U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/14/97 - 05/15/97 ** EVENT NUMBERS ** 32325 32326 32327 32328 32329 32330 32331 32332 32333 32334 32335 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32325 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:37 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/13/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/14/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |McCORMICK-BARGER RDO | | DOCKET: 0707002 | | +------------------------------------------------+ | |NRC NOTIFIED BY: SISLER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE #1 DECLARED INOPERABLE DUE TO PARTIALLY CLOGGED CONDENSATE LINE. | | | | AT 1718 ON 05/13/97, AN OPERATOR IN THE X-344A BUILDING RECEIVED AN AUDIBLE | | AND VISUAL ALARM INDICATING STEAM SHUT DOWN OF AUTOCLAVE #1. THE | | INVESTIGATION REVEALED THAT HIGH LEVEL CONDENSATE ALARMS WERE ACTIVATED | | CAUSING THE STEAM TO SHUT DOWN. AUTOCLAVE #1 WAS SHUT DOWN AND DECLARED | | INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT AT 1721 ON 5/13/97. | | | | AT 2000 ON 05/13/97, THE CERTIFICATE HOLDER DETERMINED THAT A VALID SAFETY | | SYSTEM ACTUATION HAD OCCURRED DUE TO A PARTIALLY PLUGGED CONDENSATE LINE. | | THE NRC RESIDENT HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32326 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. AIR FORCE RADIOISOTOPE COMM |NOTIFICATION DATE: 05/14/97 | | CITY: REGION: 4 |NOTIFICATION TIME: 12:23 [ET]| | COUNTY: STATE: TX |EVENT DATE: 05/12/97 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 09:30[CDT]| | DOCKET: |LAST UPDATE DATE: 05/14/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | |DON COOL, NMSS EO | +------------------------------------------------+FRANK CONGEL, IRD AEOD | |NRC NOTIFIED BY: MANNING | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. AIR FORCE RADIOISOTOPE COMMITTEE REPORTED THAT 8 MICROCURIES OF | | AMERICIUM WERE MISSING IN NEW MEXICO. | | | | THIS OCCURRED WHEN A LANTIRN (LOW ALTITUDE NAVIGATION AND TARGETING | | INFRARED-NIGHT) POD WAS LOST IN THE VICINITY OF CANNON AIR FORCE BASE, NEW | | MEXICO, FOLLOWING THE CRASH OF AN F-16 FIGHTER IN AN ISOLATED AREA NEAR THE | | BASE. THE U.S. AIR FORCE HAS SEARCHED FOR THE SOURCE, BUT IT COULD NOT BE | | FOUND. THE AIR FORCE IS NOW UNDER THE ASSUMPTION THAT THE AMERICIUM SOURCE | | IS EITHER BURIED OR WAS CONSUMED IN THE CRASH. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32327 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/14/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 12:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/14/97 | +------------------------------------------------+EVENT TIME: 11:05[EDT]| |NRC NOTIFIED BY: HOFFMAN |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP SIGNAL WHILE IN MODE 3. (REFER TO EVENT #32333 | | FOR ADDITIONAL INFORMATION.) | | | | THE REACTOR TRIP OCCURRED DURING TESTING OF THE POWER RANGE NUCLEAR | | INSTRUMENTS, WHEN AN APPARENT PROCEDURAL PROBLEM CAUSED TWO OUT OF FOUR | | LOGIC CHANNELS OF THE 'P-8' (48% REACTOR POWER) INTERLOCK TO TRIP WITH THE | | TURBINE ALREADY TRIPPED, GENERATING