U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/22/96 - 03/25/96 ** EVENT NUMBERS ** 30004 30037 30067 30151 30152 30153 30154 30155 30156 30157 30158 30159 30160 30161 30162 30163 30164 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30004 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/21/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 03:34 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/21/96 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: STEPHEN DAVIS |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL SINGLE FAILURE CONCERNS WHICH COULD IMPACT TRAIN 'A' AND 'B' | | ENGINEERED SAFEGUARDS FEATURES (ESF) ACTUATION CIRCUITRY WHILE THE UNIT IS | | IN COLD SHUTDOWN DUE TO A LACK OF SEPARATION BETWEEN TRAIN 'A' AND TRAIN | | 'B' COMPONENTS | | | | DURING REVIEW OF AN EXTENT OF CONDITION EVALUATION, ENGINEERING IDENTIFIED | | THAT THE TWO CONTAINMENT ISOLATION PHASE 'B' ACTUATION PUSH BUTTONS LOCATED | | IN THE CONTROL ROOM ARE NOT SEPARATED OR MODULARIZED AS REQUIRED. EACH | | PUSH BUTTON ACTUATES THE CONTAINMENT ISOLATION PHASE 'B' RELAYS IN BOTH | | TRAINS 'A' AND 'B'. WIRES FROM BOTH TRAINS 'A' AND 'B' ARE TERMINATED ON | | THE CONTACT BLOCKS OF BOTH PUSH BUTTONS AND COME INTO CONTACT BEFORE THEY | | EXIT THE PANEL. THE TWO PUSH BUTTONS ARE LOCATED APPROXIMATELY ONE INCH | | APART. POWER SUPPLIES TO THE PHASE 'B' ISOLATION RELAYS ARE COMMON WITH | | ALL OTHER ESF RELAYS. DUE TO A LACK OF SEPARATION BETWEEN TRAIN 'A' AND | | TRAIN 'B' COMPONENTS, THERE ARE POTENTIAL SINGLE FAILURE CONCERNS WHICH | | COULD IMPACT TRAIN 'A' AND TRAIN 'B' ESF ACTUATION CIRCUITRY. THIS IS | | STILL UNDER EVALUATION BY ENGINEERING. | | | | THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR | | OPERATION AT THIS TIME BECAUSE IT IS IN A COLD SHUTDOWN CONDITION. ONE | | RESIDUAL HEAT REMOVAL PUMP AND ONE REACTOR COOLANT PUMP ARE CURRENTLY IN | | SERVICE. THE EMERGENCY DIESEL GENERATORS ARE ALSO AVAILABLE. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0837 ON 03/22/96, BY STEVE SMITH ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE DETERMINED THAT THE SINGLE FAILURE CRITERION WAS MET BY THE | | AS-BUILT PHYSICAL CONFIGURATION OF THE CIRCUITRY. A SINGLE ACTIVE FAILURE | | IN ONE TRAIN WILL NOT PREVENT THE OTHER TRAIN FROM PERFORMING ITS SAFETY | | FUNCTION BASED ON THE PHYSICAL SEPARATION AND ELECTRICAL PROTECTION | | INVOLVED. THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R1DO JOHN ROGGE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30037 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/27/96 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 20:16 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/25/96 | +------------------------------------------------+EVENT TIME: 20:17[MST]| |NRC NOTIFIED BY: BURT GRABO |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ANLI 50.72(b)(1)(iii) LIGHTNING | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LIGHTING STRIKE CAUSED UNANALYZED ABNORMAL ELECTRICAL CONFIGURATION - | | | | AT 2017 MST ON 02/25/96, WITH UNITS 1, 2, AND 3 EACH AT 100% POWER, UNIT 1 | | EXPERIENCED A LIGHTNING STRIKE TO ITS #X01C MAIN TRANSFORMER WHICH CAUSED | | THE UNIT 1 MAIN TURBINE TO TRIP. UNIT 1 REACTOR REMAINED CRITICAL AT 46% | | POWER DUE TO THE PROPER OPERATION OF THE REACTOR CUTBACK SYSTEM. | | | | THE LICENSEE DISCOVERED THAT STARTUP TRANSFORMERS #XFMR-X01 AND X02 WERE | | CROSS TIED DUE TO BOTH THE NORMAL AND ALTERNATE SUPPLY BREAKERS BEING | | CLOSED ON BUS #1E-NAN-S06. THIS CONFIGURATION IS NOT NORMAL FOR PALO VERDE | | AND POTENTIALLY PUTS PALO VERDE IN AN UNANALYZED CONFIGURATION (CONDITION) | | WHERE A DESIGN ELECTRICAL FAULT COULD HAVE EXCEEDED THE DESIGNED | | INTERRUPTING CAPACITY