRY AND | | MASS/MODERATION WHICH ARE REQUIRED FOR DOUBLE CONTINGENCY WERE | | REESTABLISHED BY 1200 (WITHIN THE 4-HOUR CRITERIA). THE HIGH ENRICHMENT | | BLENDER OPERATION WAS SHUTDOWN PENDING AN INVESTIGATION AND IMPLEMENTATION | | OF CORRECTIVE ACTIONS. THE LICENSEE'S CORRECTIVE ACTIONS INCLUDED THE | | REPLACEMENT OF ALL PINS WITH AN IMPROVED DESIGN. | | | | ONE INDIVIDUAL DID RECEIVE A SLIGHT SKIN CONTAMINATION WHICH WAS LESS THAN | | THE MINIMUM DETECTABLE ALLOWABLE (MDA) VALUE. THE LUNG COUNTS AND NASAL | | SMEARS WERE NEGATIVE, SO THERE WAS NO INTAKE. THE MINOR SKIN CONTAMINATION | | WAS PROMPTLY CLEANED OFF WHEN THE INDIVIDUAL'S FACE WAS WASHED. | | | | THE LICENSEE PLANS TO NOTIFY THE STATE OF NORTH CAROLINA (BROWN) AND THE | | NRC REGION 2 OFFICE (DECKER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MALLINCKRODT MEDICAL |NOTIFICATION DATE: 03/29/96 | | CITY: MARYLAND HEIGHT REGION: 3 |NOTIFICATION TIME: 15:09 [ET]| | COUNTY: ST LOUIS STATE: MO |EVENT DATE: 03/01/96 | |LICENSE#: 24-04206-01 AGREEMENT: N |EVENT TIME: 00:00[CST]| | DOCKET: |LAST UPDATE DATE: 03/29/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEWIS MILLER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DAN RIEMER | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MALLINCKRODT MEDICAL, MARYLAND HEIGHTS, MISSOURI. | | | | A MOLYBDENUM/TECHNETIUM GENERATOR WAS DETERMINED TO BE MISSING ON MARCH 1, | | 1996. AS A RESULT OF DISCUSSIONS WITH REGION 3, THE LICENSEE DETERMINED | | THAT THEY MADE A MATH ERROR IN THE ACTIVITY CALCULATION AND THIS EVENT | | SHOULD HAVE BEEN REPORTED AT THE TIME THE LOSS WAS DISCOVERED. AT THE TIME | | OF THE LOSS THE GENERATOR'S ACTIVITY WAS 425 mCi WITH A 66 HOUR HALF LIFE. | | THE GENERATOR WAS NEVER RECEIVED BY THE CUSTOMER, AND THE LICENSEE SUSPECTS | | THAT THE GENERATOR GOT MIXED IN WITH RETURN/RECYCLED GENERATORS AND IS | | SITTING AT THE SHIPPERS DECAY FACILITY. THE ACTIVITY LEVEL OF THE | | GENERATOR AS OF TODAY IS 398 MICRO Ci. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30199 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/29/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 15:13 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/29/96 | +------------------------------------------------+EVENT TIME: 14:20[EST]| |NRC NOTIFIED BY: JOE WALDMAN |LAST UPDATE DATE: 03/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |DTHR 73.71(c) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - | | | | THE LICENSEE DETERMINED THAT THE VEHICLE BARRIER SYSTEM IN PLACE WOULD NOT | | DEFEAT THE DESIGN BASIS VEHICLE. COMPENSATORY MEASURES WERE PUT IN PLACE | | AT 1425 EST. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30200 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CENTRO DE MEDICINA NUCLEAR |NOTIFICATION DATE: 03/29/96 | | CITY: GUAYAMA REGION: 2 |NOTIFICATION TIME: 15:22 [ET]| | COUNTY: STATE: PR |EVENT DATE: 03/24/96 | |LICENSE#: 52-25127-01 AGREEMENT: N |EVENT TIME: 00:00[AT ]| | DOCKET: |LAST UPDATE DATE: 03/29/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GEORGE AL BELISLE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SANTIAGO