U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/04/97 - 04/07/97 ** EVENT NUMBERS ** 31987 32082 32083 32084 32085 32086 32087 32088 32089 32090 32091 32092 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31987 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 17:41 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/13/96 | +------------------------------------------------+EVENT TIME: 00:00[MST]| |NRC NOTIFIED BY: STROUD |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DETERMINATION THAT A LOGGABLE EVENT SHOULD HAVE BEEN CALLED/REPORTED TO THE | | NRC OPERATION CENTER | | | | DURING A SECURITY INSPECTION PERFORMED TODAY (03/20/97), IT WAS DISCOVERED | | THAT A DOCUMENT CONTAINING SAFEGUARDS INFORMATION WAS NOT CONTROLLED IN | | ACCORDANCE WITH 10 CFR 73.71. THE INFORMATION WAS POTENTIALLY SIGNIFICANT | | AND WAS DISCOVERED OUTSIDE THE PROTECTED AREA. THIS EVENT OCCURRED ON | | 09/13/96, AND IT WAS ENTERED AS A LOGGABLE EVENT REPORT. AN ONGOING | | INVESTIGATION BY THE REGION IV SECURITY INSPECTOR DETERMINED THAT THIS | | REPORT SHOULD HAVE BEEN CALLED INTO THE NRC OPERATION CENTER. THE NRC | | REGION IV SECURITY INSPECTOR WAS PROVIDED WITH DETAILS OF THE EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1147 ON 04/04/97, FROM RUSSELL STROUD TAKEN BY BAILEY * * * | | | | SUBSEQUENT REVIEWS OF THIS EVENT REVEALED THAT THE DOCUMENT (ALTHOUGH | | MARKED AS SUCH) WAS NOT SAFEGUARDS INFORMATION, AND IT WAS SUBSEQUENTLY | | DECONTROLLED IN ACCORDANCE WITH SITE PROCEDURES. IT WAS ALSO DETERMINED | | THAT THERE WAS NO EVIDENCE TO SUGGEST THAT THE INFORMATION WAS COMPROMISED | | AS INITIALLY BELIEVED. THEREFORE, THE LICENSEE IS RETRACTING THE INITIAL | | NOTIFICATION, AND THE EVENT HAS BEEN LOGGED IN ACCORDANCE WITH 10 CFR | | 73.71(c) and 10 CFR 73, APPENDIX G.II(b). | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. THE R4DO (POWERS) | | WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32082 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 03:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 01:29[EST]| |NRC NOTIFIED BY: CHRIS REEVES |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS EXPERIENCED AN AUTOMATIC START OF THE STATION EMERGENCY DIESEL | | GENERATORS (EDG) AND AN AUXILIARY BUILDING VENTILATION ISOLATION DUE TO AN | | ELECTRICAL GROUND DURING MAINTENANCE ACTIVITIES. (REFER TO EVENT #32086 | | FOR A SIMILAR EVENT.) | | | | THE FOLLOWING TEXT WAS RECEIVED VIA FACSIMILE FROM THE LICENSEE: | | | | "AT 0129 EST, MODIFICATIONS PERSONNEL WERE DRILLING INTO THE #1-M-1 CONTROL | | PANEL IN PREPARATION OF INSTALLING A METAL PATCH. WHILE DRILLING, THEY | | ACCIDENTALLY DRILLED INTO A CONTROL POWER CABLE (125 VDC) AND CAUSED THE | | NORMAL AC SUPPLY BREAKER (#ACB-1718) TO TRIP OPEN WHICH DEENERGIZED THE | | #1A-A 6.9-KV SHUTDOWN BOARD. THIS RESULTED IN THE #1A-A EDG STARTING AND | | CONNECTING TO THE #1A-A 6.9-KV SHUTDOWN BOARD. THE #2A-A AND #2B-B EDGs | | ALSO STARTED AS EXPECTED DUE TO THE LOSS OF VOLTAGE TO THE #1A-A 6.9-KV | | SHUTDOWN BOARD. THE #2A-A AND #2B-B EDGs DID NOT TIE ONTO THEIR RESPECTIVE | | BOARDS SINCE THEY WERE STILL BEING SUPPLIED BY THEIR NORMAL (OFFSITE) POWER | | SUPPLIES. THE #1B-B EDG DID NOT START SINCE IT IS CURRENTLY INOPERABLE AND | | REMOVED FROM SERVICE UNDER A HOLD ORDER. ALL SYSTEMS RESPONDED CORRECTLY | | TO THE [ENGINEERED SAFETY FEATURE] CONDITION. THE PLANT ALSO RECEIVED AN | | AUXILIARY BUILDING ISOLATION (ABI) DUE TO 1-RM-90-101 AS A RESULT OF THE | | LOSS OF THE 6.9-KV SHUTDOWN BOARD. [LIMITING CONDITIONS FOR OPERATION] | | UNIT 1: NONE, UNIT 2: 3.8.1.1.b (DUE TO THE #1B-B EDG BEING INOPERABLE). | | ABNORMAL OPERATING PROCEDURE #AOP-P.05 WAS IMPLEMENTED DUE TO THE LOSS OF | | POWER TO THE #1A-A 6.9-KV SHUTDOWN BOARD. RECOVERY OF THE PLANT IS IN | | PROGRESS AT THIS TIME." | | | | UNIT 1 SHUT DOWN ON 03/22/97, FOR A REFUELING OUTAGE, AND IT IS CURRENTLY | | DEFUELED. BOTH UNITS SHARE A COMMON SPENT FUEL POOL (SFP). AT THE TIME OF | | THE EVENT, BOTH SFP PUMPS 'A' AND 'B' WERE IN OPERATION. AFTER THE | | SPURIOUS BLACKOUT SIGNAL WAS RECEIVED, ALL UNIT 1 ELECTRICAL LOADS WERE | | STRIPPED INCLUDING SFP PUMP 'A'. OPERATORS RESPONDED PROMPTLY BY PLACING | | THE CONTAINMENT SPRAY PUMP ALIGNED TO UNIT 2 IN SERVICE. SFP TEMPERATURE | | REMAINED AT 97øF DURING THE TRANSIENT. (THE HIGH TEMPERATURE ALARM | | SETPOINT IS 110øF.) A COUPLE OF AIR COMPRESSORS SUPPLYING SERVICE AND | | INSTRUMENT AIR WERE ALSO DEENERGIZED; HOWEVER, NO LOW AIR PRESSURE ALARMS | | WERE RECEIVED. EDG #1A-A WILL REMAIN IN SERVICE CARRYING REQUIRED | | ELECTRICAL LOADS UNTIL CORRECTIVE ACTIONS ARE COMPLETED. THIS INCLUDES | | IDENTIFICATION AND REPAIR OF AFFECTED WIRING. A VISUAL EXAMINATION OF THE | | DAMAGE SHOWED 'GRAZING' OF THE WIRING BUNDLE. THE UNIT 2 EDGs AND | | AUXILIARY BUILDING VENTILATION SYSTEM HAVE BEEN RETURNED TO STANDBY AND | | RESTORED, RESPECTIVELY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32083 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/04/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:32 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/03/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:50[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/04/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |RONALD GARDNER RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC SHUTDOWN OF AUTOCLAVE #2 AT THE 'X-342A' FACILITY DUE TO HIGH | | CONDENSATE LEVEL. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON 4/3/97, AT 1750 HOURS, THE OPERATOR AT 'X-342A', THE FEED VAPORIZATION | | AND FLUORINE GENERATION FACILITY, RECEIVED AN AUDIBLE AND VISUAL ALARM | | INDICATING STEAM SHUTDOWN OF AUTOCLAVE #2. THE INVESTIGATION OF THE ALARM | | REVEALED THAT BOTH 'A' AND 'B' HIGH LEVEL CONDENSATE ALARMS WERE ACTIVATED | | CAUSING THE STEAM TO SHUTDOWN. THE CONDENSATE LEVEL SHUTOFF SYSTEM IS | | PROVIDED TO PREVENT OVERPRESSURIZATION OR A NUCLEAR CRITICALITY IN AN | | AUTOCLAVE FOLLOWING A POSTULATED UF6 RELEASE. THE SYSTEM FUNCTIONS TO | | DETECT EITHER A DRAIN LINE PLUG OR RESTRICTION AND TO SHUT OFF THE STEAM | | FLOW TO THE AUTOCLAVE. (REF. TSR-PORTS REV. 5, SECTION 2.1.3.7) | | | | THE AUTOCLAVE WAS IMMEDIATELY SHUTDOWN AND DECLARED INOPERABLE BY THE PLANT | | SHIFT SUPERINTENDENT AT 1755 HOURS. THERE WAS NO RELEASE OF HAZARDOUS | | MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURES ASSOCIATED WITH THIS | | ACTUATION." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: THIS PREVIOUSLY OCCURRED ON 3/25/97 - SEE EVENT #32014 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32084 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MATTINGLY TESTING SERVICE |NOTIFICATION DATE: 04/04/97 | | CITY: BILLINGS REGION: 4 |NOTIFICATION TIME: 11:03 [ET]| | COUNTY: STATE: MT |EVENT DATE: 04/04/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 07:30[MST]| | DOCKET: |LAST UPDATE DATE: 04/04/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DALE POWERS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BRIAN BUCKLEY, ASST RSO | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STOLEN RADIOGRAPHY CAMERA CONTAINING A LOCKED IR-192 SHIELDED SOURCE - | | | | AT 0730 MST ON 04/04/97, MATTINGLY TESTING SERVICE COMPANY PERSONNEL | | DISCOVERED THAT A LOCKED STORAGE BUILDING AT THEIR FACILITY IN BILLINGS, | | MONTANA, PLACARDED WITH A RADIOACTIVE SYMBOL, HAD BEEN BROKEN INTO; AND | | AN INDUSTRIAL NUCLEAR RADIOGRAPHY CAMERA HAD BEEN STOLEN. THE CAMERA, | | (MODEL #IR-100, SERIAL #4136, LABELED WITH A RADIOACTIVE SYMBOL) CONTAINS | | A 25-CURIE, SEALED, SHIELDED, RADIOACTIVE, IR-192 SOURCE (SERIAL #6420). | | THE $10,000 CAMERA IS APPROXIMATELY 12 INCHES X 8 INCHES X 6 INCHES AND | | WEIGHS APPROXIMATELY 50 POUNDS. THE SOURCE IS LOCKED INSIDE THE UNDAMAGED | | CAMERA; THE METAL KEY WAS NOT STOLEN WITH THE CAMERA. | | | | AT 0900 MST, MATTINGLY PERSONNEL NOTIFIED THE LOCAL SHERIFF ABOUT THE THEFT | | AND PLAN TO SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 30 DAYS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32085 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:15 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 10:45[EST]| |NRC NOTIFIED BY: PHILIP RAINHA |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |R. BARKLEY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STACK RADIATION MONITOR OUT OF SERVICE | | | | AN ENGINEERING ANALYSIS SHOWED THAT THE ADEQUACY OF THE R-14A SAMPLE NOZZLE | | DOES NOT CONFORM TO THE DESCRIPTION CONTAINED IN THE FINAL SAFETY ANALYSIS | | REPORT. THE SAMPLE NOZZLE IS NOT DRAWING A REPRESENTATIVE SAMPLE OF THE | | PROCESS MONITORED. THEREFORE, THE MONITOR IS OUT OF SERVICE. MANUAL | | SAMPLING IS BEING PERFORMED IN ACCORDANCE WITH THE TECHNICAL | | SPECIFICATIONS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32086 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 10:36[EST]| |NRC NOTIFIED BY: PORTER |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTOMATIC START OF THE EMERGENCY DIESEL GENERATORS DUE TO | | LOSS OF POWER TO THE "1A-A" 6.9-KV SHUTDOWN BOARD. (REFER TO EVENT #32082 | | FOR