OF THE NON-CLASS-1E 13.8-KV CIRCUIT BREAKERS. THIS | | PUTS PALO VERDE IN A CONDITION OUTSIDE ITS DESIGN BASIS (GENERAL DESIGN | | CRITERIA #5 AND #17). THIS CONFIGURATION DID NOT IMPACT THE INTEGRITY OF | | THE SAFETY-RELATED BUS TO BE LOADED. BOTH UNIT 1 EMERGENCY DIESEL | | GENERATORS REMAINED OPERABLE THROUGHOUT THIS EVENT, AND ALL SAFETY-RELATED | | COMPONENTS WERE FULLY CAPABLE OF PERFORMING THEIR DESIGN FUNCTIONS. THE | | LICENSEE RESTORED UNIT 1 TO ITS NORMAL DESIGN CONFIGURATION. THE LICENSEE | | IS DETERMINING WHY BOTH BREAKERS WERE CLOSED. UNIT 2 WAS UNAFFECTED BY | | THIS EVENT; UNIT 3 RAN BACK TO 35% POWER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. (SEE EVENT #30026 FOR A | | RELATED EVENT.) | | | | * * * 1505 EST MARCH 22, 1996, UPDATE FROM EKLUND RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT DUE TO THE DETERMINATION THAT THE | | EQUIPMENT FAILURE OF THE ALTERNATE SUPPLY BREAKER CLOSING ON INTERMEDIATE | | BUS 1-E-NAN-S06 DID NOT RESULT IN THE PLANT BEING OUTSIDE GENERAL DESIGN | | CRITERIA #5 AND #17. A POSTULATED SHORT CIRCUIT COULD HAVE CAUSED | | CATASTROPHIC FAILURE OF DISTRIBUTION EQUIPMENT; HOWEVER, THE DAMAGE WOULD | | HAVE BEEN LIMITED TO BUSES 1-E-NAN-S06 OR 2-E-NAN-S05. A SHORT CIRCUIT ON | | DISTRIBUTION EQUIPMENT DOWNSTREAM OF 1-E-NAN-S06 AND 2-E-NAN-S05, INCLUDING | | CLASS 1E BUSES, WOULD NOT BE AFFECTED BY THIS CONDITION BECAUSE OF THE | | SHORT CIRCUIT CURRENT LIMITING EFFECT OF COMPONENTS SUCH AS CABLES AND | | TRANSFORMERS. LOSS OF ONE TRAIN OF CLASS 1E POWER DUE TO A POSTULATED | | SHORT CIRCUIT WOULD NOT RESULT IN LOSS OF THE OTHER TRAIN. THEREFORE, A | | PREFERRED POWER SOURCE (TRAIN 'B' ON UNIT 1 AND TRAIN 'A' ON UNIT 2) AND | | BOTH EMERGENCY DIESEL GENERATORS WOULD BE AVAILABLE TO PERFORM THEIR DESIGN | | FUNCTIONS IF REQUIRED DURING THIS CONDITION. ALTHOUGH THIS CONDITION HAS | | NOT BEEN SPECIFICALLY ANALYZED, THE LICENSEE BELIEVES THAT THIS EVENT DID | | NOT RESULT IN A CONDITION THAT SIGNIFICANTLY COMPROMISED PLANT SAFETY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R4DO (LINDA HOWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/05/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [3] CE |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 13:55[CST]| |NRC NOTIFIED BY: PIPKINS |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM (SPDS) DEGRADED | | | | SPDS DISPLAY POINTS (19 OF 37) WILL BE TEMPORARILY DEGRADED OVER THE NEXT 3 | | WEEKS. THE SPDS POINTS WILL BE DISCONNECTED AND INOPERABLE DURING THE | | PERFORMANCE OF CORRECTIVE MAINTENANCE THAT IS NECESSARY TO CORRECT A | | PROBLEM THAT HAS RESULTED IN FOUR RECENT FAILURES. THE PLANNED MAINTENANCE | | WILL AFFECT ABOUT ONE THIRD OF THE SPDS SCREEN LAYOUT. THE 19 DIGITAL | | INPUTS TO SPDS AFFECT ESFAS STATUS INDICATIONS. ALSO, 22 OF THE POINTS | | AFFECTED WILL BE INFORMATION THAT WOULD BE INPUTTED TO THE SEQUENCE OF | | EVENTS (SOE) SYSTEM THUS IMPACTING POST TRIP ASSESSMENT CAPABILITY. THE 19 | | SPDS POINTS ARE ALSO SOE POINTS. THE SPDS AND SOE POINTS ARE NOT SAFETY | | RELATED. THE PLANT MONITORING COMPUTER IS CONSIDERED NOT AVAILABLE DURING | | AND AFTER AN ACCIDENT. IT IS ESTIMATED THAT THE SPDS POINTS WILL BE OUT OF | | SERVICE FROM MARCH 5 TO 22, 1996. THE SPDS POINTS INVOLVED ARE DIGITAL | | POINTS THAT ARE DUPLICATIONS OF CONTROL ROOM ANNUNCIATOR POINTS THAT ARE | | PROVIDED AS AN INDICATION TO THE CONTROL ROOM OPERATORS THAT A PLANT | | PROTECTION SYSTEM OR EMERGENCY SAFEGUARDS SYSTEM ACTUATION HAS OCCURRED OR | | THAT A SAFETY BUS UNDERVOLTAGE OR GROUND CONDITION EXISTS. THE ANNUNCIATOR | | WILL REMAIN OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1459 MARCH 22, 1996, UPDATE FROM PIPKINS RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS IN THE PROCESS OF RESTORING THE AFFECTED SPDS DISPLAY | | POINTS AND WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R4DO (LINDA HOWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/22/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 02:34 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: MATT POHL |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HYDRAZINE DISCHARGE TO MISSOURI RIVER EXCEEDED NPDES PERMIT LIMIT - | | | | THE LICENSEE WILL NOTIFY THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY | | THAT AT 2300 CST ON 03/21/96, THE HYDRAZINE LEVEL (143 PPB) IN A SAMPLE OF | | THE PLANT CIRCULATING WATER DISCHARGED TO THE MISSOURI RIVER EXCEEDED THE | | NATIONAL POLLUTION DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT LIMIT OF | | 100 PPB. THE LICENSEE TERMINATED THE CONDENSATE SYSTEM FLUSH WHICH WAS THE | | SOURCE OF THE HYDRAZINE RELEASE. HYDRAZINE IS USED TO SCAVENGE OXYGEN IN | | THE CONDENSATE AND FEEDWATER SYSTEMS. | | | | THE HYDRAZINE LEVEL IN A CIRCULATING WATER SAMPLE TAKEN AT 0015 CST ON | | 03\22\96 WAS 3 PPB. THE LICENSEE IS DETERMINING THE REASON FOR THE HIGH | | HYDRAZINE LEVEL IN THE CONDENSATE SYSTEM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30152 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/22/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 04:22 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 04:00[EST]| |NRC NOTIFIED BY: BILL BANDHAUER |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CREV SYSTEM DESIGN FLOW RATE CALCULATIONS MAY BE NONCONSERVATIVE - | | | | THE LICENSEE DETERMINED THAT THE CONTROL ROOM EMERGENCY VENTILATION (CREV) | | SYSTEM DESIGN CALCULATIONS ASSUMED NOMINAL AIR FLOW VALUES. THE CREV FANS | | HAVE AN ALLOWABLE ADJUSTMENT TOLERANCE OF ñ10% OF THE NOMINAL FLOW RATE. | | THE CURRENTLY MEASURED ACTUAL FLOW RATES ARE WITHIN THE ALLOWABLE DESIGN | | FLOW RATE TOLERANCE. THE DESIGN CALCULATIONS DO NOT PROVIDE ASSURANCE THAT | | ADJUSTMENT WITHIN THIS TOLERANCE WILL PROVIDE ADEQUATE CHARCOAL FILTRATION | | EFFICIENCY AT THE HIGHER TOLERANCE OR ADEQUATE DILUTION OF AIR IN LEAKAGE | | (DOSE) AT THE LOWER TOLERANCE. THE CALCULATION IS CURRENTLY BEING | | REPERFORMED USING THE TOLERANCE VALUES. THE LICENSEE WILL RESOLVE THIS | | ISSUE PRIOR TO THE PLANT ENTERING MODE 4 WHEN THE CREV SYSTEM WILL BE | | REQUIRED. THE CASE FOR FUEL MOVEMENT (FUEL HANDLING ACCIDENT) HAS ALREADY | | BEEN ANALYZED AND IS WELL WITHIN THE DESIGN LIMITS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30153 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTRONICS |NOTIFICATION DATE: 03/22/96 | | CITY: KINGWOOD REGION: 4 |NOTIFICATION TIME: 14:38 [ET]| | COUNTY: STATE: TX |EVENT DATE: 03/12/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CST]| | DOCKET: |LAST UPDATE DATE: 03/22/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LINDA HOWELL RDO | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: CHRIS KELLY |HENRY BAILEY ERB | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION REGARDING THE DISCOVERY OF A FIRMWARE BUG THAT | | EXISTS IN ASSOCIATION WITH AN ENHANCED MATH PACKAGE ON WESTRONICS SERIES | | 3000C AND 3200C CHART RECORDERS | | | | WESTRONICS DISCOVERED A FIRMWARE BUG THAT EXISTS IN ASSOCIATION WITH THE | | ENHANCED MATH OPTION OF THE SERIES 3000C FIRMWARE (VERSIONS 3.0A AND ABOVE) | | AND THE SERIES 3200C FIRMWARE (VERSIONS 2.0A AND ABOVE). THIS PROBLEM IS | | CAUSED BY AN OUT OF CONTROL SOFTWARE POINTER; AND MANIFESTATIONS OF THE BUG | | INCLUDED CHANGING OF PRINTED LOG SCALE END POINTS, CHANGING OF PROGRAMMED | | POINT OUTPUT SCALES, THE TIME OF 20:XX:XX PRINTED AS 6C:XX:XX IN MARGIN | | LOGS, AND THE RANDOM SUPPRESSION OF POINT DATA FROM