GOMEZ | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CENTRO DE MEDICINA NUCLEAR, GUAYAMA, PUERTO RICO. | | TEN DECAYED MOLYBDENUM-99/TECHNETIUM-99m GENERATORS STOLEN. | | | | ON MARCH 24, 1996, TEN SPENT GENERATORS WERE STOLEN FROM THE LICENSEE'S | | DECAY ROOM AT THEIR FACILITY IN GUAYAMA, PUERTO RICO. THE NEWEST SOURCE | | HAD AN ACTIVITY OF 50 mCi. THE COMBINED TOTAL ACTIVITY FOR ALL TEN SOURCES | | IS LESS THAN 100 mCi. THIS EVENT WAS PREVIOUSLY REPORTED TO REGION 2, AND | | PNO-II-96-022 WAS ISSUED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30201 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 03/29/96 | |UNIT: [ ] [4] [ ] STATE: FL |NOTIFICATION TIME: 15:32 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 03/29/96 | +------------------------------------------------+EVENT TIME: 13:40[EST]| |NRC NOTIFIED BY: TOM WOGAN |LAST UPDATE DATE: 03/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 4 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY INJECTION (SI) ACTUATION DUE TO HUMAN ERROR. | | | | DURING PREPARATIONS FOR STEAM GENERATOR TESTING, AN I&C TECH INADVERTENTLY | | INSERTED TWO PRESSURE SIGNALS WHICH ALLOWED THE AUTOMATIC UNBLOCKING OF SI | | ENGINEERED SAFETY FEATURES (ESF) SIGNALS. BECAUSE UNIT 4 IS SHUT DOWN, | | MAIN STEAM LINE DELTA P (PRESSURE DIFFERENCE BETWEEN STEAM LINES EXCEEDING | | THE SET POINT) SIGNALS WERE IN PLACE. THIS ACTUATED THE SI ESF LOGIC | | CAUSING START OF THE SI PUMPS, START OF THE EMERGENCY DIESEL GENERATORS, | | START OF THE COMPONENT COOLING WATER SYSTEM IN EMERGENCY MODE, AND A PHASE | | "A" CONTAINMENT ISOLATION. NO INJECTION TO THE REACTOR VESSEL TOOK PLACE | | BECAUSE THE INJECTION VALVES WERE CLOSED. THE ESF SYSTEMS WERE RESTORED TO | | NORMAL OPERATING MODE IN 20 TO 30 MINUTES. PLANT RESPONSE TO THE SI ESF | | ACTUATION WAS AS EXPECTED WITH RESPECT TO EQUIPMENT AVAILABILITY. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 03/29/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:24 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 03/29/96 | +------------------------------------------------+EVENT TIME: 10:56[EST]| |NRC NOTIFIED BY: DAVE PIETROSKI |LAST UPDATE DATE: 03/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 +------------------------------------------------------------------------------+ | DISCREPANCY BETWEEN TECH SPECS AND PROCEDURES. | | | | THE LOW VOLTAGE ALARM SET POINT FOR THE "C" 125 VDC DISTRIBUTION CENTER HAS | | A TECH SPEC REQUIREMENT OF 115 +/- 1 VDC. THE LICENSEE'S PROCEDURE HAS 120 | | +/- 1 VDC. THE PROCEDURE WILL BE CHANGED TO COMPLY WITH THE TECH SPEC | | REQUIREMENT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30203 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/29/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 19:50 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/29/96 | +------------------------------------------------+EVENT TIME: 19:39[EST]| |NRC NOTIFIED BY: JOHN MANSELL |LAST UPDATE DATE: 03/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HOT SHORTS COULD CAUSE UNINTENDED MOTION OF