AN AUTOMATIC REACTOR TRIP SIGNAL. PRIOR | | TO THE TRIP SIGNAL, SHUTDOWN BANKS 'A' AND 'B' WERE OUT OF THE CORE, AND | | REACTOR TEMPERATURE WAS 557øF. ALL RODS THAT WERE OUT OF THE CORE FULLY | | INSERTED BACK INTO THE CORE ON THE TRIP SIGNAL. WHEN THE REACTOR TRIPPED, | | FEEDWATER ISOLATION OCCURRED (ENGINEERED SAFETY FEATURE) DUE TO THE REACTOR | | TRIP AND LOW Tavg. THE LICENSEE PLANS TO CORRECT THE PROCEDURE DISCREPANCY | | PRIOR TO CONTINUING WITH LOW POWER PHYSICS TESTING. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32328 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 05/14/97 | | CITY: PITTSBURGH REGION: 1 |NOTIFICATION TIME: 14:38 [ET]| | COUNTY: STATE: PA |EVENT DATE: 05/14/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/14/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM MCCORMICKBARGER RDO | | | | +------------------------------------------------+VERN HODGE, RVIB NRR | |NRC NOTIFIED BY: SEPP | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION - WESTINGHOUSE ELECTRIC CORPORATION HAS | | IDENTIFIED DEFECTS THAT COULD CREATE A SUBSTANTIAL SAFETY HAZARD SHOULD | | THEY REMAIN UNCORRECTED. | | | | DEVIATIONS WERE IDENTIFIED BY WESTINGHOUSE DURING A LESSONS LEARNED REVIEW | | OF A PILOT PROGRAM TO PROVIDE SAFETY-RELATED CIRCUIT BREAKER REFURBISHMENT | | FOR THE BYRON AND BRAIDWOOD NUCLEAR SITES. THIS PILOT PROGRAM, WHICH WAS | | CONDUCTED AT WESTINGHOUSE SATELLITE FACILITIES, INCLUDED BOTH WESTINGHOUSE | | TYPE 'DHP' SERIES AND 'DS' SERIES BREAKERS. IT WAS DISCOVERED THAT CORRECT | | PROCEDURES WERE NOT UTILIZED, RESULTING IN CERTAIN TESTS AND INSPECTIONS | | NOT BEING PERFORMED OR DOCUMENTED. THE ITEMS WHICH WERE OMITTED OR NOT | | DOCUMENTED INCLUDED THE PERFORMANCE OF TIMING TESTS, CONTACT RESISTANCE | | CHECKS TO CORRECT VALUES, REAPPLICATION OF LUBRICANT, OPENING FORCE MARGIN | | VERIFICATION, AND WELD INSPECTIONS. THESE TESTS AND INSPECTIONS ARE | | DESIGNED TO PROVIDE ASSURANCE THAT BREAKER OPERATION (EITHER TO OPEN OR | | CLOSE) WILL BE SUCCESSFULLY COMPLETED. WESTINGHOUSE DETERMINED THAT THE | | TESTS THAT WERE PERFORMED ON THE REFURBISHED BREAKERS BEFORE THEIR RETURN | | TO BYRON AND BRAIDWOOD WERE INSUFFICIENT TO REESTABLISH FULL QUALIFICATION | | OF THE BREAKERS. ALL BREAKERS THAT WERE REFURBISHED USING INCORRECT | | PROCEDURES HAVE BEEN IDENTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32329 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 05/14/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 05/14/97 | +------------------------------------------------+EVENT TIME: 14:27[EDT]| |NRC NOTIFIED BY: KEITH HOLBROOK |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNEXPECTED EMERGENCY CORE COOLING SYSTEM DISCHARGE (GRAVITY DRAIN) TO THE | | REACTOR COOLANT SYSTEM DURING THE PERFORMANCE OF SURVEILLANCE TESTING | | | | WITH THE UNIT IN COLD SHUTDOWN AS PART OF A REFUELING OUTAGE, AN UNEXPECTED | | SAFETY INJECTION OCCURRED DURING THE PERFORMANCE OF SURVEILLANCE TESTING ON | | THE 'A' TRAIN SOLID STATE ACTUATION LOGIC AND MASTER RELAYS. THERE WERE NO | | HIGH HEAD SAFETY INJECTION PUMPS IN SERVICE AT THE TIME OF