LOGS AND THE DISPLAY. | | THE NOTED PROBLEMS ARE TRIGGERED SPECIFICALLY BY THE PROGRAMMING AND | | TRENDING OF LOGARITHMIC POINT TYPES AND LOG SCALES WITH THE RECORDER IN THE | | TREND MODE. IF THE INSTRUMENT IS EQUIPPED WITH THE ENHANCED MATH OPTION | | AND IF THE CUSTOMER IS NOT USING THE LOGARITHMIC POINT TYPES AND LOG | | SCALES, THEN THE NOTED PROBLEMS WILL NOT APPEAR. THE ENHANCED MATH OPTION | | REQUIRES THE PRESENCE OF THE PI100117 OPTION DECODER 'PROM.' INSTRUMENTS | | NOT ORDERED FROM THE FACTORY WITH THE ENHANCED MATH OPTION DO NOT HAVE THE | | OPTION DECODER 'PROM' INSTALLED AND WILL NOT EXPERIENCE THE NOTED PROBLEMS. | | THE PROBLEMS THAT LED TO THE DISCOVERY OF THIS BUG WERE BROUGHT TO THE | | ATTENTION OF WESTRONICS ON OR ABOUT MARCH 12, 1996. | | | | WESTRONICS HAS BEEN ABLE TO DETERMINE THAT SOUTHERN CALIFORNIA EDISON (SAN | | ONOFRE) IS IN POSSESSION OF INSTRUMENTS THAT ARE CONFIGURED WITH THE | | REQUIRED OPTIONS AND THAT CONTAIN THE AFFECTED SOFTWARE. THE SINGLE NOTED | | LICENSEE HOLDER HAS RECEIVED NOTIFICATION BY WESTRONICS. | | | | (REFER TO THE HOO LOG FOR THE CONTACT'S ADDRESS AND TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30154 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/22/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 16:01 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: ERIK McCARTNEY |LAST UPDATE DATE: 03/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INADEQUATE TESTING OF BOTH | | EMERGENCY SAFEGUARDS SEQUENCERS | | | | AT 1500 ON MARCH 21, 1996, A DETERMINATION WAS MADE THAT INADEQUATE TESTING | | HAD BEEN PERFORMED ON BOTH EMERGENCY SAFEGUARDS SEQUENCERS. (THIS WAS | | FOUND AS PART OF THE LICENSEE'S RESEARCH ON THE GENERIC LETTER 96-01 | | REVIEWS.) FROM 1500 ON MARCH 21, 1996, TO 1500 ON MARCH 22, 1996, THE | | LICENSEE HAD APPLIED TECHNICAL SPECIFICATION 4.0.3 WHICH ALLOWS 24 HOURS TO | | TEST THE EQUIPMENT SATISFACTORILY. DURING THIS TIME FRAME, THE LICENSEE | | HAD BEEN ACTIVELY DEVELOPING TESTS TO DEMONSTRATE OPERABILITY OF THE | | APPLICABLE FEATURES. (THE PROBLEM INVOLVES BLOCKING RELAYS THAT ACTUATE | | BLOCKING SIGNALS FOR AUTOMATIC START SIGNALS OF NON-ENGINEERED SAFEGUARDS | | FEATURES EQUIPMENT.) UPON EXPIRATION OF THE 24-HOUR PERIOD ALLOWED BY | | TECHNICAL SPECIFICATION 4.0.3 (AT 1500 ON MARCH 22, 1996), THE PLANT | | ENTERED THE ACTIONS FOR TECHNICAL SPECIFICATION 3.0.3. THIS REQUIRES THE | | UNIT TO BE PLACED IN MODE 3 (HOT STANDBY) BY 2200 ON MARCH 22, 1996, UNLESS | | A SEQUENCER IS RESTORED TO AN OPERABLE STATUS. SUBSEQUENT ACTIONS OF THAT | | SPECIFICATION MAY ALSO BE REQUIRED. THE LICENSEE IS CURRENTLY MAKING | | PREPARATIONS FOR AN ORDERLY PLANT SHUTDOWN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 1828 MARCH 22, 1996, UPDATE FROM FLEMING RECEIVED BY TROCINE * * * | | | | THE LICENSEE COMMENCED A UNIT LOAD DECREASE AT 1804 ON MARCH 22, 1996, IN | | PREPARATION TO COMPLY WITH THE UNIT BEING IN MODE 3 (HOT STANDBY) BY 2200. | | SUBSEQUENT ACTIONS MAY BE TO PLACE THE UNIT IN MODE 4 (HOT SHUTDOWN) BY | | 0400 ON MARCH 23, 1996, AND MODE 5 (COLD SHUTDOWN) BY 0400 ON MARCH 24, | | 1996, PER TECHNICAL SPECIFICATION 3.0.3. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, AND THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (SHYMLOCK). | | | | * * * 2222 MARCH 22, 1996, UPDATE FROM FLEMING RECEIVED BY TROCINE * * * | | | | DUE TO THE ACTIONS REQUIRED BY TECHNICAL SPECIFICATION 3.0.3, THE UNIT WAS | | TAKEN OFF LINE IN AN ORDERLY MANNER AT 2139, AND MODE 3 WAS ACHIEVED AT | | 2152. BOTH EMERGENCY SAFEGUARDS SEQUENCERS REMAIN INOPERABLE, AND TESTING | | IS UNDERWAY ON THE 1A-SA SEQUENCER. UNLESS ONE SEQUENCER IS RESTORED TO | | OPERABLE STATUS PRIOR TO 0400 ON MARCH 23, 