PRESSURIZER PORV AND BLOCK | | VALVES. | | | | A RE-ANALYSIS OF THE APPENDIX R FIRE PROTECTION PROGRAM PERFORMED BY THE | | LICENSEE DETERMINED THAT A CABLE TRAY FIRE MIGHT RESULT IN A HOT SHORT | | CROSS CONNECTING DC CONTROL WIRING TO ANOTHER DC SOURCE. THIS COULD RESULT | | IN UNANTICIPATED MOTION OF THE PRESSURIZER PORVs OR BLOCK VALVES. THE | | CORRECTIVE ACTIONS ARE TO ESTABLISH HOURLY FIRE WATCH TOURS AND TO CLOSE | | THE BLOCK VALVES PRIOR TO ANY CONTROL ROOM EVACUATION. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30204 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/29/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:08 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/29/96 | +------------------------------------------------+EVENT TIME: 20:48[CST]| |NRC NOTIFIED BY: LARRY LEES |LAST UPDATE DATE: 03/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LEE SPESSARD EO | | |DAMICO FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 81 POWER OPERATION | 72 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO ENTRY INTO EMERGENCY OPERATING PROCEDURE 05, | | "EMERGENCY SHUTDOWN". | | | | THE UNIT IS BEING SHUT DOWN BECAUSE OF A LEAK IN THE MAIN CONDENSER. | | INDICATIONS OF THE LEAKAGE ARE RISING SODIUM CONTENT, GREATER THAN 100 | | PARTS PER BILLION, AND RISING CATION CONDUCTIVITY. RIVER WATER IS | | CONTAMINATING THE FEED WATER. | | | | THE LICENSEE IS DECREASING POWER AT 10% PER HOUR. POWER MUST BE LOWER | | THAN 30% WITHIN FOUR HOURS OF THE DECLARATION OF THE UNUSUAL EVENT. | | CRITERIA FOR EXITING THE UNUSUAL EVENT ARE DECREASING CONDUCTIVITY, SODIUM | | CONCENTRATION LOWER THAN 100 PPB, OR REACTOR SHUT DOWN AND ISOLATION OF THE | | MAIN CONDENSER. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND | | NOTIFIED STATE AND LOCAL GOVERNMENT AGENCIES. | | | | * * * UPDATE AT 0001 ON 03/30/96 BY SANDHOEFNER ENTERED BY JOLLIFFE * * * | | | | AT 2235 (CST) ON 03/29/96, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE | | PLANT FROM 30% POWER. ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS | | BEING DUMPED TO THE 'B' MAIN CONDENSER. THE PLANT IS STABLE IN MODE 3 | | (HOT STANDBY). THE LICENSEE ISOLATED, DRAINED, AND OPENED THE 'A' MAIN | | CONDENSER AND WILL LOCATE AND PLUG THE LEAKING TUBE(S). | | | | AT 2312 (CST) ON 03/29/96, THE LICENSEE TERMINATED THE UNUSUAL EVENT AND | | WILL NOTIFY STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R4DO BLAINE MURRAY, NRR EO LEE SPESSARD, AND FEMA AUSTIN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30205 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/30/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 00:45 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 03/29/96 | +------------------------------------------------+EVENT TIME: 22:50[EST]| |NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 03/30/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 1 TO 3 GALLONS OF ANTIFREEZE LEAKED INTO THE PLANT AUXILIARY RESERVOIR - | | | | THE LICENSEE NOTIFIED WAKE COUNTY OFFICIALS THAT 1 TO 3 GALLONS OF ETHYLENE | | GLYCOL (ANTIFREEZE) LEAKED FROM A DIESEL FIRE