U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/11/97 - 04/14/97 ** EVENT NUMBERS ** 31909 31954 32017 32030 32044 32092 32093 32127 32129 32130 32131 32132 32133 32134 32135 32136 32137 32138 32139 32140 32141 32142 32143 32144 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31909 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 03/07/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 10:45 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 12:30[EST]| |NRC NOTIFIED BY: JOHN BASS |LAST UPDATE DATE: 04/12/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McCORMICK-BARGER RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EECW SYSTEM MAY NOT ALIGN PROPERLY FOR USE FROM REMOTE SHUTDOWN PANEL. | | | | DURING AN ENGINEERING REVIEW, THE LICENSEE DISCOVERED THAT THE EMERGENCY | | EQUIPMENT COOLING WATER (EECW) SYSTEM MAY NOT PROPERLY ALIGN FOR OPERATION | | FROM THE REMOTE SHUTDOWN PANEL, AS SPECIFIED IN THE DEDICATED SHUTDOWN | | PROCEDURE FOR A SERIOUS CONTROL ROOM FIRE. SPECIFICALLY, THE EECW MAKEUP | | VALVE FROM THE EECW MAKEUP TANK MAY NOT OPEN DUE TO AN ELECTRICAL INTERLOCK | | WITH THE REACTOR BUILDING CLOSED COOLING WATER (RBCCW) TO EECW ISOLATION | | VALVES, UNLESS THE ISOLATION VALVES ARE FULLY CLOSED. THERE ARE NO LOCAL | | TRANSFER SWITCHES TO OVERRIDE THE INTERLOCK. THIS INTERLOCK COULD PREVENT | | THE EECW SYSTEM FROM BEING ALIGNED TO THE EECW MAKEUP TANK TO SUPPORT | | OPERATION OF THE SYSTEM FROM THE REMOTE SHUTDOWN PANEL. HOWEVER, THE EECW | | SYSTEM MAKEUP VALVE IS LOCATED ADJACENT TO THE DEDICATED SHUTDOWN PANEL, | | AND IS ACCESSIBLE FOR MANUAL OPERATION. | | | | THIS CONDITION IS NOT IN COMPLIANCE WITH TECHNICAL SPECIFICATION 3.7.11.d, | | WHICH CONCERNS 10 CFR PART 50, APPENDIX R ALTERNATE SHUTDOWN CONTROL | | CIRCUITS. UFSAR TABLE 9A.6.9-1 LISTS THE EECW MAKEUP VALVE AS A CONTROL | | CIRCUIT NECESSARY TO SUPPORT THE TECHNICAL SPECIFICATION. THIS TECHNICAL | | SPECIFICATION IS ONLY APPLICABLE IN OPERATING MODES 1, 2 AND 3. THE PLANT | | IS CURRENTLY IN MODE 4. | | | | THE LICENSEE STATED THAT THIS CONDITION REQUIRES A 24-HOUR REPORT DUE TO | | THE VIOLATION OF OPERATING LICENSE CONDITION 2.C(9) AS A CONDITION THAT | | ADVERSELY AFFECTS THE ABILITY OF THE PLANT TO REACH AND MAINTAIN SAFE | | SHUTDOWN IN THE EVENT OF A FIRE. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED OF THIS NOTIFICATION BY THE LICENSEE. | | | | * * * UPDATE 1044 4/12/97 FROM SKLARCZYK TAKEN BY STRANSKY * * * | | | | DURING THE ONGOING APPENDIX R REVIEW OF THE DEDICATED SHUTDOWN PROCEDURE | | (20-000.18), THE LICENSEE HAS IDENTIFIED THAT AN OXYGEN DEFICIENT | | ATMOSPHERE MAY EXIST IN AREAS OF THE AUXILIARY BUILDING INTO WHICH | | OPERATORS WOULD BE REQUIRED TO ENTER IN ORDER TO COMPLETE THE DEDICATED | | SHUTDOWN PROCEDURE. THE OXYGEN DEFICIENCY COULD BE THE RESULT OF SMOKE OR | | CARBON DIOXIDE DUE TO THE POSTULATED FIRE. THE LICENSEE EXPECTS THAT | | OPERATORS WOULD DON SELF-CONTAINED BREATHING APPARATUS (SCBA) UNITS OR | | OTHER PERSONNEL SAFETY ITEMS NEEDED TO ENTER AN OXYGEN DEFICIENT | | ATMOSPHERE, BUT THE NEED FOR THIS EQUIPMENT IS NOT MENTIONED IN THE | | PROCEDURE, NOR IS SCBA EQUIPMENT PROVIDED IN THE DEDICATED SHUTDOWN | | EQUIPMENT BOX. THE INABILITY TO ENTER THESE AREAS OF THE AUXILIARY BUILDING | | COULD RESULT IN THE INABILITY TO COMPLETE THE DEDICATED SHUTDOWN PROCEDURE | | AS PLANNED. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS REPORT. | | NOTIFIED R3DO (MADERA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31954 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:30 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/14/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/11/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WAYNE KROPP RDO | | DOCKET: 0707001 |JOSEPHINE PICCONE EO | +------------------------------------------------+KEVIN RAMSEY (FAX) NMSS | |NRC NOTIFIED BY: MARK LOMBARD | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION REGARDING STRESS CORROSION CRACKING OF CYLINDER | | VALVE PACKING NUTS | | | | IT HAS BEEN DETERMINED THAT STRESS CORROSION CRACKING OF THE 1-INCH | | CYLINDER VALVE PACKING NUTS USED IN VARIOUS STAGES OF THE ENRICHMENT | | PROCESS HAS, IN ONE CASE, RESULTED IN A REPORTABLE RELEASE OF UF6. THIS | | PROBLEM HAS ONLY BEEN OBSERVED IN THE 636-ALLOY NUTS ON VALVES SUPPLIED BY | | HUNT VALVE CO., INC. | | | | * * * UPDATE 1740EDT 4/11/97 FROM MARK LOMBARD TO S. SANDIN * * * | | | | THE LICENSEE SUBMITTED AN UPDATE VIA FAX. NOTIFIED R3DO(MADERA) AND | | FORWARDED TO NMSS(RAMSEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32017 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: VICTOREEN, INC. |NOTIFICATION DATE: 03/25/97 | | CITY: SOLON REGION: 3 |NOTIFICATION TIME: 18:23 [ET]| | COUNTY: STATE: OH |EVENT DATE: 04/15/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 18:23[EST]| | DOCKET: |LAST UPDATE DATE: 04/11/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROGER LANKSBURY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LINDA NASH |VERN HODGE NRR | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RESISTOR NETWORKS IN MODEL 530 INSTRUMENTS CAN CRACK, CAUSING IT TO BECOME | | NON-FUNCTIONAL. MEASUREMENTS MADE WITH DEFECTIVE INSTRUMENTS COULD RESULT | | IN ADDITIONAL RADIATION EXPOSURES. IF THE INSTRUMENT IS USED AS A | | CALIBRATION STANDARD, ALL CALIBRATED DEVICES WOULD BE IN ERROR. SURVEY | | METERS AND PERSONAL DOSIMETERS COULD BE AFFECTED. RADIATION WORKERS COULD | | BE EXPOSED UNNECESSARILY, POSSIBLY EXCEEDING ALLOWED LIMITS. | | | | * * * UPDATE 1720EDT 4/11/97 VIA FAX RECEIVED BY S. SANDIN * * * | | | | VICTOREEN SUBMITTED THE CORRECTIVE ACTIONS AND CLOSE-OUT OF THIS | | NOTIFICATION VIA FAX. NOTIFIED R3DO(MADERA) AND FORWARDED TO NRR(HODGE). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32030 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:30 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 08:28[CST]| |NRC NOTIFIED BY: GREEN |LAST UPDATE DATE: 04/13/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STETKA 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 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF SECONDARY CONTAINMENT WHEN BOTH INNER AND OUTER REACTOR BUILDING | | DOORS WERE OPENED SIMULTANEOUSLY. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "TODAY FROM 8:28:29 TO 8:35:56 SECONDARY CONTAINMENT APPEARS TO HAVE BEEN | | BREACHED WHEN BOTH THE INNER AND OUTER REACTOR BUILDING DOORS WERE | | INADVERTENTLY OPENED AT THE SAME TIME. THE DOORS APPEAR TO HAVE BEEN BOTH | | OPENED SEVERAL TIMES DURING THIS TIME FRAME. PRIOR TO THIS INCIDENT A | | REACTOR BUILDING HIGH PRESSURE ALARM WAS RECEIVED AT 0823. THIS CONDITION | | WAS CAUSED BY THE PERFORMANCE OF AN INSTRUMENT AND CONTROL CALIBRATION | | PROCEDURE. THE INSTRUMENT AND CONTROL TECHNICIANS PERFORMING THE PROCEDURE | | WERE INSTRUCTED TO BACK OUT OF THE PROCEDURE AND THE REACTOR BUILDING HIGH | | PRESSURE ALARM WAS CLEARED AT 0832. A PROCEDURE CHANGE IS BEING GENERATED | | TO PREVENT THIS CONDITION FROM OCCURRING AGAIN. THE SHIFT TECHNICAL ADVISOR | | WAS DISPATCHED TO THE REACTOR BUILDING ENTRANCE TO DETERMINE THE STATUS OF | | THE AIRLOCK DOORS. THE DOORS WERE CLOSED AND AN INDIVIDUAL WAS STATIONED AT | | THE DOORS TO ENSURE THAT BOTH DOORS WERE NOT OPENED AT THE SAME TIME AGAIN. | | THE CAUSE OF BOTH DOORS OPENING AT THE SAME TIME APPEARS TO BE PERSONNEL | | ERROR." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | [HOO NOTE: SEE RELATED EN 32022.] | | | | * * * UPDATE 1127 4/12/97 FROM RATZLAFF TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. UPON FURTHER EVALUATION, THE | | LICENSEE HAS DETERMINED THAT THIS REPORT WAS NOT REPORTABLE. | | | | "THE REACTOR BUILDING HIGH PRESSURE CONDITION RESULTED FROM A CALIBRATION | | PROCEDURE WHICH WAS BEING PERFORMED ON A CONTROLLER FOR THE REACTOR | | BUILDING NORMAL VENTILATION SYSTEM. SINCE THE NORMAL REACTOR BUILDING | | VENTILATION FANS TRIP OFF AS A RESULT OF A SECONDARY CONTAINMENT ISOLATION | | SIGNAL, THIS TEMPORARY POSITIVE PRESSURIZATION WOULD HAVE TERMINATED HAD AN | | EVENT REQUIRING SECONDARY CONTAINMENT OCCURRED. FURTHER, THE CONSEQUENCES | | OF THE REACTOR BUILDING BEING SLIGHTLY PRESSURIZED AT THE INITIATION OF, | | FOR EXAMPLE, A LOCA HAVE NO EFFECT ON DOSE CALCULATIONS SINCE THEY ASSUME | | AN UNFILTERED FLOW FOR UP TO 90 SECONDS DUE TO THE NORMAL VENTILATION | | SYSTEM OPERATING UNTIL THE REACTOR BUILDING IS ISOLATED AND STANDBY GAS | | TREATMENT SYSTEM INITIATES ON A GROUP 6 ISOLATION SIGNAL. ACCORDINGLY, THE | | PLANT WAS NOT IN A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT. | | | | THE CALIBRATION PROCEDURE WAS TERMINATED AND THE REACTOR BUILDING PRESSURE | | RETURNED TO NORMAL LIMITS. SECONDARY CONTAINMENT WAS RESTORED BY CLOSING | | THE AIRLOCK DOORS. TECHNICAL SPECIFICATION 3.7.C.1.e WAS CORRECTLY ENTERED | | DUE TO THE LOSS OF SECONDARY CONTAINMENT INTEGRITY PER TECHNICAL | | SPECIFICATION DEFINITION 1.0.V. REPORTING UNDER 50.72(b)(2)(iii)(C) OR (D) | | WAS NOT REQUIRED AS THE INTEGRITY OF THE REACTOR BUILDING DOORS WAS NEVER | | IN QUESTION (THAT IS, THERE WAS NOTHING PREVENTING THE DOORS FROM PROPERLY | | CLOSING AND ONCE EITHER DOOR WAS CLOSED, SECONDARY CONTAINMENT WAS RESTORED | | TO THE AS-TESTED CONFIGURATION). FURTHER, REPORTING UNDER 50.73(a)(2)(i)(B) | | WAS NOT REQUIRED AS THE ASSOCIATED TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION WAS NOT VIOLATED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R4DO (JOHNSON). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/28/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:04 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/27/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:25[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/11/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UF6 RELEASE DETECTION AND ISOLATION SAFETY SYSTEM DECLARED INOPERABLE | | DURING SURVEILLANCE TESTING. | | | | AT 0325CST ON 3/27/97, DURING TSR SURVEILLANCE TESTING OF THE UF6 RELEASE | | DETECTION AND ISOLATION SAFETY SYSTEM ON THE C-310 WEST NORMETEX PUMP, THE | | SAFETY SYSTEM FOR THE OPERATING EAST NORMETEX PUMP WAS DETERMINED TO BE | | INOPERABLE. AT 0410CST, THE EAST NORMETEX PUMP WAS PLACED IN MODE 3 | | (STANDBY) AS REQUIRED BY THE TSR. AT 2200CST, PLANT PERSONNEL PERMITTED | | PERFORMANCE OF THE SURVEILLANCE TEST BASED ON THE EXISTENCE OF TWO | | INDEPENDENT INSTRUMENT CHANNELS, EITHER OF WHICH IS CAPABLE OF PROVIDING | | THE PROTECTIVE FUNCTION. THE SURVEILLANCE TESTS THE ABILITY OF THE | | DETECTION AND ISOLATION SAFETY SYSTEM TO PERFORM THEIR INTENDED SAFETY | | FUNCTIONS. EACH OF THE TWO INSTRUMENT CHANNELS IS TESTED INDEPENDENTLY AND | | IS INOPERABLE DURING TESTING. PERSONNEL PERFORMING THE SURVEILLANCE, USING | | AN IN-HAND PROCEDURE, DID NOT REALIZE THAT THE TSR LCO CANNOT BE MET IF ONE | | OF THE TWO CHANNELS IS INOPERABLE FOR MORE THAN ONE HOUR. A LATER REVIEW | | BY ENGINEERING DETERMINED THAT BOTH INSTRUMENT CHANNELS MUST BE OPERABLE TO | | COMPLY WITH THE TSR. THE INOPERABLE CONDITION WAS CORRECTED AND THE UF6 | | RELEASE DETECTION AND ISOLATION SYSTEM WAS SUBSEQUENTLY DECLARED OPERABLE | | AND THE PUMP WAS RETURNED TO MODE 2 (WITHDRAWAL). | | | | THE 'A' INSTRUMENT CHANNEL, REMOVED FROM SERVICE AT 2200CST ON 3/26/97 FOR | | TESTING, WAS NOT RESTORED UNTIL 0447CST ON 3/27/97. THIS EXCEEDED THE 1 | | HOUR ALLOWED PER TSR LCO, THUS, RENDERING THE ASSOCIATED SAFETY EQUIPMENT | | INOPERABLE. TESTING OF THE 'B' INSTRUMENT CHANNEL HAS NOT BEEN PERFORMED. | | THE LICENSEE HAS LONG TERM CORRECTIVE ACTIONS UNDER REVIEW, HOWEVER, | | BELIEVES THAT THE 1 HOUR CURRENTLY ALLOWED IS SUFFICIENT FOR TESTING. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION ON 04/11/97 @ 1125 EDT BY BOREN TAKEN BY MACKINNON * * * | | | | THIS REPORT IS BEING RETRACTED AFTER AN ENGINEERING OPERABILITY EVALUATION | | CONCLUDED THAT AT NO TIME DURING THE EVOLUTION OF THE ABOVE MENTIONED TEST | | ON THE INOPERABLE PUMP DID THE TEST AFFECT THE OPERABILITY OF THE RUNNING | | PUMP. THE R3DO (MADERA) & NMSS EO (FRED COMBS) WERE NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS RETRACTION BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32092 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 03:39[CDT]| |NRC NOTIFIED BY: YURKOVICH |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO IMPLEMENT COMPENSATORY MEASURES WITHIN TEN MINUTES FOR A | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM FUNCTIONS | | | | AT 0339 CDT, THE LICENSEE DISCOVERED THAT COMPENSATORY MEASURES FOR A | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM FUNCTIONS HAD NOT BEEN | | IMPLEMENTED WITHIN TEN MINUTES AS REQUIRED BY THE STATION SECURITY PLAN. | | COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE'S | | INVESTIGATION IS ONGOING. (REFER TO THE HOO LOG FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1442EDT 4/10/97 FROM STEVE ROONEY TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | UPON INVESTIGATION OF THE EVENT IT WAS DETERMINED THAT THE COMPENSATORY | | MEASURES, WHICH WERE NOT IMPLEMENTED WITHIN 10 MINUTES, WERE NOT REQUIRED. | | THE COMPENSATORY MEASURES WERE ENTERED AS A PRECAUTIONARY MEASURE ONLY. NO | | UNCOMPENSATED FAILURE OR DEGRADATION OF ANY PORTION OF THE SAFEGUARDS | | SYSTEM WHICH COULD HAVE ALLOWED UNAUTHORIZED OR UNDETECTED ACCESS TO THE | | VITAL OR PROTECTED AREAS OCCURRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND REGIONAL OFFICE. | | NOTIFIED R3DO(MADERA). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32093 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 12:14 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 11:25[EDT]| |NRC NOTIFIED BY: DICK CZARNECKI |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DISCOVERY OF SUSPECTED CONTRABAND INSIDE PROTECTED AREA - | | | | A SUSPECTED DRUG SMOKING DEVICE WAS FOUND IN A PORTABLE TOILET INSIDE THE | | PROTECTED AREA. THE LICENSEE HAS TAKEN COMPENSATORY MEASURES AND IS | | CONTINUING ITS INVESTIGATION. (REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1400EDT 4/11/97 FROM CZARNECKI TO C. GOULD * * * | | | | THE LICENSEE IS RECLASSIFYING THIS EVENT BASED ON THE FOLLOWING: | | | | "FPL IS REVISING THIS EVENT AS BEING REPORTABLE PURSUANT TO 10 CFR PART 26 | | INSTEAD OF 10 CFR PART 73. FPL MADE THE INITIAL REPORT BASED ON THE | | POSSIBILITY THAT THE EVENT MAY HAVE CONSTITUTED A CRIMINAL ACT. FURTHER | | INVESTIGATION HAS REVEALED THAT THIS INCIDENT HAS LITTLE OR NO SAFEGUARDS | | SIGNIFICANCE AS DESCRIBED IN 10 CFR 73.71 OR APPENDIX G TO PART 73. THE | | REPORTABILITY OF THIS EVENT IS BEING RECLASSIFIED AS BEING A 24 HOUR REPORT | | REQUIRED BY 10 CFR 26.73. THE EVENT IS REPORTABLE AS A FITNESS FOR DUTY | | (FFD) REPORT IN ACCORDANCE WITH CLARIFYING GUIDANCE PROVIDED BY THE NRC | | GENERIC LETTER 91-03." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO(SKINNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32127 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/10/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 18:12 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/10/97 | +------------------------------------------------+EVENT TIME: 17:04[EDT]| |NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION POTENTIALLY AFFECTING THE PERFORMANCE | | OF 480-VOLT MOTOR CONTROL CENTER BREAKERS DURING A SEISMIC EVENT. | | | | "DETROIT EDISON HAS IDENTIFIED THAT CERTAIN 480-VOLT MOTOR CONTROL CENTER | | FUSED DISCONNECT SWITCHES (BREAKERS) AT THE FERMI-2 SITE MAY NOT FULLY | | LATCH WHEN PLACED IN THE 'ON' POSITION. AT LEAST THREE INSTANCES HAVE | | RECENTLY BEEN IDENTIFIED WHERE ELECTRICAL CONTACT HAS BEEN OBTAINED, YET | | THE BREAKER TRIPS FREE FOR NO APPARENT REASON. BASED ON A REVIEW OF THE | | CONDITION, DETROIT EDISON BELIEVES THAT THE BREAKERS MAY, ON RARE | | OCCASIONS, NOT FULLY LATCH CLOSED IN THE 'ON' POSITION. THESE CIRCUIT | | BREAKERS MAY NOT BE SEISMICALLY QUALIFIED UNLESS THEY ARE IN THE FULLY | | LATCHED CONDITION. DETROIT EDISON IS REPORTING THIS AS A POTENTIAL | | CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF A SAFETY | | FUNCTION OF STRUCTURES OR SYSTEMS THAT ARE NEEDED TO MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. AT THIS TIME THERE IS NO REASON TO BELIEVE | | THAT THERE ARE MUTUALLY REDUNDANT COMPONENTS OR MULTIPLE SYSTEMS OR | | INDEPENDENT TRAINS OR CHANNELS THAT ARE IN THIS CONFIGURATION, BUT THERE IS | | NO POSITIVE MANNER AVAILABLE TO CONFIRM THIS. PRELIMINARY INVESTIGATION | | INDICATES THAT THIS CONDITION IS CAUSED BY, OR EXACERBATED BY, LACK OF | | PROPER LUBRICATION FOR THE BREAKER LINKAGE MECHANISM. THE TOTAL POPULATION | | OF BREAKERS THAT ARE POTENTIALLY SUSCEPTIBLE TO THIS CONDITION IS | | APPROXIMATELY 800, APPROXIMATELY 273 OF WHICH ARE SAFETY RELATED. AS THIS | | CONDITION IS INVESTIGATED AND CORRECTED, THE AS-FOUND CONDITION OF THE | | BREAKERS WILL BE DOCUMENTED SO THE MAGNITUDE OF THE CONDITION CAN BE | | IDENTIFIED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1202EDT 4/11/97 FROM JOE SKLARCCYK TO S. SANDIN * * * | | | | THE LICENSEE FURNISHED THE FOLLOWING ADDITIONAL INFORMATION: | | | | BREAKER MANUFACTURER: GOULD ITE 5600 SERIES CATALOG #7860 | | | | MODE OF OPERATION AT TIME OF OCCURRENCES: | | | | 2/04/97 2125 HOURS MODE 4 | | 3/19/97 0012 HOURS MODE 4 | | 4/03/97 1940 HOURS MODE 4 | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(MADERA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32129 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/11/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 00:20 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/10/97 | +------------------------------------------------+EVENT TIME: 22:36[CDT]| |NRC NOTIFIED BY: DALY |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOHN ZWOLINSKI EO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP |RICH BARRETT (IRD) AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN DUE TO AUXILIARY CONTACT HOUSING ON MERLIN | | GERLIN BREAKERS BEING SUSCEPTIBLE TO CRACKING OF THE OPEN/CLOSE LIMIT | | SWITCH. | | | | UPON INSPECTION OF MERLIN GERLIN 4KV BREAKERS, IT HAS BEEN DETERMINED THAT | | THIS TYPE OF BREAKER IS SUSCEPTIBLE TO CRACKING OF THE OPEN/CLOSED LIMIT | | SWITCH ASSEMBLY. FAILURE MODE WOULD RESULT IN THE BREAKER POSITION | | DISAGREEING WITH CONTROL ROOM INDICATION WHEN THE BREAKER IS CALLED UPON TO | | OPERATE. CONSERVATIVELY, ANY EQUIPMENT UTILIZING THIS TYPE OF BREAKER WAS | | DECLARED INOPERABLE AT 2112 CDT. THIS RENDERS VARIOUS SYSTEMS INOPERABLE, | | THE CONTAINMENT COOLING SERVICE WATER SYSTEM BEING THE MOST LIMITING | | (SUPPLIES COOLING WATER TO THE LPCI HEAT EXCHANGERS). SHUTDOWN OF UNIT 2 | | COMMENCED AT 2236 CDT PER TECHNICAL SPECIFICATION 3.8.A.1.d (12 HOURS TO BE | | IN HOT SHUTDOWN CONDITION FROM 2112 CDT). ALL EMERGENCY CORE COOLING | | SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED. | | THE LICENSEE BELIEVES THAT THE BREAKERS WERE SUPPLIED BY GOLDEN GATE | | SWITCHBOARD (LOCATED IN NAPA, CA). THE LICENSEE BELIEVES THAT 60 OF THESE | | BREAKERS ARE ONSITE (SOME INSTALLED ON UNIT 2, UNIT 3 AND SOME SPARE | | BREAKERS). THE NEED FOR A PART 21 NOTIFICATION IS BEING EVALUATED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | SEE SIMILAR EVENT CALLED IN BY QUAD CITIES UNIT 1 (EVENT # 32114) ON | | 04/09/97. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32130 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/11/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 08:32 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 05:03[EDT]| |NRC NOTIFIED BY: ADAMSON |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL THREE TURBINE AUXILIARY FEEDWATER PUMPS STARTED ON A LOSS OF ALL | | FEEDWATER SIGNAL. | | | | WHILE STARTING THE "3B" STEAM GENERATOR FEEDWATER PUMP THE FEEDWATER | | BREAKER FAILED TO CLOSE. THE CONTROL SWITCH FOR THE STEAM GENERATOR | | FEEDWATER PUMP WAS RETURNED TO THE MID-POSITION WITH NO OTHER STEAM | | GENERATOR FEEDWATER PUMPS OPERATING. THIS COMPLETED THE LOGIC SIGNAL (LOSS | | OF ALL FEEDWATER) FOR THE ACTIVATION OF ALL THREE TURBINE AUXILIARY | | FEEDWATER PUMPS. THE LOSS OF ALL FEEDWATER SIGNAL IS LISTED IN TECHNICAL | | SPECIFICATION TABLE 3.3-2 ITEM (6)(e). THE AUXILIARY FEEDWATER WATER SYSTEM | | HAS BEEN RESTORED TO ITS NORMAL LINEUP. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32131 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:16 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 09:57[EDT]| |NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEW JERSEY STATE DEPARTMENT OF ENVIRONMENTAL | | PROTECTION OF A MINOR OIL SPILL TO THE DELAWARE RIVER. | | | | "WHILE REPOSITIONING THE INTAKE STRUCTURE TRASH RAKE, THE MOTOR GEAR BOX | | FOR THE UNIT STRUCK A SCAFFOLDING KNUCKLE. THE KNUCKLE DISTORTED THE | | GEARBOX SUCH THAT INTERNAL LUBRICATING OIL SPILLED OUT (APPROXIMATELY 1 | | PINT). SOME OF THIS OIL FELL THROUGH A GRATING INTO THE DELAWARE RIVER. | | ALTHOUGH MOST OF THIS SPILLAGE LANDED ON SOME DEAD MARSH GRASS, THE WAVE | | ACTION IS WASHING THE LUBRICANT RESULTING IN A SMALL OIL SHEEN. THIS | | REPORT IS BEING MADE DUE TO THE REQUIRED NOTIFICATION OF OUR ENVIRONMENTAL | | LICENSING GROUP TO THE UNITED STATES COAST GUARD/NATIONAL RESPONSE CENTER | | (NAT. RESP. CENTER CASE # IS 383327). ADDITIONALLY, THE NEW JERSEY | | DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS NOTIFIED OF THE EVENT (NJDEP | | CASE # 97-4-11-1013-46). THE PLANT CONTINUES TO RUN AT 100% POWER WITH NO | | OTHER SYSTEMS AFFECTED BY THIS EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32132 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/11/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 13:17 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: STEPHEN M. SMITH |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION OF A MINOR SANITATION LINE SPILL TO THE DISCHARGE CANAL. | | | | "AT 1145 HOURS, INDIAN POINT 3 NOTIFIED THE NYS DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION (SPILL REPORT #97-0059) OF A SANITATION LINE SPILL VIA A STORM | | DRAIN TO THE PLANT DISCHARGE CANAL. THIS OCCURRED AS A RESULT OF | | DEWATERING OF AN EXCAVATION PIT THROUGH WHICH A CRACKED SANITATION LINE | | RAN." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32133 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 14:05 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 13:45[EDT]| |NRC NOTIFIED BY: JIM ANDERSON |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO YELLOW NYLON BAGS LABELLED "CAUTION RADIOACTIVE MATERIAL" WERE FOUND AT | | THE SCENE OF A FATAL AUTO ACCIDENT. | | | | A CONTRACT EMPLOYEE HIRED FOR THE UNIT 2 OUTAGE WAS KILLED IN AN AUTO | | ACCIDENT APPROXIMATELY 15 MILES NORTH OF THE SITE. TWO YELLOW NYLON BAGS | | LABELLED "CAUTION RADIOACTIVE MATERIAL" WERE IN THE VEHICLE. LOCAL AND | | STATE AGENCIES RESPONDED TO THE SCENE AND CONFIRMED THAT THE BAGS WERE NOT | | CONTAMINATED. THE LICENSEE NOTED THAT THERE WAS MEDIA INTEREST IN THE | | ACCIDENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: HENNIG |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THAT THE ALARM SETPOINT OF 105 AMPS FOR THE P15A HIGH | | HEAD SI PUMP MOTOR PROTECTIVE RELAY WAS NON-CONSERVATIVE. | | | | "DURING AN EXTENSIVE REVIEW OF A 10 CFR 50.59 SAFETY EVALUATION FOR THE | | RESETTING OF THE P15A HIGH HEAD SI PUMP MOTOR PROTECTIVE RELAYING, IT WAS | | DETERMINED THAT THE EVALUATION WAS IN ERROR IN ALLOWING THE ALARM PORTION | | OF THE RELAY TO BE SET ABOVE THE MAXIMUM FULL LOAD CURRENT TIMES THE | | SERVICE FACTOR. FULL LOAD (85 AMPS) TIMES SERVICE FACTOR (1.15) EQUALS | | 97.75 AMPS. HOWEVER, THE ALARM WAS SET TO 105 AMPS. THIS WOULD PREVENT | | THE RECEIPT OF AN OPERATOR ANNUNCIATOR PROVIDING INDICATION OF PUMP | | OPERATION OUTSIDE IT'S DESIGN BASIS. THE RELAYING WAS RESET ON FEB 6, 1997 | | AND UNIT 1 WAS SHUTDOWN FOR AN EXTENDED MAINTENANCE OUTAGE ON FEB 18, 1997. | | THE RELAYING FOR UNIT 2 HAD ALSO BEEN RESET ON FEB 6, 1997 BUT SINCE THE | | UNIT WAS DEFUELED THE CONDITION IS NOT REPORTABLE FOR UNIT 2. BOTH UNIT 1 | | AND 2 P15A HIGH HEAD SI PUMPS HAVE BEEN DECLARED INOPERABLE. AS CORRECTIVE | | ACTION THE RELAYS WILL BE RECALIBRATED OR MODIFIED TO ENSURE PROTECTION AND | | ALARMS ARE PROVIDED FOR DESIGN CONDITIONS BEFORE LEAVING COLD SHUTDOWN." | | | | THE LICENSEE INITIATED THE 50.59 EVALUATION IN RESPONSE TO AN EVENT WHICH | | OCCURRED DURING TESTING ON FEB 5, 1997 (SEE EVENT #31737). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MERCK PHARMACEUTICAL |NOTIFICATION DATE: 04/11/97 | | CITY: REGION: 1 |NOTIFICATION TIME: 18:57 [ET]| | COUNTY: UNION COUNTY STATE: NJ |EVENT DATE: 04/11/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/11/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES NOGGLE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BOB STERN (NJ DEP) | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (NJDEP) RADIATION | | PROTECTION PROGRAM OFFICE WAS NOTIFIED BY MERCK PHARMACEUTICAL THAT A 2ml | | SOLUTION CONTAINING I-125 WAS INADVERTENTLY DISPOSED OF IN THE NORMAL TRASH | | SOMETIME THIS AFTERNOON . MERCK IS ATTEMPTING TO RECLAIM THE MATERIAL FROM | | THE UNION COUNTY UTILITY AUTHORITY PRIOR TO INCINERATION. THE NJDEP | | ESTIMATES THAT 880ęCi OF I-125 IS INVOLVED AND THAT AN INDIVIDUAL PRESENT | | AT THE TIME OF INCINERATION COULD INHALE MATERIAL EXCEEDING THE MAXIMUM | | PERMISSIBLE CONCENTRATION (MPC). THE STATE OFFICIAL WAS EXPECTING | | ADDITIONAL INFORMATION FROM MERCK BEFORE DETERMINING WHETHER THE STATE | | WOULD RESPOND. THE ADDRESS OF THE MERCK FACILITY AND LOCATION OF THE | | DISPOSAL SITE WERE NOT AVAILABLE AT THE TIME OF THIS REPORT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32136 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 19:09 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 16:43[CDT]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A DEGRADED TUBE NOT MEETING THE MARGINS REQUIRED BY | | REG. GUIDE 1.121 DURING INSPECTION OF THE '1C' STEAM GENERATOR (SG). | | | | "ON 4/11/97 FARLEY NUCLEAR PLANT WAS SHUTDOWN IN A REFUELING OUTAGE | | CONDUCTING EDDY CURRENT INSPECTION OF SG's. FNP IS APPROVED TO USE THE | | ALTERNATE REPAIR CRITERIA FOR TUBE SUPPORT PLATES. WHILE INSPECTING THE | | '1C' SG WITH THE BOBBIN PROBE, A 13.97 VOLT INDICATION WAS FOUND AT THE | | FIRST SUPPORT PLATE INTERSECTION. THIS VOLTAGE CORRESPONDS TO A BURST | | PRESSURE (FOR A FREE SPAN TUBE LENGTH) THAT DOES NOT MEET THE MARGINS | | REQUIRED BY REG. GUIDE 1.121 WHICH IS THE BASIS FOR THE ALTERNATE REPAIR | | CRITERIA. THUS, THIS CONDITION IS REPORTABLE UNDER 50.72(b)(2)(i). | | ADDITIONAL INFORMATION: | | | | 1. THERE WAS NO SIGNIFICANT PRIMARY TO SECONDARY LEAKAGE PRIOR TO | | SHUTDOWN. | | | | 2. THE ESTIMATED BURST PRESSURE FOR THE 13 VOLT INDICATION WAS | | APPROXIMATELY 3300 PSI WHICH IS ABOVE THE MAXIMUM STEAM LINE BREAK | | DIFFERENTIAL PRESSURE THAT THE TUBE WOULD EXPERIENCE IN A DESIGN BASIS | | ACCIDENT. | | | | 3. FURTHER PLUS POINT AND OTHER NDE WILL BE CONDUCTED ON THIS INTERSECTION | | TO BETTER CHARACTERIZE THE NATURE OF THE INDICATION. | | | | 4. THE PREVIOUS OUTAGE BOBBIN VOLTAGE WAS APPROXIMATELY 1.4 VOLTS. | | | | ADDITIONAL DATA IS BEING COLLECTED TO FURTHER CHARACTERIZE THE FLAW AND THE | | NATURE OF THE DEGRADATION. THE TUBE (ROW 2, COLUMN 85) WILL BE REPAIRED OR | | PLUGGED." | | | | ALL THREE STEAM GENERATORS ARE CLASSIFIED "C-3" WITH INSPECTION OF THE '1A' | | 90%, THE '1B' 100% AND THE '1C' 99% COMPLETED. NO OTHER INDICATIONS OF | | THIS NATURE HAVE BEEN FOUND. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32137 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 19:26 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 18:21[CDT]| |NRC NOTIFIED BY: RICHARD FLACK |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED THAT CONTROL ROOM VENTILATION WOULD NOT ISOLATE | | UNDER CERTAIN ACCIDENT CONDITIONS ASSUMING A SINGLE FAILURE. | | | | "FOR THE POSTULATED FUEL HANDLING ACCIDENT, THE RADIATION MONITORING SYSTEM | | POTENTIALLY DOES NOT PROVIDE CONTROL ROOM VENTILATION ISOLATION WITHIN THE | | SINGLE FAILURE DESIGN. THE CONTROL ROOM VENT OUTSIDE AIR SUPPLY HAS BEEN | | ISOLATED. NO FUEL HANDLING WAS IN PROGRESS. UNDER LOCA EVENTS A REDUNDANT | | SAFETY INJECTION SIGNAL WOULD PROVIDE ISOLATION OF CONTROL ROOM | | VENTILATION. THE CONTROL ROOM VENTILATION SYSTEM IS OPERABLE WITH THE | | OUTSIDE AIR DAMPERS ISOLATED." | | | | BOTH UNITS SHARE A COMMON CONTROL ROOM. THERE ARE TWO TRAINS OF CONTROL | | ROOM VENTILATION. EACH TRAIN RECEIVES AN INDEPENDENT RAD MONITOR AND | | REDUNDANT ESF INPUTS FOR ACTUATION. DURING A FUEL HANDLING ACCIDENT WHEN | | NO ESF ACTUATION WOULD OCCUR, A FAILURE OF EITHER RAD MONITOR WOULD RESULT | | IN THAT TRAIN OF CONTROL ROOM VENTILATION NOT ISOLATING. THIS CONDITION | | WAS DISCOVERED BY A SYSTEM ENGINEER DURING A DESIGN REVIEW. THE LICENSEE | | WILL DETERMINE APPROPRIATE CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32138 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/11/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 19:37 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 18:58[EDT]| |NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED ADDITIONAL WIRING