THE EVENT, AND | | THE DISCHARGE TO THE CORE OCCURRED BY GRAVITY DRAIN FROM THE REFUELING | | WATER STORAGE TANK WHEN A SAFETY INJECTION SIGNAL ON THE 'A' TRAIN CAUSED | | VALVE MOVEMENT. THE INJECTION WAS IMMEDIATELY RECOGNIZED, AND IT WAS | | SECURED WITHIN 2 TO 3 MINUTES. THE LICENSEE BELIEVES THAT THE AMOUNT OF | | WATER INJECTED WAS MINIMAL, AND THERE WAS A SMALL REACTOR VESSEL WATER | | LEVEL CHANGE (ON THE ORDER OF INCHES). ALL SYSTEMS FUNCTIONED AS REQUIRED, | | AND ALL EQUIPMENT REQUIRED FOR MODE 5 OPERATIONS WAS OPERABLE. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE SAFETY INJECTION | | SIGNAL. APPARENTLY, THE SURVEILLANCE PROCEDURE HAD BEEN REVISED TO INCLUDE | | THIS PARTICULAR PORTION OF THE TEST AS A NEW SECTION, AND THIS WAS BELIEVED | | TO BE THE FIRST USAGE OF THE NEW SECTION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: CURRENTLY, THE VESSEL HEAD IS IN PLACE AND TENSIONED, AND THE | | REACTOR COOLANT SYSTEM IS DEPRESSURIZED. WATER LEVEL IS | | APPROXIMATELY 20 INCHES BELOW THE FLANGE (ABOVE MID-LOOP), AND | | CONTROL ROOM LEVEL INDICATION IS VIA THE STANDPIPE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32330 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DEPT. OF VETERANS AFFAIRS MED. CTR. |NOTIFICATION DATE: 05/14/97 | | CITY: BUFFALO REGION: 1 |NOTIFICATION TIME: 15:47 [ET]| | COUNTY: ERIE STATE: NY |EVENT DATE: 05/13/97 | |LICENSE#: 31-00786-02 AGREEMENT: Y |EVENT TIME: 16:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/14/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN CARUSO RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: PHILLIP CUNNINGHAM | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNDERDOSE OF IODINE-131 (SODIUM IODIDE) AT THE DEPARTMENT OF VETERANS | | AFFAIRS MEDICAL CENTER LOCATED IN BUFFALO, NEW YORK | | | | DURING THE PERFORMANCE OF A TOTAL BODY METASTASIS SCAN OF IODINE-131 | | (SODIUM IODIDE), A PATIENT RECEIVED A DOSE OF 50 MICROCURIES INSTEAD OF THE | | PRESCRIBED DOSE OF 5 MILLICURIES. THE IODINE-131 WAS IN THE FORM OF A | | CAPSULE. PRELIMINARY INVESTIGATIONS INDICATE THIS RESULTED FROM THE | | FAILURE OF A TECHNOLOGIST TO VERIFY THE MEASURED DOSE EVEN THOUGH THE | | INDIVIDUAL SIGNED THAT THE DOSE HAD BEEN VERIFIED. THE LICENSEE STATE THAT | | THERE WERE NO HEALTH AFFECTS TO THE PATIENT, AND THAT BOTH THE PATIENT AND | | THE REFERRING PHYSICIAN HAVE BEEN INFORMED. | | | | THE LICENSEE NOTIFIED THE NRC REGION 1 OFFICE (DAVID EVERHART). (REFER TO | | THE HOO LOG FOR A STREET ADDRESS AND SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32331 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/14/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/14/97 | +------------------------------------------------+EVENT TIME: 16:10[CDT]| |NRC NOTIFIED BY: TIM CLOUSER |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT FLOOR DRAINS ARE IN DIRECT COMMUNICATION WITH MULTIPLE ROOMS | | IN THE SAFEGUARDS BUILDING AND THAT THIS COULD ALLOW PROPAGATION OF HARSH | | ENVIRONMENTS IN THE EVENT OF A ONE SQUARE FOOT NON-MECHANISTIC MAIN STEAM | | OR FEEDWATER LINE BREAK IN THE MAIN STEAM AND