PUMP HOSE INTO THE PLANT | | AUXILIARY RESERVOIR. THE LICENSEE STOPPED THE LEAK AND WILL REPLACE THE | | HOSE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30206 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/30/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 15:49 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/30/96 | +------------------------------------------------+EVENT TIME: 15:49[EST]| |NRC NOTIFIED BY: TIM KULTERMAN |LAST UPDATE DATE: 03/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED UNIT SHUTDOWN TO CORRECT A DESIGN DEFICIENCY IN THE | | AUXILIARY FEED WATER SYSTEM CONTAINMENT ISOLATION VALVES. | | | | AS A RESULT OF TESTING, THE LICENSEE HAS DETERMINED THAT 4 CONTAINMENT | | ISOLATION VALVES (1FWA*HV36A, B, C, AND D) FOR THE TURBINE DRIVEN AUXILIARY | | FEED WATER (AFW) PUMP WOULD NOT SATISFY THE REQUIREMENTS OF TECH SPEC | | 3.6.3, "CONTAINMENT ISOLATION VALVES". THE LCO FOR THIS TECH SPEC IS | | CORRECTION OF THE PROBLEM WITHIN 4 HOURS OR BE IN HOT STANDBY WITHIN THE | | FOLLOWING 6 HOURS. THE CLOCK FOR THE LCO STARTED AT 1415 EST. UNIT | | SHUTDOWN AT 0.5% PER MINUTE STARTED AT 1549 EST. THE LICENSEE PLANS GO TO | | MODE 5 TO CORRECT THE PROBLEM. | | | | THE ISOLATION VALVES ARE TARGET ROCK SOLENOID OPERATED VALVES. TESTING | | DISCLOSED THAT THIS DESIGN CAN HOLD PRESSURE IN THE DIRECTION OF FLOW | | (FROM AFW PUMP TO STEAM GENERATOR), BUT NOT IN THE REVERSE DIRECTION. | | IF AN ACCIDENT OCCURS THAT PRESSURIZES CONTAINMENT, AND THE SECONDARY SIDE | | OF THE STEAM GENERATOR OPENS TO CONTAINMENT PRESSURE, AND THE AFW PIPING | | BETWEEN THE PUMP AND THE VALVE BECOMES DEPRESSURIZED, THESE VALVES WOULD | | NOT ADEQUATELY PREVENT LEAKAGE FROM CONTAINMENT TO THE ENVIRONMENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND STATE & LOCAL | | OFFICIALS AND WILL ISSUE A PRESS RELEASE. | | | | * * * UPDATE AT 1007 ON 03/31/96 BY LANGAN ENTERED BY HOO JOLLIFFE * * * | | | | UNIT 3 IS IN MODE 3 (HOT STANDBY). AT 0948 ON 03/31/96, THE LICENSEE | | NOTIFIED THE NRC RESIDENT INSPECTOR AND STATE & LOCAL OFFICIALS THAT UNIT 3 | | WILL BE SHUTDOWN LONGER THAN 48 HOURS. THE HOO NOTIFIED R1DO NICHOLSON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30207 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/31/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 06:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/31/96 | +------------------------------------------------+EVENT TIME: 04:33[EST]| |NRC NOTIFIED BY: JIM McGINNIS |LAST UPDATE DATE: 03/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 DUE TO STEP COUNTER DEVIATIONS DURING PLANT STARTUP - | | | | WHILE STARTING THE PLANT UP, THE ROD CONTROL PULSE-TO-ANALOG CONVERTER | | INDICATED 36 STEPS (OF 229 STEPS) BUT CONTROL BANK 'D' WAS AT 16 STEPS. | | CONTROL ROOM OPERATORS TERMINATED THE PLANT STARTUP. | | | | CONTROL ROOM OPERATORS WERE INSERTING ALL CONTROL BANKS WHEN THE STEP | | COUNTERS FOR CONTROL BANK 'A', GROUP 1, DEVIATED FROM THE STEP COUNTERS | | FOR CONTROL BANK 'A', GROUP 2 BY 4 STEPS. | | | | TECH SPEC LCO A/S 3.1.7 REQUIRES THAT THE GROUP DEMAND POSITION