A SIMILAR EVENT.) | | | | AT 1036, MAINTENANCE PERSONNEL WERE CUTTING THE 125 VDC CONTROL POWER CABLE | | AT CONTROL PANEL "1-M-1" FOR THE NORMAL FEEDER BREAKER HAND SWITCH FOR | | 6.9-KV SHUTDOWN BOARD "1A-A." THIS WORK WAS INTENDED TO REPAIR THE DAMAGE | | CAUSED WHEN THE CABLE WAS PENETRATED BY A DRILL BIT AT 0129. WHEN THE | | CABLE WAS CUT, THE ALTERNATE FEEDER BREAKER TO THE "1A-A" SHUTDOWN BOARD | | TRIPPED OPEN UNEXPECTEDLY, WHICH DE-ENERGIZED THE "1A-A" 6.9-KV SHUTDOWN | | BOARD. THE "1A-A" DIESEL GENERATOR STARTED, CONNECTED TO THE BOARD, AND IS | | CURRENTLY SUPPLYING THE "1A-A" SHUTDOWN BOARD LOADS. THE "2A-A" AND "2B-B" | | DIESEL GENERATORS ALSO STARTED BUT DID NOT CONNECT TO THEIR RESPECTIVE | | SHUTDOWN BOARDS, WHICH REMAINED ENERGIZED FROM OFFSITE POWER. THE "1B-B" | | DIESEL GENERATOR, WHICH IS TECHNICALLY INOPERABLE, WAS RUNNING FULLY LOADED | | IN PARALLEL WITH OFFSITE POWER FOR TROUBLESHOOTING AND WAS NOT AFFECTED BY | | THIS EVENT. THE "1B-B," "2A-A," AND "2B-B" DIESEL GENERATORS WERE SHUT | | DOWN USING NORMAL PLANT PROCEDURES. ALL SYSTEMS RESPONDED AS EXPECTED TO | | THE LOSS OF THE "1A-A" SHUTDOWN BOARD. SPENT FUEL POOL COOLING WAS NOT | | AFFECTED. ABNORMAL OPERATING PROCEDURE AOP-05 WAS IMPLEMENTED, AND | | RECOVERY IS IN PROGRESS. AS A RESULT OF THIS EVENT, UNIT 2 ENTERED | | LIMITING CONDITION FOR OPERATION 3.8.1.1 ACTION "C" DUE TO ONE DIESEL | | GENERATOR AND ONE OFFSITE POWER SOURCE BEING INOPERABLE. THE CAUSE OF THE | | BREAKER TRIP IS NOT FULLY UNDERSTOOD AT THIS TIME. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32087 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 14:19 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 13:19[CST]| |NRC NOTIFIED BY: FLACK |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 | | 2 | N Y 36 POWER OPERATION | 36 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE PLANS TO NOTIFY THE MINNESOTA POLLUTION CONTROL AGENCY THAT | | THE NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM (NPDES) LIMITS WILL BE | | EXCEEDED. | | | | THE PLANT WILL EXCEED THE 300 CUBIC FEET PER SECOND BLOWDOWN LIMIT OF THE | | NPDES PERMIT BY AN UNKNOWN AMOUNT DUE TO THE RISING RIVER. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32088 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 11:45[CST]| |NRC NOTIFIED BY: DON NOLDIN |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND |AL CHAFFEE EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DECLARED ALL 5 STATION BATTERIES INOPERABLE DUE THE USE OF | | THE WRONG TESTING METHOD. | | | | THIS CONDITION WAS THE RESULT OF PERFORMING A DISCHARGE PERFORMANCE TEST ON | | THE 5 STATION DC BATTERIES (WHICH ARE BEYOND 85% OF THEIR 10-YEAR DESIGN | | LIFE SPAN) EVERY 60 MONTHS. THIS 60-MONTH INTERVAL IS FOR TESTING | | BATTERIES THAT ARE LESS THAN 85% OF THEIR DESIGN LIFE SPAN. THE LICENSEE | | SHOULD HAVE BEEN USING THE 18-MONTH INTERVAL WHICH IS FOR BATTERIES BEYOND | | 85% OF THEIR 10-YEAR DESIGN LIFE SPAN PER TECHNICAL SPECIFICATION | | SURVEILLANCE 4.15.1.E.4. ALL OF THE BATTERIES ARE OVER 10 YEARS OLD. | | IMMEDIATE CORRECTIVE ACTION IS TO DO A PERFORMANCE TEST. FINAL CORRECTIVE | | ACTION IS TO REPLACE BATTERIES OR HAVE THE 10-YEAR DESIGN LIFE SPAN | | RE-EVALUATED BY THE MANUFACTURER. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32089 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 16:19 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 14:05[CST]| |NRC NOTIFIED BY: HENNIG |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT POINT BEACH HAS BEEN OPERATED WITH NEITHER | | RESIDUAL HEAT REMOVAL (RHR) NORMAL DECAY HEAT REMOVAL LOOP OPERABLE DURING | | PAST REFUELING SHUTDOWN CONDITIONS. | | | | THIS CONDITION WAS DISCOVERED DURING A REVIEW OF NRC INSPECTION REPORT | | EA97-75 DATED 03/03/97. NORMAL RHR DECAY HEAT REMOVAL TAKES SUCTION FROM | | THE "A-LOOP" HOT LEG AND RETURNS TO THE "B-LOOP" COLD LEG. DURING PAST | | PERFORMANCES OF TECHNICAL SPECIFICATION TEST TS-30 (UNIT 1) AND TS-31 (UNIT | | 2), HIGH AND LOW HEAD SAFETY INJECTION CHECK VALVE LEAKAGE TEST, THE RHR | | RETURN WAS ALIGNED TO CORE DELUGE THROUGH VALVES "SI-852A" AND "B," | | POTENTIALLY BYPASSING THE REACTOR CORE. THE FINAL SAFETY ANALYSIS REPORT | | DESCRIPTION FOR THE ANALYZED RHR DECAY HEAT REMOVAL METHOD DOES NOT UTILIZE | | THE CORE DELUGE PATH SINCE TOTAL FLOW MAY NOT PASS THROUGH THE REACTOR CORE | | TO REMOVE DECAY HEAT. | | | | PRESENTLY, UNIT 1 IS OPERATING ON NORMAL RHR DECAY HEAT REMOVAL, AND UNIT 2 | | IS DEFUELED. THE METHOD TO UTILIZE THE CORE DELUGE RHR MODE IS PRESENTLY | | RESTRICTED, AND OTHER METHODS TO PERFORM THE REQUIRED TESTING ARE BEING | | ANALYZED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32090 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 16:37 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: FLACK |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 | | 2 | N Y 36 POWER OPERATION | 36 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT EXISTING SETPOINTS FOR AUTOMATICALLY | | BLOCKING ATWS MITIGATING SYSTEM ACTUATION CIRCUITRY (AMSAC) ACTUATION ON | | BOTH UNITS IS NON-CONSERVATIVE. | | | | DURING THE REVIEW OF AMSAC DESIGN DOCUMENTS AS A RESULT OF A CONDITION | | PREVIOUSLY REPORTED CONCERNING CONFORMANCE WITH LOSS OF FEEDWATER | | ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) LICENSING BASES, IT HAS BEEN | | DETERMINED THAT THE EXISTING SETPOINTS FOR AUTOMATICALLY BLOCKING AMSAC | | ACTUATION ON BOTH UNITS ARE NON-CONSERVATIVE WITH RESPECT TO THE SAFETY | | ANALYSIS REPORT. THIS CONDITION HAS THE EFFECT OF NOT PERMITTING AN AMSAC | | ACTUATION UNTIL INCREASING ABOVE APPROXIMATELY 48% POWER COMPARED TO THE | | REQUIRED 40% SETPOINT. IN ADDITION, AN AMSAC ACTUATION WOULD AUTOMATICALLY | | BE BLOCKED WHEN DECREASING POWER AT APPROXIMATELY 48% POWER COMPARED TO THE | | REQUIRED SETPOINT OF 40%. THIS CONDITION HAS EXISTED SINCE ORIGINAL AMSAC | | SYSTEM INSTALLATION. | | | | AT THE PRESENT TIME, UNIT 1 IS OPERATING AT 100% POWER, AND AMSAC IS | | CONSIDERED TO BE OPERABLE FOR THIS FUNCTION ABOVE 