FEEDWATER PIPE PENETRATION | | AREA OUTSIDE CONTAINMENT. | | | | THE LICENSEE IS REQUIRED TO EVALUATE THE ENVIRONMENTAL EFFECTS (PRESSURE, | | TEMPERATURE, FLOODING, AND RELATIVE HUMIDITY) RESULTING FROM A ONE SQUARE | | FOOT NON-MECHANISTIC MAIN STEAM OR FEEDWATER LINE BREAK IN THE MAIN STEAM | | AND FEEDWATER PIPE PENETRATION AREA OUTSIDE THE CONTAINMENT. THESE LINE | | BREAKS ARE INCLUDED IN THE LICENSEE'S DESIGN BASIS, BUT THEY ARE NOT PART | | OF THE BASES FOR THE LICENSEE'S TECHNICAL SPECIFICATIONS. | | | | THE ENVIRONMENTAL ANALYSIS ASSUMES THAT THESE COMPARTMENTS ARE ISOLATED | | FROM THE REMAINING PART OF THE SAFEGUARDS BUILDING (VIA HEATING VENTILATION | | AND AIR CONDITIONING DAMPERS AND WATER TIGHT DOORS) IN ORDER TO PREVENT THE | | PROPAGATION OF THESE HARSH ENVIRONMENTS. CONTRARY TO THIS, THE FLOOR | | DRAINS ARE IN DIRECT COMMUNICATION WITH MULTIPLE ROOMS IN THE SAFEGUARDS | | BUILDING. DUE TO THE COMPLEXITY OF THESE ANALYSES, THE RESULTING | | ENVIRONMENTS OF THE AFFECTED AREAS ARE NOT CURRENTLY KNOWN. A BOUNDING | | CONSERVATIVE ASSESSMENT OF THE AFFECTED AREAS COULD NOT CONFIRM THAT THE | | ENVIRONMENTS WILL REMAIN WITHIN THE VALUES PRESENTLY CONTAINED IN THE | | PLANT'S DESIGN BASIS. | | | | COMPENSATORY ACTION HAS BEEN TAKEN TO PLUG THE DRAINS IN THE MAIN STEAM AND | | FEEDWATER AREAS OF BOTH UNITS TO MITIGATE THE CONSEQUENCES OF PRESSURE, | | TEMPERATURE, FLOODING, AND RELATIVE HUMIDITY IN AN UNLIKELY EVENT THAT A | | MAIN STEAM AND/OR FEEDWATER LINE BREAK OCCURS. THESE CONDITIONS ARE BEING | | FURTHER ANALYZED BY ENGINEERING PERSONNEL. | | | | THE NON-CONFORMING CONDITION DOES NOT IMPACT OPERABILITY PER THE TECHNICAL | | SPECIFICATIONS BECAUSE THESE BREAKS ARE NOT PART OF THE BASIS FOR THE | | TECHNICAL SPECIFICATIONS. IN ADDITION, THE COMPENSATORY ACTION ELIMINATED | | ANY POSTULATED ADVERSE EFFECTS WHICH MAY EXCEED THE LICENSEE'S DESIGN | | BASIS. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32332 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/14/97 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 17:30 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 05/14/97 | +------------------------------------------------+EVENT TIME: 16:00[CDT]| |NRC NOTIFIED BY: R. H. SHEIDE |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A CONDITION WHERE EMERGENCY CORE COOLING SYSTEM SUCTION COULD | | SHIFT TO THE CONTAINMENT SUMP PREMATURELY RESULTING IN THE HIGH HEAD SAFETY | | INJECTION PUMPS BEING INITIALLY UNABLE TO DELIVER FLOW TO THE REACTOR CORE | | | | THE LICENSEE HAS IDENTIFIED A CONDITION WHERE TECHNICAL SPECIFICATIONS | | ALLOW A CONFIGURATION TO EXIST INDEFINITELY SUCH THAT A SINGLE FAILURE | | WOULD RESULT IN THE INITIATION OF AN INADVERTENT RECIRCULATION ACTUATION | | SIGNAL. A RECIRCULATION ACTUATION SIGNAL IS INITIATED WHENEVER ANY TWO OF | | THE FOUR REFUELING WATER TANK (RWT) LEVEL INSTRUMENTS INDICATE A LOW TANK | | LEVEL. TECHNICAL SPECIFICATION 3.3.2.1.b, TABLE 3.3-3, ALLOWS AN | | INOPERABLE CHANNEL OF RWT LEVEL INSTRUMENTATION TO BE PLACED IN THE | | 'TRIPPED' CONDITION INDEFINITELY. | | | | ASSUMING THAT A CHANNEL OF RWT LEVEL