1996, THE PLANT WILL HAVE TO BE | | IN MODE 4 (HOT SHUTDOWN) BY THAT TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (SHYMLOCK). | | | | * * * 0006 MARCH 23, 1996, UPDATE FROM FLEMING RECEIVED BY WEAVER * * * | | | | AT 2336 ON MARCH 22, 1996, CONDITIONS FOR TECHNICAL SPECIFICATION 3.0.3 | | ACTIONS NO LONGER APPLY. VARIOUS BLOCKING RELAYS ON THE 1A-SA SEQUENCER | | WERE TESTED SATISFACTORILY. THE 1B-SB SEQUENCER REMAINS INOPERABLE WHILE | | ITS ASSOCIATED TEST PROCEDURE IS BEING PREPARED. TECHNICAL SPECIFICATION | | 3.8.1.1.H ACTIONS APPLY WHICH REQUIRE THE UNIT TO BE IN MODE 5 (COLD | | SHUTDOWN) BY 2100 ON MARCH 24, 1996, IF THE 1B-SB IS STILL INOPERABLE. THE | | UNIT IS CURRENTLY AT NO LOAD TEMPERATURE AND PRESSURE WITH ALL RODS | | INSERTED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (SHYMLOCK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30155 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 03/22/96 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:19 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 10:50[EST]| |NRC NOTIFIED BY: DAVID GUDGER |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 +------------------------------------------------------------------------------+ | FOSSIL UNIT SUPERVISOR WITH ACCESS TO NUCLEAR UNIT FOUND TO BE UNFIT FOR | | DUTY FOLLOWING RANDOM ALCOHOL TEST | | | | A FOSSIL UNIT (UNIT 1) SUPERVISOR WITH UNESCORTED ACCESS AUTHORIZATION FOR | | THE NUCLEAR UNIT (UNIT 2) WAS FOUND TO BE UNFIT FOR DUTY BASED ON THE | | RESULTS OF A RANDOM BREATHALYZER ALCOHOL TEST. THE INDIVIDUAL'S ACCESS HAS | | BEEN TERMINATED PENDING THE RESULTS OF THE SECOND PART OF THE | | FITNESS-FOR-DUTY SCREEN (URINE ANALYSIS TEST). | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30156 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION DATE: 03/22/96 | | CITY: BETHESDA REGION: 1 |NOTIFICATION TIME: 16:41 [ET]| | COUNTY: MONTGOMERY STATE: MD |EVENT DATE: 03/22/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 15:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/22/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN ROGGE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ROBERT ZOON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAD1 20.2202(a)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IRRADIATOR MALFUNCTIONED - NO PERSONNEL EXPOSURE | | | | AT THE END OF AN IRRADIATION WITH A J.L. SHEPHERD AND ASSOCIATES MARK I | | IRRADIATOR, THE 4,476-CURIE CESIUM-137 SOURCE (STRENGTH AS OF SEPTEMBER 4, | | 1992) FAILED TO FULLY RETURN TO ITS SHIELDED POSITION AND STOPPED | | APPROXIMATELY 2 INCHES BEFORE REACHING THE "OFF" POSITION. PERSONNEL | | PROMPTLY RETURNED THE SOURCE TO THE SHIELDED POSITION USING MANUAL | | PROCEDURES. THIS PERMITTED THE CHAMBER TO BE ACCESSED AND THE SAMPLES TO | | BE SAFELY REMOVED. THERE WERE NO EXPOSURES INCURRED AS A RESULT OF THIS | | INCIDENT, AND THE IRRADIATOR HAS BEEN TAKEN OUT OF SERVICE UNTIL PROPER | | OPERATION CAN BE VALIDATED BY AN AUTHORIZED J.L. SHEPHERD AND ASSOCIATES | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30157 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/22/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:01 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 16:45[EST]| |NRC NOTIFIED BY: NATHAN JAYCOX |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED CONDITION WHILE DEFUELED DUE TO THE FAILURE OF PROCEDURES TO | | ACCOUNT FOR THE UNUSABLE VOLUME IN THE CONDENSATE STORAGE TANK | | | | TECHNICAL SPECIFICATION 3.5.C.3 REQUIRES A MINIMUM OF 250,000 GALLONS OF | | USABLE WATER IN THE CONDENSATE STORAGE TANK (CST) IN ORDER TO ENSURE | | OPERABILITY OF THE FEEDWATER COOLANT INJECTION SYSTEM, AND PLANT PROCEDURES | | REQUIRE THE CST