50% POWER. (THERE ARE NO | | LOAD REDUCTIONS PLANNED PRIOR TO CORRECTION OF THIS SETPOINT.) UNIT 2 IS | | CURRENTLY OPERATING AT 36% POWER, AND POWER ESCALATION IS NOT PLANNED UNTIL | | RESOLUTION OF AUXILIARY FEEDWATER SYSTEM PERFORMANCE WITH RESPECT TO THE | | ATWS LICENSING BASIS IS COMPLETE. THE SETPOINTS ARE ANTICIPATED TO BE | | RESET TO THE APPROPRIATE VALUE WITHIN 24 HOURS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32091 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/06/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 13:59 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/06/97 | +------------------------------------------------+EVENT TIME: 13:30[EDT]| |NRC NOTIFIED BY: SINGER |LAST UPDATE DATE: 04/06/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN HANNON EO | |NLCO TECH SPEC LCO A/S |SWEETSER FEMA | | |STUART RUBIN, IRD AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DECLARATION OF AN UNUSUAL EVENT AND INITIATION OF A PLANT COOLDOWN DUE TO | | PRESSURE BOUNDARY LEAKAGE FROM A THIMBLE GUIDE TUBE (TECHNICAL | | SPECIFICATION 3.4.6.2 ACTION STATEMENT REQUIRES THE UNIT TO BE IN COLD | | SHUTDOWN WITHIN 30 HOURS.) | | | | THE PLANT IS COOLING DOWN TO MODE 5 DUE TO PRESSURE BOUNDARY LEAKAGE | | DISCOVERED DURING THE OVERPRESSURE TEST AND LEAK INSPECTION FOLLOWING A | | REFUELING OUTAGE. THE LEAKAGE WAS FROM THIMBLE GUIDE TUBE H-1, AND IT | | MEASURED 1-2 DROPS PER MINUTE. THE CAUSE OF THE LEAKAGE IS UNKNOWN AT THIS | | TIME AND IS BEING INVESTIGATED. THE PLANT IS CURRENTLY COOLING DOWN AND IS | | EXPECTED TO BE IN MODE 5 BEFORE THE 30-HOUR TIME CLOCK EXPIRES. | | | | STATE AND LOCAL AGENCIES WERE NOTIFIED BY THE LICENSEE, AND THE LICENSEE | | PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2145 ON 04/06/97, FROM REIMERS TO GOULD * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 2120 AFTER MODE 5 WAS ENTERED. THE | | TECHNICAL SPECIFICATION ACTION STATEMENT WAS EXITED AT 2114 WHICH WAS THE | | TIME THE UNIT ENTERED MODE 5. THE LICENSEE IS STILL INVESTIGATING THE | | CAUSE OF THE LEAKAGE. | | | | STATE AND LOCAL AGENCIES WERE NOTIFIED BY THE LICENSEE, AND THE LICENSEE | | PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER | | NOTIFIED THE R2DO (SHYMLOCK), NRR EO (HANNON), FEMA (BAGWELL), AND AEOD IRD | | (RUBIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32092 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 03:39[CDT]| |NRC NOTIFIED BY: YURKOVICH |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO IMPLEMENT COMPENSATORY MEASURES WITHIN TEN MINUTES FOR A | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM FUNCTIONS | | | | AT 0339 CDT, THE LICENSEE DISCOVERED THAT COMPENSATORY MEASURES FOR A | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM FUNCTIONS HAD NOT BEEN | | IMPLEMENTED WITHIN TEN MINUTES AS REQUIRED BY THE STATION SECURITY PLAN. | | COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE'S | | INVESTIGATION IS ONGOING. (REFER TO THE HOO LOG FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+