INSTRUMENTATION IS IN THE TRIPPED | | CONDITION AT THE TIME OF A LARGE BREAK LOSS OF COOLANT ACCIDENT AND THAT | | THE ADDITIONAL SINGLE FAILURE IS THAT OF ANOTHER CHANNEL OF RWT LEVEL | | INSTRUMENTATION, AN INADVERTENT RECIRCULATION ACTUATION SIGNAL WILL OCCUR. | | EMERGENCY CORE COOLING SYSTEM SUCTION WOULD BE SHIFTED TO THE CONTAINMENT | | SUMP PREMATURELY RESULTING IN THE HIGH PRESSURE SAFETY INJECTION PUMPS | | BEING INITIALLY UNABLE TO DELIVER FLOW TO THE REACTOR CORE. | | | | THE LICENSEE BELIEVES THAT UNIT 2 HAS NOT OPERATED WITH A CHANNEL OF RWT | | LEVEL INSTRUMENTATION IN A TRIPPED CONDITION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32333 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/14/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 19:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/14/97 | +------------------------------------------------+EVENT TIME: 11:05[EDT]| |NRC NOTIFIED BY: KEN HOFFMAN |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT BOTH SOURCE RANGE CHANNELS WERE INOPERABLE DURING A PREVIOUS | | EVENT (REFER TO EVENT #32327 FOR ADDITIONAL INFORMATION.) | | | | DURING THE REACTOR TRIP AND FEEDWATER ISOLATION THAT OCCURRED EARLIER TODAY | | (EVENT #32327), THE UNIT ALSO ENTERED TECHNICAL SPECIFICATION 3.0.3 DUE TO | | BOTH SOURCE RANGE CHANNELS BEING INOPERABLE FOR APPROXIMATELY ONE SECOND. | | THE UNIT HAD TWO OUT OF FOUR CHANNELS ABOVE P-10 (10% POWER). BOTH SOURCE | | RANGE CHANNELS BEING INOPERABLE WAS NOT RECOGNIZED AS BEING A REPORTABLE | | EVENT UNTIL APPROXIMATELY 1700. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32334 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/14/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 19:40 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/14/97 | +------------------------------------------------+EVENT TIME: 17:20[EDT]| |NRC NOTIFIED BY: THOMAS McKEE |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | M/R Y 90 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE RUNBACK FROM 90% REACTOR POWER DUE TO OVER-POWER DELTA TEMPERATURE | | ON ONE OF FOUR LOOPS AND MANUAL REACTOR TRIP FROM APPROXIMATELY 60% POWER | | | | AT APPROXIMATELY 1720, A LICENSED OPERATOR MANUALLY TRIPPED THE REACTOR | | FROM APPROXIMATELY 60% POWER DUE TO A TURBINE RUNBACK FROM 90% POWER WHICH | | DID NOT APPEAR TO BE RECOVERABLE. THE RUNBACK WAS DUE TO OVER-POWER DELTA | | TEMPERATURE ON ONE OF FOUR LOOPS. ALL INSTRUMENTATION SHOWED NORMAL WHICH | | INDICATED THAT THE RUNBACK WAS PROBABLY DUE TO A CIRCUITRY PROBLEM, BUT THE | | EXACT CAUSE HAS NOT YET BEEN DETERMINED. ALL SAFETY EQUIPMENT FUNCTIONED | | AS REQUIRED. ALL RODS FULLY INSERTED ON THE TRIP SIGNAL. THE MAIN BOILER | | FEEDWATER PUMPS TRIPPED AS EXPECTED, AND THE MOTOR-DRIVEN AUXILIARY | | FEEDWATER PUMPS AUTOMATICALLY STARTED (NOT AN ENGINEERED SAFETY FEATURE). | | THERE WERE NO SAFETY INJECTION SIGNALS, AND NONE OF THE SAFETY RELIEF | | VALVES LIFTED. | | | | THE UNIT IS CURRENTLY STABLE IN HOT SHUTDOWN. PRESSURIZER HEATERS AND | | SPRAYS, NORMAL CHARGING AND LETDOWN, AND THE REACTOR COOLANT PUMPS ARE | | CURRENTLY BEING UTILIZED