LEVEL TO BE GREATER THAN 300,000 GALLONS. ENGINEERING | | EVALUATIONS HAVE CONCLUDED THAT THE UNUSABLE CST VOLUME DUE TO THE LOCATION | | OF THE SUCTION NOZZLE, INSTRUMENT UNCERTAINTY, AND PUMP VORTEXING IS | | APPROXIMATELY 65,000 GALLONS. THEREFORE, IN ORDER TO MEET THIS TECHNICAL | | SPECIFICATION, PLANT PROCEDURES SHOULD HAVE REQUIRED CST LEVEL TO BE | | GREATER THAN 315,000 GALLONS. THIS WAS DISCOVERED DURING A DESIGN BASIS | | REVIEW, AND IT HAS BEEN THE CASE SINCE 1987 WHEN THE LICENSEE CHANGED THE | | REQUIRED CST WATER VOLUME IN TECHNICAL SPECIFICATION 3.5.C.3 FROM 225,000 | | GALLONS TO 250,000 GALLONS AND ADDED THE WORD USABLE. | | | | THE LICENSEE HAS NOT YET COMPLETED ITS REVIEW OF ALL OF THE UNIT 1 TANKS | | (INCLUDING THE REFUELING WATER STORAGE TANK), BUT IT HAS BEEN DETERMINED | | THAT SOME OF THE UNIT 1 SITE FIRE WATER TANKS HAVE ANTI-VORTEXING DEVICES | | IN THEM. THE LICENSEE ALSO PLANS TO GENERATE AN ADVERSE CONDITION REPORT | | TO INFORM THE OTHER MILLSTONE UNITS OF THIS ISSUE. IN ADDITION, THE | | LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND THE APPROPRIATE | | STATE AND LOCAL OFFICIALS OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30158 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/22/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:16 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 19:20[EST]| |NRC NOTIFIED BY: PETER FARSACI |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE ACTUAL FIELD CONDITION OF THE LOWER SPRING WEDGE CONTACT | | AREA OF A CORE SHROUD REPAIR TIE ROD SUPPORT WAS DIFFERENT THAN THE | | PREVIOUS DESCRIPTION IN THE APPROVED NRC SAFETY EVALUATION REPORT | | | | DETAILED REVIEW OF INSPECTION TAPES BY LICENSEE AND GENERAL ELECTRIC (GE) | | ENGINEERING PERSONNEL ALONG WITH SUBSEQUENT 3-DIMENSIONAL COMPUTER-AIDED | | DRAFTING LAYOUT BY GE OF THE LOWER SPRING WEDGE CONTACT AREA OF THE 270ø | | AZIMUTH CORE SHROUD REPAIR TIE ROD SUPPORT WAS COMPLETED. THE LOWER SPRING | | WEDGE CONTACT AREA IS ON THE NOZZLE BLEND RADIUS OF A RECIRCULATION NOZZLE | | WELD, AND THE ACTUAL LOCATION IS DIFFERENT THAN WAS PREVIOUSLY DESCRIBED IN | | THE APPROVED NRC SAFETY EVALUATION REPORT. ENGINEERING REVIEW OF THIS | | CONDITION INDICATES THAT ALL FOUR OF THE CORE SHROUD REPAIR TIE RODS ARE | | CURRENTLY OPERABLE AS-IS. HOWEVER, THE LICENSEE IS REPORTING THIS TO BE | | CONSERVATIVE BECAUSE THE ACTUAL FIELD CONDITION IS DIFFERENT FROM THE | | APPROVED DESIGN WHICH WAS DESCRIBED IN A LICENSEE LETTER TO THE NRC DATED | | MARCH 23, 1995. | | | | THAT LETTER STATED THAT THE BEARING CONTACT AREA BETWEEN THE LOWER WEDGE | | AND THE REACTOR PRESSURE VESSEL RECIRCULATION NOZZLE IS APPROXIMATELY 66% | | OF THE WEDGE AREA. THE ACTUAL FIELD CONDITION COULD BE AS LOW AS 9.4% OF | | THE WEDGE AREA BASED UPON CURRENT ENGINEERING ASSESSMENT. THE LICENSEE | | LETTER INDICATED THAT 10% AREA WAS REQUIRED. | | | | THE SHORT-TERM ACTIONS ARE TO CONFIRM THE ANALYSIS WHICH MAY CURRENTLY OVER | | PREDICT THE IMPACT OF THIS ENGINEERING EVALUATION. THE LICENSEE PLANS TO | | DISCUSS THIS MATTER WITH THE APPROPRIATE NRC OFFICES REGARDING PLANS TO | | SUBMIT A REVISED LETTER AND REPAIR PLANS, IF NEEDED, FOR THE NEXT SCHEDULED | | REFUELING OUTAGE. THIS WAS DISCOVERED DURING WORK AS PART OF AN ONGOING | | EVALUATION BY LICENSEE ENGINEERING AND GE PERSONNEL TO EVALUATE AS-BUILT | | INFORMATION FOR THE POTENTIAL REWORK OF THIS PARTICULAR TIE ROD DURING THE | | SCHEDULED 1997 REFUELING OUTAGE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30159 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 03/22/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 23:54 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 23:12[EST]| |NRC NOTIFIED