INDICATORS | | BE WITHIN +/- 2 STEPS FOR EACH ROD OR TO IMMEDIATELY OPEN THE REACTOR TRIP | | BREAKERS. | | | | AT 0433, CONTROL ROOM OPERATORS MANUALLY OPENED THE REACTOR TRIP BREAKERS. | | ALL CONTROL RODS INSERTED COMPLETELY. THE PLANT IS STABLE IN MODE 3 (HOT | | STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE(S) AND WILL MAKE REPAIRS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30208 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 03/31/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 05:55 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 03/31/96 | +------------------------------------------------+EVENT TIME: 02:54[CST]| |NRC NOTIFIED BY: JAY DRESSEN |LAST UPDATE DATE: 03/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER 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 | A/R Y 70 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MAIN TURBINE TRIP/Rx TRIP WHILE TESTING MAIN TURBINE REHEAT STOP VALVES - | | | | WHILE TESTING THE MAIN TURBINE REHEAT STOP VALVES, CONTROL ROOM OPERATORS | | LOCALLY CLOSED MAIN TURBINE REHEAT STOP VALVE #1B2 BY DEPRESSURIZING THE | | FLUID SYSTEM THAT IS USED TO POSITION THE VALVE. | | | | HOWEVER, WHEN THE POSITIONING FLUID SYSTEM WAS DEPRESSURIZED, MAIN TURBINE | | STOP VALVES #MS-3A AND #MS-3B CLOSED UNEXPECTEDLY TRIPPING THE MAIN TURBINE | | WHICH TRIPPED THE REACTOR FROM 70% POWER. ALL CONTROL RODS INSERTED | | COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. THE LETDOWN | | AND BLOWDOWN SYSTEMS ISOLATED. | | | | THE LICENSEE RESET THE LETDOWN AND BLOWDOWN SYSTEMS AND IS INVESTIGATING | | THE CAUSE(S) OF THE MAIN TURBINE TRIP. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #30209 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 03/31/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 13:26 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 03/31/96 | +------------------------------------------------+EVENT TIME: 10:50[CST]| |NRC NOTIFIED BY: TOM APPLE |LAST UPDATE DATE: 03/31/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER 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 | A/R N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTO Rx TRIP DUE TO LOW STEAM GENERATOR WATER LEVEL WHILE IN HOT SHUTDOWN. | | | | WHILE PERFORMING ROD DROP TESTS IN ACCORDANCE WITH NRC BULLETIN 96-01, | | "CONTROL ROD INSERTION PROBLEMS", AN AUTO REACTOR TRIP OCCURRED DUE TO | | LOW WATER LEVEL IN THE "1A" STEAM GENERATOR (BELOW 17%). ALL CONTROL RODS | | INSERTED FULLY, AND STEAM GENERATOR LEVEL RETURNED TO WITHIN THE NORMAL | | BAND. STEAM GENERATOR WATER LEVEL HAD DECREASED BECAUSE THE OPERATORS WERE | | TRYING TO CONSERVE MAKEUP WATER FROM THE CONDENSATE STORAGE TANK FOR LATER | | PLANT RESTART. NO UNUSUAL PLANT CONDITIONS OCCURRED AS A RESULT OF THIS | | TRIP. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #30208 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30210 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 03/31/96 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 15:02 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 03/31/96 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: ED LYONS |LAST UPDATE DATE: 03/31/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LEE SPESSARD EO | |NLCO TECH SPEC LCO A/S |CIBOCH FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED AT 1430 DUE TO IDENTIFIED RCS LEAKAGE GREATER THAN | | THE 10 GPM TECH SPEC LIMIT. | | | | BETWEEN 1245 AND 1255, REACTOR COOLANT SYSTEM LEAKAGE OF 29 GPM WAS | | OBSERVED FROM THE LETDOWN SYSTEM "A" CHEMICAL ION EXCHANGER INLET | | VALVE PACKING. BYPASSING THE ION EXCHANGER TERMINATED THE LEAK. | | APPROXIMATELY 350 GALLONS WENT INTO AN EQUIPMENT DRAIN TANK. | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1443 WHEN THE LEAKAGE WAS STOPPED. | | THE LICENSEE WILL REPAIR THE VALVE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL | | OFFICIALS AND WILL ISSUE A PRESS RELEASE. | | | | * * * UPDATE AT 0007 ON 04/01/96 BY DAVE FIELDS ENTERED BY JOLLIFFE * * * | | | | THE FOLLOWING REPORT CLARIFIES THE ABOVE REPORT: | | | | AT APPROXIMATELY 1155 ON 03/31/96, CONTROL ROOM OPERATORS OBSERVED THAT | | THE UNIT 2 VOLUME CONTROL TANK (VCT) LEVEL WAS DROPPING VERY SLOWLY. | | CONTROL ROOM OPERATORS SUSPECTED, BUT HAD NOT CONFIRMED, THAT REACTOR | | COOLANT SYSTEM (RCS) INVENTORY LOSS EXCEEDED THE TECH SPEC LIMIT OF | | GREATER THAN 1.0 GPM OF UNIDENTIFIED LEAKAGE. CONTROL ROOM OPERATORS | | COMMENCED AN RCS INVENTORY BALANCE AND AN EXTENSIVE SEARCH FOR POSSIBLE | | LEAK PATHS. | | | | AT 1246, CONTROL ROOM OPERATORS NOTED AN INCREASED RATE OF VCT LEVEL DROP | | AND A MOMENTARY LETDOWN FLOW RATE INCREASE TO GREATER THAN 100 GPM AND THEN | | IT RETURNED TO APPROXIMATELY 82 GPM. SUBSEQUENT LICENSEE INVESTIGATION | | SHOWED THAT THE INVENTORY LOSS RATE APPEARED TO BE APPROXIMATELY 29 GPM. | | | | AT 1255, CONTROL ROOM OPERATORS BYPASSED THE LETDOWN ION EXCHANGERS WHICH | | STOPPED THE RCS INVENTORY LOSS. AN RCS INVENTORY BALANCE CONFIRMED THAT | | THE RCS INVENTORY LOSS RATE WAS APPROXIMATELY 0 GPM AND WITHIN TECH SPEC | | LIMITS. | | | | LICENSEE INVESTIGATION INDICATED THAT THE GREATER THAN 1.0 GPM LEAK | | APPEARED TO BE COMING FROM THE #2A PURIFICATION ION EXCHANGER INLET | | ISOLATION VALVE STEM LEAKOFF. THE INVESTIGATION ALSO INDICATED THAT | | A LETDOWN SYSTEM RELIEF VALVE APPEARED TO HAVE BEEN LIFTING BETWEEN | | 1246 AND 1255 AND IS SUSPECTED TO BE THE SOURCE OF THE RAPID RCS INVENTORY | | LOSS DURING THIS PERIOD. THIS RELIEF VALVE RELIEVES TO HOLDUP TANKS | | WHICH SHOWED A LEVEL INCREASE CORRESPONDING TO APPROXIMATELY 400 GALLONS. | | | | SUBSEQUENT LICENSEE REVIEW OF THIS SITUATION LED TO THE DECLARATION OF THE | | UNUSUAL EVENT AT 1430 BASED UPON RCS LEAK RATE EXCEEDING THE TECH SPEC | | LIMIT OF 1.0 GPM UNIDENTIFIED LEAKAGE. THE LICENSEE ALSO TERMINATED THE | | UNUSUAL EVENT AT 1430. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL | | OFFICIALS OF BOTH THE DECLARATION AND THE TERMINATION OF THE UNUSUAL EVENT. | | | | THE LICENSEE WILL REPAIR THE VALVE. | | | | THE HOO NOTIFIED R2DO GEORGE AL BELISLE AND EO LEE SPESSARD OF THIS UPDATE. | +------------------------------------------------------------------------------+