FOR PRIMARY SYSTEM PRESSURE, INVENTORY, AND | | TRANSPORT CONTROL. AUXILIARY FEEDWATER IS SUPPLYING WATER TO THE STEAM | | GENERATORS, AND SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. ALL | | CONTAINMENT PARAMETERS APPEAR TO BE NORMAL, AND OFFSITE POWER IS AVAILABLE. | | | | THE UNIT WAS IN THE PROCESS OF COASTING DOWN TO A REFUELING OUTAGE WHEN | | THIS EVENT OCCURRED. AS A RESULT, THE LICENSEE PLANS TO PLACE THE UNIT IN | | A COLD SHUTDOWN CONDITION AND COMMENCE THE REFUELING OUTAGE EARLY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32335 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/14/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 20:50 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/08/97 | +------------------------------------------------+EVENT TIME: 05:20[CDT]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 05/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED FUEL BUILDING VENTILATION ISOLATION AND STANDBY GAS TREATMENT | | SYSTEM INITIATION DURING THE PERFORMANCE OF A CHANNEL CALIBRATION ON MAY 8, | | 1997 | | | | WHEN THE HIGH ALARM TRIP SIGNAL WAS INSERTED DURING THE PERFORMANCE OF A | | CHANNEL CALIBRATION ON PROCESS RADIATION MONITOR 1PR006A, THE LOGIC WAS | | UNEXPECTEDLY SATISFIED. THE LOGIC ACTUATION RESULTED IN AN ISOLATION OF | | GROUP 19 (FUEL BUILDING VENTILATION) AND AN INITIATION OF BOTH VG (STANDBY | | GAS TREATMENT) TRAINS. THE TWO-OUT-OF-FOUR LOGIC WAS SATISFIED BY THE | | FOLLOWING TWO CONDITIONS: ANOTHER PROCESS RADIATION MONITOR (1PR006D) HAD | | THE LOCAL TRIP SIGNAL SWITCH IN THE TRIP POSITION, AND THE INSERTION OF THE | | HIGH ALARM TRIP SIGNAL FOR THE CHANNEL CALIBRATION OF MONITOR 1PR006A. | | | | LICENSEE PERSONNEL INITIATED THE APPROPRIATE OFF-NORMAL PROCEDURES AND | | VERIFIED ACTUAL RADIATION CONDITIONS IN THE FUEL BUILDING EXHAUST DUCTS TO | | BE NORMAL. THE EMERGENCY PROCEDURES WERE EXITED, AND RESTORATION OF THE | | FUEL BUILDING VENTILATION SYSTEM WAS INITIATED. | | | | APPARENTLY, FUEL BUILDING EXHAUST DUCT MONITOR 'D' (1PR006D) WAS PLACED IN | | A TRIPPED CONDITION ON MARCH 6, 1997, AT 1204 CST PER A MAINTENANCE WORK | | REQUEST, A CAUTION TAGOUT WAS HUNG ON THE LOCAL TRIP SWITCH. THIS TAGOUT | | WAS RELEASED AT 0555 CST ON APRIL 4, 1997, AND THE TAGOUT RESTORATION | | POSITION FOR THE TRIP SWITCH WAS (TAG) 'REMOVED.' THE SWITCH WAS NOT | | RETURNED TO THE NORMAL POSITION AT THAT TIME. | | | | AN INCORRECT INTERPRETATION REGARDING WHAT TYPES OF ENGINEERED SAFETY | | FEATURE ACTUATIONS ARE EXEMPT FROM THE REPORTING REQUIREMENTS RESULTED IN A | | DELAYED DETERMINATION OF REPORTABILITY. THE LICENSEE BELIEVES THIS | | MISUNDERSTANDING OF THE REPORTING REQUIREMENTS WAS SUPPORTED BY RELATED BUT | | UNCLEAR GUIDANCE PROVIDED IN NUREG-1022 WHICH ADDRESSES EXCLUDING CERTAIN | | TYPES OF STANDBY GAS TREATMENT SYSTEM ACTUATIONS. SUBSEQUENT DISCUSSIONS | | WITH THE NRC (HEADQUARTERS) AND OTHER UTILITIES REGARDING THE | | 10CFR50.72(b)(2)(ii)(3) REQUIREMENTS AND THE RELATED GUIDANCE IN NUREG-1022 | | CONFIRMED THAT THE EVENT SHOULD HAVE BEEN REPORTED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+