BY: HUMMEL |LAST UPDATE DATE: 03/22/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 5 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH-HIGH LEVEL IN THE "A" STEAM GENERATOR RESULTED IN ESF ACTUATIONS | | | | MAIN TURBINE PEDESTAL CHECKS WERE IN PROGRESS WITH REACTOR POWER AT BETWEEN | | 3 AND 5% AND WITH THE MAIN GENERATOR DISCONNECTED FROM THE GRID WHEN | | REACTOR COOLANT SYSTEM (RCS) TEMPERATURE BEGAN TO RAPIDLY DROP. THE | | LICENSEE INDICATED THAT THE DROP IN RCS TEMPERATURE COMBINED WITH THE | | CONTINUED STEAM DEMAND BY THE MAIN TURBINE CAUSED STEAM GENERATOR LEVELS TO | | SWELL. STEAM GENERATOR "A" REACHED THE HIGH-HIGH LEVEL SETPOINT AND CAUSED | | A MAIN TURBINE TRIP, FEEDWATER ISOLATION, AND START OF THE AUXILIARY | | FEEDWATER SYSTEM MOTOR-DRIVEN PUMPS. | | | | THE DROP IN RCS TEMPERATURE WAS CAUSED BY A COMBINATION OF BORATION AND ROD | | INSERTION. THE INSERTION OF NEGATIVE REACTIVITY CAUSED REACTOR POWER TO | | DROP BELOW STEAM DEMAND AND THEREBY CREATED THE MISMATCH BETWEEN REACTOR | | POWER AND STEAM DEMAND WHICH CAUSED THE DROP IN RCS TEMPERATURE. THE | | LICENSEE WAS MAKING PREPARATIONS TO PERFORM ROD TESTING IN ACCORDANCE WITH | | THE NRC BULLETIN RECENTLY ISSUED FOR WESTINGHOUSE PLANTS WHEN THIS EVENT | | OCCURRED. | | | | THE PLANT IS SUBCRITICAL, AND THE BORATION IS CONTINUING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30160 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/23/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 03:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/23/96 | +------------------------------------------------+EVENT TIME: 01:35[EST]| |NRC NOTIFIED BY: BRUCE BUTLER |LAST UPDATE DATE: 03/23/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 Y 17 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM ON HIGH REACTOR PRESSURE | | | | THE MAIN TURBINE WAS MANUALLY TRIPPED FROM 17% POWER AS PART OF THE | | SHUTDOWN PROCEDURE. TURBINE BYPASSES OPENED AS EXPECTED BUT THEN CLOSED. | | REACTOR PRESSURE INCREASED TO THE SCRAM SETPOINT. THE REACTOR SCRAM WAS | | NORMAL WITH NO COMPLICATIONS. ALL RODS FULLY INSERTED INTO THE CORE AND NO | | SAFETY RELIEF VALVES OPENED. FURTHER BYPASS ACTUATION WAS NOT REQUIRED | | BECAUSE OF THE LOW AMOUNT OF DECAY HEAT GENERATED. THE PLANT IS STABLE IN | | HOT STANDBY. THE LICENSEE IS INVESTIGATING WHY THE BYPASSES FAILED TO | | FUNCTION AS DESIGNED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 30161 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SPERRY-SUN DRILLING SERVICES |NOTIFICATION DATE: 03/23/96 | | CITY: HOUSTON REGION: 4 |NOTIFICATION TIME: 13:52 [ET]| | COUNTY: STATE: TX |EVENT DATE: 03/23/96 | |LICENSE#: 42-26844-01 AGREEMENT: Y |EVENT TIME: 11:00[CST]| | DOCKET: |LAST UPDATE DATE: 03/23/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LINDA HOWELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: RICHARD ARSENAULT | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPERRY-SUN DRILLING SERVICES WELL LOGGING SOURCE EVENT | | | | NAME OF WELL OWNER: VASTAR RESOURCES | | | | LOCATION OF THE WELL: FIELD SOUTH PASS BLOCK #60 IN THE GULF OF MEXICO OFF | | THE COAST OF LOUISIANA | | | | WELL IDENTIFICATION: OUTER CONTINENTAL SHELF OSC-G-1611C-21 SIDE TRACK #3 | | | | ISOTOPES: ONE AMERICIUM-241/BERYLLIUM, SPECIAL-FORM, ENCAPSULATED SOURCE | | (GAMATRON #C-756) LOCATED IN THE WELL AT A DEPTH OF 5,473 FEET AND ONE | | CESIUM-137, SPECIAL-FORM, ENCAPSULATED SOURCE (AMERSHAM #1920GW) LOCATED IN | | THE WELL AT A DEPTH OF 5,483 FEET | | | | QUANTITIES: 3 CURIES AND 2 CURIES, RESPECTIVELY | | | | REQUEST FOR IMMEDIATE NRC APPROVAL TO BEGIN ABANDONMENT: YES - THE DRILL | | STRING BECAME STUCK AT APPROXIMATELY 2300 CST ON MARCH 18, 1996, AND THE | | LICENSEE