U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/08/96 - 11/12/96 ** EVENT NUMBERS ** 30081 31263 31290 31295 31296 31297 31298 31299 31300 31301 31302 31303 31304 31305 31306 31307 31308 31309 31310 31311 31312 31313 31314 31315 31316 31317 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30081 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LANE CONSTRUCTION CORP, MERIDAN, CT |NOTIFICATION DATE: 03/08/96 | | CITY: MERIDAN REGION: 1 |NOTIFICATION TIME: 09:37 [ET]| | COUNTY: STATE: CT |EVENT DATE: 03/08/96 | |LICENSE#: 06-06284-02 AGREEMENT: N |EVENT TIME: 09:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JAY CRUICKSHANK | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STOLEN TROXLER SOIL MOISTURE DENSITY GAUGE WITH SOURCE INTACT - | | | | BETWEEN 1730 ON MARCH 7, 1996, AND 0900 ON MARCH 8, 1996, A TROXLER SOIL | | MOISTURE DENSITY GAUGE INSIDE ITS STORAGE CASE WAS STOLEN FROM A LOCKED | | CABINET INSIDE A LOCKED STORAGE AREA AT THE LANE CONSTRUCTION CORPORATION | | CORPORATE OFFICE IN MERIDEN, CONNECTICUT. THE CORRECT NUCLEAR SYMBOL WAS | | ON THE GAUGE AND ITS CASE. THE RADIOACTIVE SOURCE IS 8 MILLICURIES OF | | CESIUM-137 AND 40 MILLICURIES OF AMERICIUM-241. THE COST OF THE GAUGE IS | | APPROXIMATELY $5,500. | | | | THE LICENSEE NOTIFIED THE LOCAL POLICE AND WILL SUBMIT A WRITTEN REPORT TO | | THE NRC WITHIN 30 DAYS. | | | | NOTE: REFER TO THE HOO LOG FOR A LICENSEE CONTACT TELEPHONE NUMBER. | | | | * * * 2018 NOVEMBER 11, 1996, UPDATE FROM THE CONNECTICUT RADIATION PROGRAM | | (KEVIN SCOTT) RECEIVED BY TROCINE * * * | | | | THE CONNECTICUT RADIATION PROGRAM DUTY OFFICER (KEVIN SCOTT) REPORTED THAT | | A TROXLER MOISTURE DENSITY GAUGE (MODEL #22276, SOURCE #75-3942) HAD BEEN | | FOUND IN BRANFORD, CONNECTICUT. LOCAL LAW ENFORCEMENT PERSONNEL DETERMINED | | THAT THE GAUGE WAS ORIGINALLY REPORTED TO BE STOLEN FROM LANE CONSTRUCTION | | IN MERIDAN, CONNECTICUT, DURING MARCH OF THIS YEAR. | | | | THE GAUGE WAS FOUND BEHIND AN EXCAVATION COMPANY GARAGE BY THE OWNER'S SON, | | AND THE BOY BROUGHT THE GAUGE HOME. THE EXCAVATION COMPANY'S OWNER | | RECOGNIZED THE GAUGE AND IMMEDIATELY CALLED THE LOCAL FIRE DEPARTMENT. THE | | CONNECTICUT RADIATION PROGRAM DUTY OFFICER RECEIVED NOTIFICATION OF THIS | | ISSUE AT 1856 VIA HIS INTERNAL EMERGENCY RESPONSE ORGANIZATION. HE | | RESPONDED TO THE SCENE AT 2001 AND PERFORMED SURVEYS OF THE GAUGE. THE | | DEVICE WAS FOUND TO BE IN TACT AND LOCKED IN ITS SHIELDED POSITION. IT | | ALSO EXHIBITED NORMAL RADIATION READINGS FOR A TROXLER GAUGE IN THIS | | CONFIGURATION. IN ADDITION, THE CONNECTICUT RADIATION PROGRAM DUTY OFFICER | | PLANS TO INTERVIEW THE INDIVIDUAL WHO FOUND THE GAUGE TO DETERMINE IF HE IN | | ANY WAY UNSHIELDED THE SOURCE. | | | | THE CONNECTICUT RADIATION PROGRAM DUTY OFFICER STATED THAT LANE | | CONSTRUCTION HAD NOT YET BEEN INFORMED BUT THAT THE COMPANY WOULD PROBABLY | | BE NOTIFIED TOMORROW MORNING. THE NRC OPERATIONS CENTER NOTIFIED THE R1DO | | (CONTE). (REFER TO THE HOO LOG FOR CONTACT TELEPHONE NUMBERS FOR THE | | CONNECTICUT RADIATION PROGRAM DUTY OFFICER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/01/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 11:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/01/96 | +------------------------------------------------+EVENT TIME: 09:25[EST]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -COMPONENT COOLING WATER SYSTEM IN AN UNANALYZED CONDITION WHILE DEFUELED- | | | | DURING TESTING OF UNIT 2 WHILE IN A DEFUELED CONDITION, THE LICENSEE | | DETERMINED THAT THE COMPONENT COOLING WATER SYSTEM IS IN AN UNANALYZED | | CONDITION. THIS CONDITION HAS A DIRECT IMPACT ON THE RESIDUAL HEAT REMOVAL | | (RHR) SYSTEM'S CAPABILITY TO REMOVE DECAY HEAT DURING AN ACCIDENT | | CONDITION. THIS CONDITION IS DUE TO ERRORS DISCOVERED IN THE INSTALLED RHR | | HEAT EXCHANGER COMPONENT COOLING FLOW METERS. BY USING ULTRASONIC FLOW | | METERS DURING THE TEST, THE LICENSEE DETERMINED THAT THE INSTALLED METERS | | ARE READING ABOUT 1,000 GPM HIGHER THAN NORMAL (NORMAL IS 3,000 TO 4,000 | | GPM) WHICH IS NON-CONSERVATIVE. THIS INSTRUMENTATION IS USED TO SET THE | | FLOW REQUIRED FOR RHR DURING ACCIDENT CONDITIONS AND TO PERFORM | | SURVEILLANCE TESTING OF THE COMPONENT COOLING WATER PUMPS. DUE TO ACTUAL | | FLOW BEING LOWER THAN INDICATED FLOW DURING COMPONENT COOLING WATER PUMP | | SURVEILLANCES, A DEGRADED PUMP CONDITION WITH PARAMETERS OUTSIDE THOSE THAT | | ARE ACCEPTABLE MAY HAVE GONE UNDETECTED. | | | | THE LICENSEE IS DETERMINING THE CAUSE AND CORRECTIVE ACTIONS AND PLANS TO | | DETERMINE IF THIS CONDITION ALSO EXISTS ON UNIT 1. | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND WILL NOTIFY THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 2014 EST ON 11/8/96, FROM PRIESTLEY TAKEN BY KARSCH * * * | | | | ON 1801 EST ON 11/8/96, THE LICENSEE DETERMINED THAT THE COMPONENT COOLING | | WATER SYSTEM MAY HAVE BEEN IN AN UNANALYZED CONDITION DUE TO A VALVE | | OPERATOR DETERMINED TO BE NON-SAFETY RELATED IN A SAFETY RELATED | | APPLICATION. THE FAILURE MECHANISM FOR THE COMPONENT WOULD HAVE RESULTED | | IN LESS FLOW THAN REQUIRED FOR THE LONG TERM COOLING OF THE RESIDUAL HEAT | | REMOVAL HEAT EXCHANGERS WHEN COMBINED WITH THE PREVIOUSLY IDENTIFIED | | INSTRUMENT INACCURACIES. IN ADDITION, THIS WOULD CAUSE RUN-OUT OF THE | | COMPONENT COOLING WATER PUMPS. THE VALVE OPERATOR WILL BE UPGRADED PRIOR | | TO FUEL RELOAD. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR AND LOWER ALLOWAYS | | CREEK TOWNSHIP. THE HOO NOTIFIED R1DO (RICH CONTE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31290 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/07/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:59 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/07/96 | +------------------------------------------------+EVENT TIME: 14:40[EST]| |NRC NOTIFIED BY: STEVE SUDIGALA |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT SUMPS CONSIDERED INOPERABLE DUE TO GAPS IN THEIR SCREEN. | | | | THE CONTAINMENT RECIRCULATION SUMP IS SEPARATED BY A MESH SCREEN INTO AN | | "A" AND A "B" TRAIN SUMP. THE LICENSEE HAS FOUND TWO GAPS IN THE SCREEN | | MEASURING 1/2 INCH BY 4 FEET AND 2 INCHES BY 2 INCHES. BECAUSE OF THESE | | GAPS THE RECIRCULATION SUMPS HAVE BEEN DECLARED INOPERABLE. THE CAUSE OF | | THE GAPS IS NOT KNOWN. THE GAPS WILL BE REPAIRED PRIOR TO ENTERING MODE 4. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE STATE GOVERNMENT. | | | | HOO NOTE: GAPS IN SUMP SCREENS AND THE POSSIBILITY OF RENDERING SAFETY | | RATED PUMPS INOPERABLE DUE TO THE INGESTION OF DEBRIS HAS BEEN DISCUSSED IN | | AEOD REPORTS; AEOD/T916 AND AEOD/T923. | | | | * * * UPDATE ON 11/8/96, AT 1828 EST FROM MARTIN TAKEN BY KARSCH * * * | | | | THE CONTAINMENT SUMP SCREENS WERE INSPECTED AND THE LICENSEE FOUND THAT THE | | MESH SIZE FOR THE OUTER SCREEN IS SMALLER THAN THE SIZE SPECIFIED IN THE | | DESIGN DOCUMENTS. THE LICENSEE IS EVALUATING THE CONSEQUENCES OF A SMALLER | | MESH SIZE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R1DO | | (RICH CONTE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 11/08/96 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 05:46 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/08/96 | +------------------------------------------------+EVENT TIME: 05:05[EST]| |NRC NOTIFIED BY: KITCHEN |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |PHILLIP MCKEE, NRR EO | | |JOHN DAVIDSON, NMSS IAT | | |NANCY ERVIN, NRR IAT | | |AL GIBSON R2 | | |JORDAN, BARRETT AEOD | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 30 POWER OPERATION | 30 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - | | | | ACTUAL TAMPERING WITH SECURITY EQUIPMENT EVENT. IMMEDIATE COMPENSATORY | | MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE DID NOT NOTIFY THE LOCAL | | LAW ENFORCEMENT AGENCY OR ISSUE A PRESS RELEASE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO LOG | | FOR DETAILS.) | | | | NOTE: SEE EVENT #31304 FOR A RELATED SECURITY EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31296 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 11/08/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 09:37 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/02/96 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: BROWN/SACHATELLO |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH CONTE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |AL CHAFFEE EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO WORKERS RECEIVED INTERNAL AND EXTERNAL CONTAMINATION (ALPHA | | CONTAMINATION AND COBALT-60 CONTAMINATION) ON 11/02/96 WHILE WORKING IN THE | | REFUEL TRANSFER CANAL. | | | | ON 11/02/96, A PLANT MAINTENANCE SUPERVISOR AND A WESTINGHOUSE REFUELING | | VENDOR WERE WORKING IN THE REFUEL TRANSFER CANAL. THEY WERE PERFORMING A | | INSPECTION OF THE TRANSFER CART MECHANISM AND ALSO REMOVING FOREIGN | | MATERIAL (HOUSE KEEPING DUTIES) FOUND IN THE REFUEL TRANSFER CANAL AREA. | | THEY REMOVED SOME PAINT CHIPS (FOREIGN MATERIAL) FROM BEHIND THE FUEL CART | | BICYCLE CHAIN AND PLACED THESE PAINT CHIPS IN A PLASTIC BAG (BAG IS 4' LONG | | BY 3'WIDE). WHILE THEY WERE BEING FRISKED, THE PLASTIC BAG WAS SURVEYED | | USING AN EVERLINE RO2A. AT 12" FROM THE PLASTIC BAG, THE EVERLINE RO2A | | READING WAS 600 mrem/hr (CONTACT READING OF THE BAG WAS 20 R/hr). IT WAS | | DETERMINED THAT A CONTAMINATION SPREAD HAD OCCURRED WHILE THE TWO MEN WERE | | COLLECTING THE PAINT CHIPS. AS A RESULT OF THE CONTAMINATION SPREAD, IT | | WAS DETERMINED THAT THE TWO MEN HAD EITHER BREATHED OR HAD SWALLOWED SOME | | CONTAMINATION. THE TWO MEN TOOK A SHOWER, AND AROUND 1000 EST ON 11/02/96, | | THE MEN WERE GIVEN A GAMMA WHOLE BODY COUNT. THE GAMMA WHOLE BODY COUNT | | DETECTS BOTH EXTERNAL AND INTERNAL CONTAMINATION. THE GAMMA WHOLE