HAS BEEN FISHING FOR THE SOURCES SINCE THAT TIME. THE DECISION TO | | ABANDON THE SOURCE WAS MADE AT APPROXIMATELY 1100 CST ON MARCH 23, 1996. | | THE TOP OF THE FISH IS LOCATED AT A DEPTH OF 4,530 FEET, AND THE OPERATOR | | HAS PROPOSED TO PLUG THE WELL WITH CEMENT FROM THE TOP OF THE FISH UP TO | | THE CASING WHICH IS SET AT A DEPTH OF 3,555 FEET AND THEN SIDE TRACK FROM | | THERE AFTER THE CEMENT SETS UP. THE LICENSEE PLANS TO SEND A REPORT TO THE | | NRC WITH COPIES TO MINERALS MANAGEMENT SERVICE AND TO THE THE STATES OF | | TEXAS AND LOUISIANA. (REFER TO THE HOO LOG FOR THE LICENSEE'S ADDRESS AND | | CONTACT'S TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30162 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/24/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 10:24 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/24/96 | +------------------------------------------------+EVENT TIME: 06:31[EST]| |NRC NOTIFIED BY: JOHN REINESBURRO |LAST UPDATE DATE: 03/24/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 7 STARTUP | 7 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENGINEERED SAFEGUARDS FEATURE ACTUATION - SECONDARY CONTAINMENT ISOLATION, | | CONTAINMENT ATMOSPHERE AND MONITORING SYSTEM ISOLATION, AND STANDBY GAS | | TREATMENT (SBGT) AUTOMATIC START | | | | AT 0631 AND AGAIN AT 0735, UNIT 1 RECEIVED SECONDARY CONTAINMENT | | ISOLATIONS, CONTAINMENT ATMOSPHERE CONTROL AND MONITORING SYSTEM | | ISOLATIONS, AND 1A AND 1B SBGT AUTOMATIC STARTS. IN EACH CASE, THE SYSTEMS | | RESPONDED AS DESIGNED. THE SYSTEMS WERE RESET AFTER THE FIRST EVENT SO | | THAT THE EVENT AT 0735 WAS A DUPLICATE OF THE FIRST EVENT. THE ISOLATIONS | | WERE CAUSED BY AN INVALID SPURIOUS SIGNAL. THAT CONCLUSION IS BASED ON THE | | REDUNDANT INDICATIONS AVAILABLE. | | | | SBGT HAS BEEN STOPPED, AND ALL CONTAINMENT ISOLATION VALVES HAVE BEEN | | RETURNED TO THEIR ORIGINAL POSITIONS. THE EXACT CAUSE OF THIS EVENT IS NOT | | KNOWN BUT IS UNDER INVESTIGATION. THIS EVENT IS NOT EXPECTED TO DELAY THE | | STARTUP IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/24/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/24/96 | +------------------------------------------------+EVENT TIME: 13:50[CST]| |NRC NOTIFIED BY: A. T. ROGERS |LAST UPDATE DATE: 03/24/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOCAL LEAK RATE TESTING FAILURE OF MAIN STEAM LINE ISOLATION VALVES WITH | | THE UNIT IN COLD SHUTDOWN | | | | DURING THE PERFORMANCE OF LOCAL LEAK RATE TESTING OF THE MAIN STEAM LINE | | ISOLATION VALVES WITH THE UNIT IN COLD SHUTDOWN, THE '2A' AND '2C' MAIN | | STEAM LINES EXCEEDED THE TECHNICAL SPECIFICATION LIMIT OF 11.5 STANDARD | | CUBIC FEET PER HOUR (SCFH). THE LEAK RATES FOR THE '2A' AND '2C' MAIN | | STEAM LINES WERE FOUND TO BE 18.69 SCFH AND 32.02 SCFH, RESPECTIVELY. AT | | THIS TIME, THE LICENSEE DOES NOT KNOW WHETHER OR NOT THE FAILURES OCCURRED | | ON THE INBOARD OR OUTBOARD VALVES. THE '2B' AND '2D' MAIN STEAM LINES WERE | | SATISFACTORILY TESTED. | | | | THE LICENSEE PLANS TO REPAIR AND RETEST THESE VALVES. THE LICENSEE ALSO | | PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30164 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 03/25/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 04:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/25/96 | +------------------------------------------------+EVENT TIME: 02:23[CST]| |NRC NOTIFIED BY: BREWER |LAST UPDATE DATE: 03/25/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | NOTIFIED BY THE TENSAS PARISH (LOUISIANA) EMERGENCY PREPAREDNESS THAT ONE | | EMERGENCY SIREN LOCATED IN THE PARISH INADVERTENTLY ACTUATED DUE TO A | | THUNDERSTORM. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+