BODY | | HIGHEST READING FOR THE TWO MEN WAS 1000 NANOCURIES (MOSTLY COBALT-60). A | | PRESS RELEASE WAS MADE BY THE LICENSEE OF THIS EVENT ON 11/02/96. THE | | HIGHEST READING GAMMA WHOLE BODY COUNT PERFORMED ON THESE TWO MEN ON | | 11/07/96, WAS 20 NANOCURIES (COBALT-60). THE LICENSEE IS TRYING TO | | QUANTIFY THE AMOUNT OF DOSE EACH INDIVIDUAL RECEIVED USING A GAMMA WHOLE | | BODY COUNTER FOR THE GAMMA RAYS AND USING DOSE ASSESSMENT FOR THE ALPHA | | ACTIVITY. | | | | THE LICENSEE PLANS TO HAVE AN INDEPENDENT EXPERT REVIEW THE RESULTS OF | | THEIR CALCULATIONS. THE LICENSEE ALSO PLANS TO MAKE A PRESS RELEASE ON | | THIS EVENT TODAY (11/08/96). AN NRC REGION 1 REPRESENTATIVE (MR. NIMITZ) | | LEFT THE LICENSEE'S SITE TODAY AFTER LOOKING INTO THIS EVENT. THE LICENSEE | | ALSO REPORTED THIS EVENT UNDER 10 CFR 20.2203(a)(2)(i) WHICH STATES THAT | | THEY WILL SUBMIT A WRITTEN REPORT ON THIS EVENT. THE LICENSEE NOTIFIED THE | | STATE AND THE NRC RESIDENT INSPECTOR OF THIS EVENT. THE STATE OF | | CONNECTICUT WAS NOTIFIED TODAY AT 0930 EST. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31297 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: N.C. DIV. OF RAD PROTECTION |NOTIFICATION DATE: 11/08/96 | | CITY: RALEIGH REGION: 2 |NOTIFICATION TIME: 10:47 [ET]| | COUNTY: STATE: NC |EVENT DATE: 11/01/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 09:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/08/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SPEIGHT | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NORTH CAROLINA DIVISION OF RADIATION PROTECTION WAS NOTIFIED BY TROXLER | | ELECTRONICS LABS, THAT A TROXLER MOISTURE DENSITY GAUGE (MODEL #4232, | | SERIAL #261) WAS MISPLACED. THIS OCCURRED WHEN A TROXLER EMPLOYEE SENT | | THIS EQUIPMENT BY FEDEX FROM ATLANTA, GEORGIA, TO TROXLER FACILITIES IN THE | | RALEIGH, NORTH CAROLINA. FEDEX IS CURRENTLY LOOKING FOR THE DEVICE. THEY | | HAVE SEARCHED THEIR ATLANTA TERMINAL AND THEIR HUB IN MEMPHIS, BUT THEY | | HAVE NOT FOUND THE DEVICE. THE DEVICE CONTAINED 100 MICROCURIES OF | | CALIFORNIUM. THE STATE DID NOT NOTIFY THE NRC IMMEDIATELY BECAUSE THEY | | THOUGHT THE GAUGE WOULD HAVE BEEN FOUND BEFORE NOW. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PROFESSIONAL SERVICE INDUSTRIES INC |NOTIFICATION DATE: 11/08/96 | | CITY: BRISTOL REGION: 2 |NOTIFICATION TIME: 11:16 [ET]| | COUNTY: STATE: VA |EVENT DATE: 05/01/96 | |LICENSE#: 45-25088-01 AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/08/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ACKERMANN | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE EXPOSURE TO A PROFESSIONAL SERVICE INDUSTRIES, INC. TECHNICIAN'S | | EXTREMITY (POSSIBLY IN EXCESS OF 50 REM) DURING DIRECT HANDLING OF A | | PORTABLE MOISTURE DENSITY GAUGE SOURCE ROD OVER A 6-MONTH TIME PERIOD | | | | WHILE WORKING OUT OF THE LICENSEE'S BRISTOL, VIRGINIA, OFFICE AT LOCATIONS | | IN BOTH VIRGINIA AND TENNESSEE, A TECHNICIAN WAS DIRECTLY HANDLING THE | | SOURCE ROD OF A PORTABLE MOISTURE DENSITY GAUGE OVER A TIME PERIOD FROM MAY | | 1996 TO THE END OF OCTOBER 1996. DIRECT HANDLING OF THE SOURCE ROD | | OCCURRED WHEN THE INDIVIDUAL OPENED THE SHUTTER ON THE BOTTOM OF THE DEVICE | | AND POSITIONED OF THE ROD INTO THE HOLE FOR TESTING. THE MOISTURE DENSITY | | GAUGE WAS A CAMPBELL PACIFIC NUCLEAR DEVICE (MODEL NUMBER MC-1), AND IT | | CONTAINED A 10-MILLICURIE CESIUM-137 SEALED SOURCE. | | | | AT THIS TIME, THE INDIVIDUAL DOES NOT EXHIBIT ANY SIGNIFICANT PHYSICAL | | EFFECTS FROM THE DIRECT HANDLING OF THE SOURCE ROD, AND THE LICENSEE DOES | | NOT HAVE AN ACCURATE ESTIMATE OF THE EXPOSURE RECEIVED BY THE INDIVIDUAL. | | THE INDIVIDUAL WAS WEARING A WHOLE BODY DOSIMETER BUT BELIEVES THAT IT | | WOULD HAVE BEEN SHIELDED BY THE DEVICE. THE INDIVIDUAL WAS NOT WEARING AN | | EXTREMITY MONITORING DEVICE BECAUSE CONTACT WITH THE SOURCE ROD WAS NOT | | EXPECTED. THE LICENSEE BELIEVES THAT THE INDIVIDUAL PRIMARILY USED ONE | | HAND BUT MAY HAVE SWITCHED HANDS OCCASIONALLY. THE LICENSEE ALSO BELIEVES | | THAT THE INDIVIDUAL'S BODY WAS SHIELDED BY THE DEVICE AND ITS INTERNAL | | SHIELDING BASED UPON THE INDIVIDUAL'S DESCRIPTION. AN EXAMINATION AT A | | MEDICAL FACILITY NOTED A COUPLE OF EXTREMELY SUPERFICIAL BLISTERS ON THE | | INDIVIDUAL'S LEFT HAND. | | | | AN NRC REGION 2 INSPECTOR WAS ON SITE YESTERDAY AND WAS AWARE OF THIS | | EVENT. (REFER TO THE HOO LOG FOR LICENSEE CONTACT TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31299 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/08/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/08/96 | +------------------------------------------------+EVENT TIME: 13:02[CST]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |AAAA 50.72 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL THREE STEAM GENERATORS ARE IN CATEGORY C-3 AS A RESULT OF | | NON-DESTRUCTIVE TESTING. | | | | STEAM GENERATOR INSPECTIONS HAVE DETERMINED THAT MORE THAN 1% OF THE TUBES | | IN EACH STEAM GENERATOR ARE DEFECTIVE. THUS ALL THREE STEAM GENERATOR'S | | INSPECTION RESULTS MEET THE C-3 CATEGORY. THE GENERAL AREA OF DEGRADATION | | IS IN THE TUBE EXPANSION AREA OF THE TUBE SHEET. THE CAUSE OF THE DAMAGE | | IS THOUGHT TO BE A COMBINATION OF OUTSIDE DIAMETER AND INSIDE DIAMETER | | STRESS CORROSION CRACKING. PRELIMINARY RESULTS ARE STEAM GENERATOR | | "A"-12.75%, "B"-4.05%, "C"-7.40%. THE LICENSEE HAS CONCLUDED THAT THESE | | RESULTS WARRANT A VOLUNTARY REPORT. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31300 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/08/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/08/96 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT PURGE AND EXHAUST VALVES FAILED THEIR STROKE TIME TESTS. | | | | THE LICENSEE'S FSAR CHAPTER 15 ANALYSIS ASSUMES THAT CONTAINMENT | | VENTILATION SYSTEM PURGE AND EXHAUST VALVES WILL CLOSE IN 5.89 SECONDS OR | | LESS TO MITIGATE THE CONSEQUENCES OF A DROPPED FUEL ASSEMBLY. THE LICENSEE | | CHANGED THEIR TEST PROCEDURE AND NOW TESTS THE STROKE TIME FOR THESE VALVES | | IN A MORE PRECISE AND CONSERVATIVE MANNER. USING THIS NEW PROCEDURE THE | | STROKE TIMES FOR THE VALVES ARE AROUND TEN SECONDS. THE PURGE AND EXHAUST | | VALVES HAVE BEEN CLOSED AND WILL REMAIN CLOSED UNTIL THE TESTING ISSUE IS | | RESOLVED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE STATE GOVERNMENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31301 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/08/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/08/96 | +------------------------------------------------+EVENT TIME: 15:58[EST]| |NRC NOTIFIED BY: KEN BURTON |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT PIPING PENETRATIONS WERE NOT ADEQUATELY ANALYZED. | | | | WHILE PERFORMING SYSTEM REVIEWS COMMITTED TO IN LER 96-007 THE LICENSEE | | DETERMINED THAT NUMEROUS PIPING PENETRATIONS THROUGH CONTAINMENT WERE NOT | | ADEQUATELY ANALYZED TO ACCOUNT FOR POST ACCIDENT PRESSURE AND TEMPERATURE | | LOADS ON SYSTEM OPERABILITY. THESE POST ACCIDENT LOADS COULD CAUSE | | OPERATIONAL FAILURE OF THE SYSTEMS EVEN THOUGH THE PRESSURE BOUNDARY WOULD | | REMAIN INTACT. SOME OF THE AFFECTED SYSTEMS ARE NORMAL CHARGING, REACTOR | | COOLANT PUMP SEAL INJECTION, MAIN STEAM PIPING TO THE SAFETY VALVES, | | AUXILIARY FEEDWATER, POST-ACCIDENT SAMPLING, CONTAINMENT HYDROGEN | | MONITORING AND RECOMBINER, CONTAINMENT VACUUM/PURGE, AND VARIOUS | | INSTRUMENTATION SYSTEMS. NO IMMEDIATE ACTIONS ARE PLANNED BY THE LICENSEE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE STATE AND LOCAL | | GOVERNMENTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31302 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ARMAMENT & CHEM AQUIS & LOGISTICS |NOTIFICATION DATE: 11/08/96 | | CITY: FORT BRAGG REGION: 2 |NOTIFICATION TIME: 17:11 [ET]| | COUNTY: HARNETT & HOKE STATE: NC |EVENT DATE: 11/07/96 | |LICENSE#: 12-00722-06 AGREEMENT: Y |EVENT TIME: 10:45[EST]| | DOCKET: |LAST UPDATE DATE: 11/08/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | |MICHAEL WEBER EO | +------------------------------------------------+ | |NRC NOTIFIED BY: BETTY PETERSON |MICHAEL JORDAN RGN3 | |HQ OPS OFFICER: RUDY KARSCH |RICHARD BARRETT AEOD | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE ARMY ARMAMENT AND CHEMICAL ACQUISITION AND LOGISTICS ACTIVITY LOCATED | | IN ROCK ISLAND, ILLINOIS, REPORTED THAT TRITIUM SOURCES WERE BROKEN IN THE | | ARMS ROOM OF THE 504TH INFANTRY IN FORT BRAGG, NORTH CAROLINA. | | | | AS MANY AS FOUR SOURCES CONTAINING A TOTAL OF 3.2 Ci OF TRITIUM WERE | | BROKEN, AND TWO PEOPLE MAY HAVE BEEN EXPOSED. BIO-ASSAYS HAVE BEEN TAKEN. | | THE ROOM HAS BEEN SURVEYED AND THE AREA OF THE BREAKAGE READS 50,000 | | DISINTEGRATIONS PER MINUTE (DPM). OTHER AREAS WITHIN THE ROOM READ BETWEEN | | 2,000 TO 8,000 DPM. THE ROOM HAS BEEN CLOSED OFF AND CLEAN UP BEGUN. ROCK | | ISLAND WILL DISPATCH A HEALTH PHYSICIST ON TUESDAY TO INSPECT THE FACILITY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31303 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/08/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:38 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/08/96 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: KURT KRUDGER |LAST UPDATE DATE: 11/08/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 87 POWER OPERATION | 87 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SINGLE CONTROL ROD SCRAM OCCURRED DUE TO A BLOWN FUSE. | | | | THE LICENSEE WAS ENGAGED IN TURBINE VALVE TESTING. DURING THIS TESTING, A | | HALF SCRAM OCCURRED ON THE "A" RPS CHANNEL. A FUSE FOR ROD 42-07 IN THE | | "B" RPS CHANNEL WAS BLOWN COMPLETING THE LOGIC FOR A FULL SCRAM. THE ROD | | INSERTED FULLY AND WAS SUBSEQUENTLY RETURNED TO ITS FULL OUT POSITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND LOWER ALLOWAYS CREEK | | TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31304 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 11/09/96 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 00:34 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/08/96 | +------------------------------------------------+EVENT TIME: 22:19[EST]| |NRC NOTIFIED BY: BOB KITCHEN |LAST UPDATE DATE: 11/09/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |PHILLIP MCKEE, NRR EO | | |NANCY ERVIN, NRR IAT | | |JOE YARDUMIAN, NMSS IAT | | |AL GIBSON R2 | | |JORDAN, BARRETT AEOD | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 36 POWER OPERATION | 36 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - | | | | ACTUAL TAMPERING WITH SECURITY EQUIPMENT EVENT. IMMEDIATE COMPENSATORY | | MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE DID NOT NOTIFY THE LOCAL | | LAW ENFORCEMENT AGENCY OR ISSUE A PRESS RELEASE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO LOG | | FOR DETAILS.) | | | | NOTE: SEE EVENT #31295 FOR A RELATED SECURITY EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31305 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/09/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 11:07 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/09/96 | +------------------------------------------------+EVENT TIME: 06:48[CST]| |NRC NOTIFIED BY: TOD MOSER |LAST UPDATE DATE: 11/09/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL REACTOR TRIP OF CONTROL BANK 'D' DURING A ROD DROP TEST - | | | | WITH THE REACTOR SUBCRITICAL AND CONTROL BANK 'D' (5 CONTROL RODS) | | WITHDRAWN, CONTROL ROOM OPERATORS WERE PERFORMING A ROD DROP TEST AND A | | DIGITAL ROD POSITION INDICATION SYSTEM TEST. | | | | WHEN THE CONTROL ROOM OPERATORS RECEIVED AN ERRONEOUS INDICATION FOR | | CONTROL ROD #M-4 OF CONTROL BANK 'D', THEY MANUALLY OPENED THE REACTOR TRIP | | BREAKERS AS A CONSERVATIVE ACTION. ALL 5 CONTROL RODS INSERTED COMPLETELY. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE ERRONEOUS INDICATION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31306 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 11/09/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/09/96 | +------------------------------------------------+EVENT TIME: 13:40[CST]| |NRC NOTIFIED BY: CURT BASNER |LAST UPDATE DATE: 11/09/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BYPASS FLOW AROUND AUXILIARY BUILDING CHARCOAL EXHAUST FILTERS COULD RESULT | | IN A SUBSTANTIAL INCREASE IN DOSE AT THE SITE BOUNDARY. | | | | THE LICENSEE DISCOVERED THAT REMOVAL OF A BLOCK WALL TO FACILITATE | | REFUELING OPERATIONS ALLOWS FUEL BUILDING VENTILATION AIR FLOW TO BYPASS | | THE AUXILIARY BUILDING CHARCOAL EXHAUST FILTERS. THE BYPASS FLOW IS | | DIVERTED THROUGH THE UNIT 2 PIPE TUNNEL. THIS TUNNEL HAS RADIATION | | MONITORS WHICH WHEN ACTUATED CAN ROUTE THE AIR BACK THROUGH THE AUX | | BUILDING FILTERS. THE LICENSEE HAS CONSERVATIVELY ASSUMED THAT THIS SAFETY | | FUNCTION WILL FAIL. | | | | THE LICENSEE'S UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) ACCIDENT | | ANALYSIS ASSUMES THAT FOLLOWING A FUEL HANDLING ACCIDENT IN THE FUEL | | BUILDING ALL THE IODINE RELEASED IN THE FUEL BUILDING PASSES THROUGH THE | | AUX BUILDING CHARCOAL EXHAUST FILTERS BEFORE RELEASE TO THE ATMOSPHERE. THE | | BYPASS FLOW WAS MEASURED AT APPROXIMATELY ONE THIRD OF THE TOTAL FLOW. THE | | PRESENT UFSAR CALCULATED POST ACCIDENT DOSE AT THE SITE BOUNDARY IS 27.2 | | REM. THE NEW POST-ACCIDENT DOSE ASSUMING UNFILTERED RELEASE OF THE BYPASS | | FLOW IS CALCULATED AS 108.7 REM AT THE SITE BOUNDARY. | | | | THE LICENSEE HAS SUSPENDED MOVEMENT OF IRRADIATED FUEL AND MOVEMENT OF FUEL | | OR COMPONENTS OVER IRRADIATED FUEL. POSSIBLE CORRECTIVE ACTIONS ARE UNDER | | EVALUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31307 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 11/09/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 21:13 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/09/96 | +------------------------------------------------+EVENT TIME: 08:41[EST]| |NRC NOTIFIED BY: LARRY GGRMARD |LAST UPDATE DATE: 11/09/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 115 KV OFF SITE LINE INSTABILITY DUE TO A GROUND FAULT ON THE 115 KV | | SYSTEM. | | | | AN ELECTRICAL DISTURBANCE ON THE 115 KV INCOMING LINE TRIPPED A 115 KV | | SUPPLY BREAKER (K207-1) AND THE BREAKER "KR-1" FOR THE VOLTAGE BOOST | | CAPACITOR BANKS. THE OTHER INCOMING LINE BREAKER, "K69-7" WAS OUT OF | | SERVICE FOR REPAIR AT THE TIME. THE PLANT WAS ON LINE AT THE TIME AND | | USING STATION SERVICE POWER FOR IN HOUSE LOADS. PLANT OPERATION WAS NOT | | ADVERSELY IMPACTED BY THE ELECTRICAL DISTURBANCE; ALL SYSTEMS CONTINUED TO | | PERFORM NORMALLY. BOTH EMERGENCY DIESEL GENERATORS WERE OPERABLE | | THROUGHOUT THE EVENT. REPAIRS WERE COMPLETED AND SYSTEMS RETURNED TO | | NORMAL AT 1904 EST. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31308 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 11/10/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 00:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/09/96 | +------------------------------------------------+EVENT TIME: 22:45[EST]| |NRC NOTIFIED BY: ALVIN PURDUE |LAST UPDATE DATE: 11/10/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE 2B EMERGENCY DIESEL GENERATOR AUTO STARTED AND LOADED DURING A FAILED | | ATTEMPT TO START THE 2D REACTOR COOLANT PUMP AS PART OF PLANT HEATUP. | | | | "TRAIN 2B D/G AUTO STARTED DUE TO UNDERVOLTAGE ON TRAIN 2B 4160 ESSENTIAL | | BUS. THE EVENT WAS CAUSED BY LOSS OF POWER TO THE TRAIN 2B 4160 ESSENTIAL | | BUS FROM THE 6900 VOLT BUS THAT SUPPLIES THE 4160 BUS. THE 6900 VOLT BUS | | WAS "LOCKED OUT" BY ACTUATION OF AN OVERCURRENT RELAY ACTUATED WHILE | | STARTING THE 2D REACTOR COOLANT PUMP. THE D/G SUCCESSFULLY LOADED THE | | TRAIN B 4160 ESSENTIAL BUS AND ALL SYSTEMS FUNCTIONED AS REQUIRED. PLANT | | HEATUP FOR UNIT RESTART WAS IN PROGRESS AND IS STOPPED UNTIL POWER IS | | RESTORED TO THE ESSENTIAL BUS. PLANS ARE TO RESTORE POWER TO THE BUS FROM | | NORMAL POWER UPON COMPLETION OF AN INVESTIGATION OF THE FAILURE." | | | | THE 2A 4160 ESSENTIAL BUS REMAINED ENERGIZED THROUGHOUT THIS EVENT. THE 2D | | REACTOR COOLANT PUMP REMAINS DEENERGIZED AT THIS TIME WITH NO INDICATION OF | | DAMAGE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31309 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 11/10/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 01:04 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/09/96 | +------------------------------------------------+EVENT TIME: 23:39[EST]| |NRC NOTIFIED BY: ALVIN PURDUE |LAST UPDATE DATE: 11/10/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE 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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL START OF BOTH MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS DURING STARTUP | | DUE TO LOSS OF MAIN FEEDWATER PUMP. | | | | "MANUAL START OF TRAIN "A" AND TRAIN "B" AUXILIARY FEEDWATER MOTOR DRIVEN | | PUMPS DUE TO LOSS OF MAIN FEEDWATER PUMP. THE LOSS OF THE MAIN FEEDWATER | | PUMP OCCURRED WHEN THE STEAM SUPPLY TO THE PUMPS WAS INTERRUPTED FROM THE | | AUXILIARY ELECTRIC BOILER "A" DUE TO THE RECIRCULATION PUMP MALFUNCTIONING. | | THE UNIT WAS IN MODE 3 PREPARING FOR STARTUP. THE STARTUP HAS BEEN SECURED | | UNTIL STEAM CAN BE SUPPLIED TO THE MAIN FEEDWATER PUMPS FROM THE AUXILIARY | | ELECTRIC BOILERS. THE CAUSE OF THE "A" AUXILIARY ELECTRIC BOILER | | RECIRCULATION PUMP TRIPPING IS NOT KNOWN AT THIS TIME AND IS UNDER | | INVESTIGATION." | | | | THE "B" MAIN FEEDWATER WAS IN SERVICE AT THE TIME OF THE EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31310 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/10/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 10:15 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/09/96 | +------------------------------------------------+EVENT TIME: 22:20[EST]| |NRC NOTIFIED BY: DICK SMEDLEY/SHERI KING |LAST UPDATE DATE: 11/10/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IS MAKING THIS REPORT UNDER FITNESS FOR DUTY. | | | | THE LICENSEE DISCOVERED A HALF FULL BOTTLE WITH A WHISKEY LABEL IN A WASTE | | BASKET INSIDE THE MEN'S ROOM LOCATED IN THE PROTECTED AREA. JANITORS | | EMPTYING THE WASTE BASKET FOUND THE BOTTLE WRAPPED IN A PLASTIC BAG UNDER | | THE WASTE BASKET LINER. THE BOTTLE HAS BEEN PRESERVED FOR FINGERPRINT | | ANALYSIS. THE LICENSEE HAS DOCUMENTED THIS PROBLEM AND WILL CONTINUE THEIR | | INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND WILL INFORM RIII (JIM | | CREED). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31311 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 11/11/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 11:39 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 06:56[CST]| |NRC NOTIFIED BY: JAY DRESSEN |LAST UPDATE DATE: 11/11/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED OVERSPEED TRIP OF THE 'A' TRAIN DIESEL GENERATOR WHILE POWER | | SUPPLIES WERE BEING SWITCHED TO THE 'A' TRAIN SAFEGUARDS ELECTRICAL BUS | | | | ON NOVEMBER 11, 1996, OPERATIONS PROCEDURE N-EHV-39, 4160-VAC SUPPLY AND | | DISTRIBUTION OPERATION, WAS BEING PERFORMED WITH THE UNIT IN REFUELING | | SHUTDOWN IN ORDER TO SWITCH POWER SUPPLIES TO THE 'A' TRAIN SAFEGUARDS | | ELECTRICAL BUS. WHEN THE NUCLEAR CONTROL OPERATOR ATTEMPTED TO SWITCH THE | | POWER SUPPLIES, THE 'A' TRAIN SAFEGUARDS BUS TEST POWER AND AUTOMATIC | | VOLTAGE RESTORING CIRCUITRY RESTORED POWER TO THE BUS IN APPROXIMATELY ONE | | SECOND. AS PART OF THE AUTOMATIC VOLTAGE RESTORING CIRCUITRY, THE 'A' | | TRAIN DIESEL GENERATOR IS EXPECTED TO START. THE 'A' TRAIN DIESEL | | GENERATOR DID START AS EXPECTED, BUT IT UNEXPECTEDLY TRIPPED ON OVERSPEED. | | DURING THIS EVENT, THE 'B' TRAIN CONTROL ROOM AIR CONDITIONERS STARTED AS | | DESIGNED, AND ALL OTHER SYSTEMS FUNCTIONED AS EXPECTED. | | | | DURING THE INVESTIGATION OF THIS EVENT, IT WAS NOTED THAT THE NUCLEAR | | CONTROL OPERATOR FAILED TO PERFORM A STEP IN PROCEDURE N-EHV-39 WHICH | | ALLOWS MANUAL TRANSFER OF POWER SUPPLIES TO THE 'A' TRAIN SAFEGUARDS BUS. | | THE LICENSEE'S INVESTIGATION AS TO WHY THE 'A' TRAIN DIESEL GENERATOR | | TRIPPED DUE TO AN OVERSPEED CONDITION IS CURRENTLY ONGOING. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31312 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 11/11/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 13:31 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 12:50[EST]| |NRC NOTIFIED BY: DANIEL BOYLE |LAST UPDATE DATE: 11/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE/REG 1 RDO | |NONR OTHER UNSPEC REQMNT |PHILLIP MCKEE/NRR EO | | |MICHAEL WEBER/NMSS EO | | |STUART RUBIN/IRD AEOD | | |EDWARD MCALPINE R2DO | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 75 POWER OPERATION | 75 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RECEIPT OF A PRESSURIZED DEMINERALIZER SHIPMENT WITH CONTACT RADIATION | | LEVELS IN EXCESS OF NRC LIMITS | | | | AT 1250 EST ON NOVEMBER 11, 1996, THE CONTROL ROOM WAS NOTIFIED BY LICENSEE | | EFFLUENTS MANAGEMENT PERSONNEL THAT A PRESSURIZED DEMINERALIZER SHIPPED ON | | A FLAT-BED TRAILER TO SUSQUEHANNA STEAM ELECTRIC STATION HAD CONTACT | | RADIATION LEVELS IN EXCESS OF NRC LIMITS. THE INCOMING HEALTH PHYSICS | | SURVEY DETECTED RADIATION LEVELS OF 280 mR/HOUR (ON CONTACT) ON THE BOTTOM | | EXTERNAL SURFACE, THE SHIPMENT VENDOR'S SURVEY DOCUMENTED 240 mR/HOUR, AND | | THE LIMIT SPECIFIED IN 10 CFR 71.47 IS LESS THAN 200 mR/HOUR. | | | | THE SHIPMENT VENDOR WAS VECTRA, AND THE SHIPMENT ORIGINATED IN COLUMBIA, | | SOUTH CAROLINA. THE SHIPMENT INCLUDED FOUR PRESSURIZED DEMINERALIZERS | | WITHOUT PACKAGES, AND ONLY ONE OF THE FOUR DEMINERALIZERS EXHIBITED THE | | ELEVATED READINGS. | | | | THE LICENSEE BROUGHT THE DEMINERALIZERS ON SITE AND POSTED THEM FOR | | RADIOLOGICAL CONDITIONS. THE LICENSEE ALSO NOTIFIED BOTH THE SHIPMENT | | VENDOR (VECTRA) AND THE NRC RESIDENT INSPECTOR OF THIS EVENT. | | | | THIS ISSUE WAS REPORTED BY THE LICENSEE AS A 1-HOUR NOTIFICATION IN | | ACCORDANCE WITH 10 CFR 20.1906(d). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31313 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 11/11/96 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 15:04 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 13:50[EST]| |NRC NOTIFIED BY: MONT SECKENS |LAST UPDATE DATE: 11/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A SUSPECTED OIL SPILL BELOW GROUND | | | | AT 1350, THE LICENSEE MADE AN OFFSITE NOTIFICATION TO THE MARYLAND | | DEPARTMENT OF THE ENVIRONMENT DUE TO THE SUSPICION OF AN OIL SPILL BELOW | | GROUND (#2 FUEL OIL) EAST OF THE 21 FUEL OIL STORAGE TANK. THE AMOUNT OF | | THE SPILL IS UNKNOWN, AND NO UNACCOUNTED LOSSES OF FUEL OIL HAVE BEEN | | DETECTED. ALL FUEL OIL STORAGE TANK LEVELS AND DAY TANK LEVELS APPEAR TO | | BE STABLE. | | | | THE SUSPECTED OIL LEAK WAS DISCOVERED WHILE LICENSEE PERSONNEL WERE | | DRILLING TEST WELLS FOR PLACING ANODES ON PIPES. APPARENTLY, LICENSEE | | PERSONNEL NOTICED OIL ON THE DRILL BIT, AND LICENSEE ENVIRONMENTAL | | PERSONNEL DETERMINED THAT THE OIL WAS FRESH RATHER THAN OLD. THE LICENSEE | | PLANS TO DO SOME EXCAVATING USING HAND SHOVELS TO TRY TO DETERMINE THE | | SOURCE OF THE SUSPECTED LEAK. THE LICENSEE CURRENTLY BELIEVES THAT THE | | SOURCE MAY BE A PIPE LEAK, BUT THE LICENSEE DOES NOT BELIEVE THAT THERE IS | | A BELOW GROUND TANK RUPTURE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31314 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 11/11/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:18 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 15:40[CST]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 11/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR THE GENERATION OF A WATER HAMMER INSIDE THE COMPONENT COOLING | | WATER (CCW) PIPING DURING SPECIFIC DESIGN BASIS EVENTS | | | | WITH THE UNIT IN COLD SHUTDOWN, THE LICENSEE DETERMINED THAT THE | | CONTAINMENT AIR COOLERS WOULD NOT FUNCTION AS REQUIRED FOR UPDATED SAFETY | | ANALYSIS REPORT, CHAPTER 14, DESIGN BASIS EVENTS. DURING A LOSS OF COOLANT | | ACCIDENT OR MAIN STEAM LINE BREAK EVENT COINCIDENT WITH A LOSS OF POWER, | | THE CCW PIPING INSIDE THE CONTAINMENT AIR COOLERS WOULD GENERATE AN | | INTERNAL STEAM BUBBLE; AND UPON RESTART OF THE CCW PUMPS, THE STEAM BUBBLE | | WOULD COLLAPSE AND GENERATE A WATER HAMMER INSIDE THE CCW PIPING. | | | | THE WATER HAMMER LOADS ARE BEING ANALYZED AT THIS TIME, AND NO RESULTS ARE | | AVAILABLE FOR DETERMINING THE IMPACT OF THIS EVENT. HOWEVER, SIMILAR | | ANALYSES AT OTHER STATIONS HAVE SHOWN THAT THE PIPING LOADS EXCEED THE | | DESIGN LIMITS FOR THE PIPE AND SUPPORTS. AN EVALUATION IS BEING PERFORMED | | IN RESPONSE TO GENERIC LETTER 96-06, ASSURANCE OF EQUIPMENT OPERABILITY AND | | CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS. | | | | THE LICENSEE IS MAKING THIS NOTIFICATION IN THE EVENT THAT THE FINAL | | RESULTS OF THE EVALUATION SHOW STEAM GENERATION IN THE CONTAINMENT AIR | | COOLING COILS AND THE WORST CASE ASSUMPTION THAT THE RESULTANT WATER HAMMER | | WILL STRESS THE PIPING AND SUPPORTS IN EXCESS OF CODE ALLOWABLES. PRIOR TO | | RESTART FROM THE CURRENT REFUELING OUTAGE, THE LICENSEE PLANS TO PERFORM | | ADDITIONAL ANALYSES TO JUSTIFY OPERABILITY OF THE CCW SYSTEM. THE LICENSEE | | PLANS TO COMPLETE FINAL RESOLUTION OF THIS ISSUE BEFORE THE END OF THE NEXT | | REFUELING OUTAGE WHICH IS SCHEDULED TO BEGIN DURING MARCH OF 1998. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31315 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/11/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 23:11 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 22:00[EST]| |NRC NOTIFIED BY: DOUGLAS SQUIRES |LAST UPDATE DATE: 11/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE COMBINED AS-FOUND TYPE 'B' AND 'C' LOCAL LEAK RATE TESTING RESULTS | | EXCEED TECHNICAL SPECIFICATION ALLOWABLE LIMITS. | | | | PRIMARY CONTAINMENT TECHNICAL SPECIFICATION 6.20.B ESTABLISHES THE MAXIMUM | | ALLOWABLE PRIMARY CONTAINMENT LEAKAGE RATE AT 0.5% OF PRIMARY CONTAINMENT | | AIRWAY PER DAY, AND THE COMBINED AS-FOUND TYPE 'B' AND 'C' LOCAL LEAK RATE | | TESTING RESULTS EXCEEDED THE TECHNICAL SPECIFICATION ALLOWABLE LIMITS. THIS | | CONDITION WAS VERIFIED UPON DECLARING FAILURES OF THE AS-FOUND TESTING OF | | REACTOR WATER CLEANUP SYSTEM INBOARD AND OUTBOARD CONTAINMENT ISOLATION | | VALVES 12-MOV-15 AND 12-MOV-18. THERE ARE NO ACTION STATEMENTS ASSOCIATED | | WITH THIS TECHNICAL SPECIFICATION BECAUSE THE UNIT IS CURRENTLY DEFUELED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31316 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 01:30 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 23:05[CST]| |NRC NOTIFIED BY: SCOTT SANDBOTHE |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 Y 20 POWER OPERATION | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED AN UNPLANNED FEEDWATER ISOLATION SIGNAL DUE TO A | | HIGH-HIGH LEVEL ON THE "A" STEAM GENERATOR (SG). | | | | UNIT 1 WAS RETURNING TO POWER AFTER COMPLETING REFUELING OUTAGE 9. POWER | | WAS INCREASING AT APPROXIMATELY 20% AFTER SYNCHRONIZING THE GENERATOR TO | | THE GRID AND COMPLETING THE VALVE SWAP FROM FEEDWATER BYPASS TO THE MAIN | | FEEDWATER REG VALVES WHEN OPERATORS OBSERVED LEVELS IN THE "A" AND "D" SGs | | TRENDING DOWN WHILE LEVELS IN THE "B" AND "C" WERE TRENDING UP. ATTEMPTS | | TO STABILIZE LEVELS BY SHIFTING THE MFRV CONTROLLERS BETWEEN AUTO AND | | MANUAL WERE UNSUCCESSFUL; i.e., THE "A" SG WAS OVERFED WHICH RESULTED IN A | | FEEDWATER ISOLATION AND TURBINE TRIP AT 78% LEVEL (NARROW RANGE). BOTH | | MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS STARTED AS EXPECTED. OPERATORS | | REDUCED POWER TO 1% AND ARE CONTROLLING AFW IN MANUAL TO MAINTAIN SG LEVEL | | AT 50% (NARROW RANGE). THE LICENSEE IS IN THE PROCESS OF RESTORING THE "B" | | MAIN FEEDWATER PUMP. UNIT 1 BRIEFLY ENTERED TS A/S 3.1.1.4 (MINIMUM | | TEMPERATURE FOR CRITICALITY) WHICH REQUIRED THAT THE RCS TEMPERATURE BE | | RESTORED TO 551øF WITHIN 15 MINUTES. THE LOWEST TEMPERATURE OBSERVED WAS | | 546øF. THIS WAS DUE TO THE TURBINE TRIP FOLLOWED BY THE RAPID DOWN POWER | | AND USE OF AFW. THE A/S WAS EXITED AFTER APPROXIMATELY 7 MINUTES. A | | PROBLEM INVOLVING DUAL INDICATION OF THE "C" MAIN FEEDWATER ISOLATION VALVE | | WAS IDENTIFIED AND IS BEING CORRECTED. THE LICENSEE HAS ASSEMBLED AN EVENT | | REVIEW TEAM TO DETERMINE THE ROOT CAUSE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31317 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 05:40 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 04:02[CST]| |NRC NOTIFIED BY: SCOTT SANDBOTHE |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 COMPLETED A TECH SPEC REQUIRED SHUTDOWN FOLLOWING THE HIGH VIBRATION | | TRIP OF REACTOR COOLANT PUMP (RCP) "B". | | | | AT 0242CST RCP "B" TRIPPED ON HIGH VIBRATION. THIS PLACED UNIT 1 IN TS | | 3.4.1.1 WHICH REQUIRES ALL REACTOR COOLANT LOOPS OPERABLE IN MODE 1 AND 2 | | OTHERWISE BE IN MODE 3 WITHIN THE FOLLOWING 6 HOURS. AT 0402CST THE | | LICENSEE COMMENCED A SHUTDOWN ENTERING MODE 3 AT 0430CST. CURRENT PLANT | | CONDITIONS ARE RCS AT NORMAL OPERATING TEMPERATURE AND PRESSURE WITH | | SHUTDOWN BANK CONTROL RODS WITHDRAWN. DECAY HEAT IS BEING REMOVED VIA THE | | MAIN CONDENSER. ALL OFFSITE POWER SOURCES ARE AVAILABLE WITH NO | | SAFETY-RELATED EQUIPMENT OUT-OF-SERVICE. THE LICENSEE WILL MAINTAIN THE | | UNIT IN MODE 3 WHILE TROUBLESHOOTING RCP "B". | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+