DISCREPANCIES ON THE DIVISION I | | SERVICE WATER DISCHARGE VALVE ASSOCIATED WITH THE EDG COOLER OUTLET. | | | | "DURING IMPLEMENTATION OF MODIFICATION TO 2SWP*MOV66A, WIRING DISCREPANCIES | | WERE FOUND WHICH WOULD HAVE RENDERED THE VALVE INOPERABLE UNDER DESIGN | | COMMITMENTS IN THE NMP2 UPDATED SAFETY ANALYSIS REPORT APPENDIX SECTION | | 9B.8.2.3, SOLUTIONS TO CONTROL/RELAY ROOM FIRE. A SIMILAR CONDITION WAS | | PREVIOUSLY ADDRESSED IN THE EVENT REPORTED UNDER 10CFR 50.72(b)(ii)(B) ON | | 4/7/97 AT 1630EST, UNDER WHICH BOTH 2SWP*MOV66A AND 2SWP*MOV66B WERE | | SIMILARLY EFFECTED. NOTE, HOWEVER, THE FIELD WIRING DISCREPANCIES WERE | | ONLY FOUND ON THE DIVISION I VALVE 2SWP*MOV66A. THE WIRING DISCREPANCIES | | HAVE BEEN CORRECTED. | | | | NMP2 CONTINUES IN TECH SPEC LCO 3.3.7.4 ACTION b FOR THE REMOTE SHUTDOWN | | SYSTEM ENTERED 4/7/97 AT 1630 HOURS. | | | | THIS NOTIFICATION IS BEING MADE PER 10CFR50.72(b)(1)(ii)(B) FOR ANY EVENT | | OR CONDITION DURING OPERATION THAT RESULTS IN THE CONDITION OF THE NUCLEAR | | POWER PLANT, INCLUDING THE PRINCIPAL SAFETY BARRIERS BEING IN A CONDITION | | THAT IS OUTSIDE THE DESIGN BASIS OF THE PLANT." | | | | THE LICENSEE IS CURRENTLY IN THE POST MAINTENANCE TESTING PHASE (PMT) OF | | THE MODIFICATION. THERE ARE NO OTHER SUSPECTED INSTANCES OF THIS NATURE. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32139 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 20:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: CALVIN FIELDS |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 LICENSEE DISCOVERED A CONDITION WHICH WOULD HAVE IMPACTED LONG TERM | | OPERABILITY OF ECCS DURING A POSTULATED ACCIDENT. | | | | "ON 4/11/97 AT 1930 HOURS, BASED ON THE EVALUATION OF CONDITIONS DOCUMENTED | | ON SQ970871 PER, THE FOLLOWING CALL IS MADE. DURING UNIT 1 SHUTDOWN ON | | 3/22/97 FOR APPROXIMATELY 2 HOURS OF MODE 4 OPERATION AND BEFORE MODE 5 | | ENTRY, AN OIL CLOTH WAS INTRODUCED INTO CONTAINMENT. THE CLOTH WAS OF SUCH | | A SIZE THAT HAD AN ACCIDENT OCCURRED NECESSITATING THE USE OF CONTAINMENT | | SPRAY, THE POSSIBILITY OF THE OIL CLOTH COMING FREE OF ITS RESTRAINTS AND | | BLOCKING ONE OR BOTH OF THE REFUELING DRAINS FROM ALLOWING INVENTORY IN | | UPPER CONTAINMENT TO FLOW FREELY TO THE CONTAINMENT SUMP IN LOWER | | CONTAINMENT EXISTED. THIS MEANT THAT LONG TERM OPERABILITY OF THE ECCS AT | | THE TIME OF RWST/CONTAINMENT SUMP SWAPOVER COULD NOT HAVE BEEN GUARANTEED. | | | | THEREFORE, THIS MEANS THE ECCS WAS CONSIDERED OUTSIDE OF THE DESIGN BASIS | | WHILE IN THIS CONDITION DURING MODE 4. ADDITIONAL DETAILS TO FOLLOW IN A | | WRITTEN REPORT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32140 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 23:28 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 19:28[CDT]| |NRC NOTIFIED BY: BART CROW |LAST UPDATE DATE: 04/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHNSON/MADERA RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | |LYNCH SP | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 LICENSEE WAS INFORMED BY IOWA AUTHORITIES THAT A TRUCK CONTAINING LOW | | LEVEL WASTE FROM CNS HAD OVERTURNED ON I-80. | | | | "AN INTERSTATE NUCLEAR SERVICES (INS) TRUCK CONTAINING LOW LEVEL | | CONTAMINATED CLOTHING OVERTURNED ON INTERSTATE 80 NEAR MILE MARKER 248 IN | | JOHNSON COUNTY, IOWA. THE INS TRUCK WAS CARRYING 15 METAL CONTAINERS OF | | CONTAMINATED CLOTHING BEING TRANSPORTED FROM COOPER NUCLEAR STATION TO THE | | INS CORPORATION IN MORRIS, ILL., TO BE LAUNDERED. | | | | AT 1928CDT ON 4/11/97 THE CEDAR RAPIDS STATE PATROL NOTIFIED THE CNS | | CONTROL ROOM OF THE INCIDENT AND REQUESTED INFORMATION ON THE CONTENTS OF | | THE TRUCK. PRELIMINARY REPORTS INDICATE THAT THE TRUCK HAD ROLLED GENTLY | | ON ITS SIDE AND DID NOT APPEAR TO BE SIGNIFICANTLY DAMAGED. CNS HAS BEEN | | IN DIRECT CONTACT WITH THE ONSITE HAZMAT TEAM. THE MAXIMUM VEHICLE SURFACE | | CONTACT READING OF THE SHIPMENT WAS 3.5 mr/hr AND 0.2 mr/hr AT 6.6 FEET | | WHEN THE SHIPMENT LEFT COOPER NUCLEAR STATION. THE CONTAMINATED CLOTHING | | IS SHIPPED IN DOUBLE BAGS LOCATED INSIDE THE METAL CONTAINERS WHICH ARE | | APPROXIMATELY 3'x 3'x 6'. INITIAL ENTRY BY THE HAZMAT TEAM INDICATE THE | | CONTAINERS APPEAR TO BE INTACT. ARRANGEMENTS ARE BEING MADE TO SECURE THE | | SCENE AND TRANSFER THE CONTENTS TO ANOTHER TRUCK. IF CONDITIONS CHANGE A | | FOLLOW UP REPORT WILL BE ISSUED." | | | | THE LICENSEE SAID THAT LAW ENFORCEMENT OFFICIALS ON THE SCENE HAD INFORMED | | DOT. A PRESS RELEASE WILL PROBABLY BE ISSUED. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32141 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/12/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 11:12 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/12/97 | +------------------------------------------------+EVENT TIME: 06:30[CDT]| |NRC NOTIFIED BY: BOSTON |LAST UPDATE DATE: 04/12/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHNSON RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT 0432 CDT, A NON-LICENSED EMPLOYEE ATTEMPTED TO ENTER THE PROTECTED AREA | | WITH A SMALL QUANTITY OF MARIJUANA. THE MATERIAL WAS CONFISCATED, AND LOCAL | | POLICE WERE NOTIFIED AND RESPONDED TO THE SITE AT 0630 CDT. THE INDIVIDUAL | | IS BEING GIVEN A FOR-CAUSE DRUG TEST. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32142 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/12/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/12/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: BILL MAGUIRE |LAST UPDATE DATE: 04/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE 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 23 POWER OPERATION | 23 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FOUR OF SIX STEAM FLOODING DAMPERS FAILED TO CLOSE DURING SURVEILLANCE | | TESTING. | | | | "ON APRIL 12, 1997 AT 1515EDT, THE CONTROL ROOM WAS NOTIFIED THAT FOUR | | STEAM FLOODING DAMPERS HAD FAILED TO CLOSE DURING TESTING. THE FOUR | | DAMPERS CONSISTED OF TWO PAIRS OF TWO DAMPERS THAT COMMUNICATE BETWEEN THE | | MAIN STEAM CHASE ON UNIT 1 REACTOR ELEVATIONS 253' AND 283' RESPECTIVELY. | | THE DAMPERS ARE REQUIRED TO CLOSE FOLLOWING A STEAM LINE BREAK IN THE | | OUTBOARD MSIV ROOM TO PROTECT SAFETY RELATED EQUIPMENT IN THE ADJOINING | | ROOMS. | | | | "SAFETY RELATED EQUIPMENT LOCATED IN THE ADJOINING ROOM ON ELEVATION 253 | | INCLUDE THE SCRAM SOLENOIDS AND HCUs, THE REDUNDANT REACTIVITY CONTROL | | SYSTEM SOLENOIDS, AND SEVERAL ECCS MOV ELECTRICAL BREAKERS. IF A HIGH | | ENERGY LINE BREAK (HELB) HAD OCCURRED IN THE OUTBOARD MSIV ROOM AND THE | | DAMPERS HAD FAILED TO CLOSE, THE ABILITY TO SHUTDOWN THE PLANT MAY HAVE | | BEEN ADVERSELY IMPACTED. | | | | CURRENTLY, THESE FOUR STEAM FLOODING DAMPERS HAVE BEEN CLEANED, LUBRICATED, | | AND RETESTED SATISFACTORILY." | | | | THERE ARE A TOTAL OF 210 STATION DAMPERS; 65 ASSOCIATED WITH EACH UNIT AND | | 80 SHARED OR COMMON TO BOTH UNITS. THESE DAMPERS ARE TESTED EVERY 4 YEARS. | | DUE TO THE RECENT TESTING OF UNIT 2 DAMPERS IN FEBRUARY 1997, AN AUGMENTED | | TESTING PROGRAM WAS IMPLEMENTED. SIX OF THE UNIT 1 DAMPERS WERE NOT TESTED | | IN FEBRUARY 1996 DUE TO ALARA CONSIDERATIONS. THE FOUR FAILURES DESCRIBED | | ABOVE ARE FROM THOSE SIX NOT PREVIOUSLY TESTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32143 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/13/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 15:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/13/97 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: JAMES R. BARNES |LAST UPDATE DATE: 04/13/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED LOSS OF 120/240VAC VITAL BUS DURING TESTING OF "2A" EMERGENCY | | DIESEL GENERATOR (EDG). | | | | "AT APPROXIMATELY 1350EDT DURING THE PERFORMANCE OF 42SV-R43-008-OS (DIESEL | | GENERATOR LOCA/LOSP LOGIC SYSTEM FUNCTIONAL TEST) THE VITAL AC BUS WAS | | DEENERGIZED WHEN ITS ALTERNATE SUPPLY BREAKER WAS RACKED TO THE TEST | | POSITION. THIS RESULTED IN AN ESF WHEN THE FISSION PRODUCT SAMPLE VALVE | | 2D11-F050 CLOSED. VITAL AC SYS WAS RESTORED VIA THE NORMAL SUPPLY AND ALL | | CONDITIONS RESET. | | | | AFTER REVIEW OF THE ABOVE EVENT AT 1445EDT IT WAS DISCOVERED THAT THE | | EMERGENCY RESPONSE DATA SYSTEM WAS ALSO LOST AS A RESULT OF THE | | DEENERGIZATION OF THE VITAL AC SYS. THIS SYSTEM WAS ALSO RESET AND IS NOW | | FUNCTIONAL." | | | | PRIOR TO THE TEST, THE STATIC TRANSFER SWITCH WAS ALIGNED TO THE ALTERNATE | | POWER SUPPLY WHICH IS THE 600VAC BUS "2C". THE NORMAL POWER SUPPLY IS FROM | | THE 120/240VAC STATIC INVERTER ASSOCIATED WITH THE 125VDC BATTERY FLOATED | | BY A 125VDC BATTERY CHARGER CONNECTED TO THE 600VAC BUS "2D". WHEN THE | | ALTERNATE SUPPLY BREAKER WAS OPENED PER THE TEST PROCEDURE FOR THE "2A" | | EDG, THE 120/240 V VITAL AC DISTRIBUTION CABINET "2A" WAS DEENERGIZED | | RESULTING IN THE LOSS OF THOSE LOADS IDENTIFIED ABOVE. THE LICENSEE | | ATTRIBUTES THE CAUSE TO AN INADEQUATE PROCEDURE WHICH DID NOT HAVE AS A | | PREREQUISITE VERIFICATION THAT THE STATIC TRANSFER SWITCH WAS ALIGNED TO | | THE NORMAL POWER SUPPLY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 32144 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SPERRY-SUN DRILLING SERVICES |NOTIFICATION DATE: 04/13/97 | | CITY: LAFAYETTE REGION: 4 |NOTIFICATION TIME: 19:49 [ET]| | COUNTY: STATE: LA |EVENT DATE: 04/13/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 04/13/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM JOHNSON RDO | | | | +------------------------------------------------+LINDA HOWELL R4 | |NRC NOTIFIED BY: CHRISTOPHER BROWN | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE REQUESTED NRC APPROVAL TO ABANDON TWO WELL LOGGING SOURCES. | | | | SPERRY-SUN DRILLING SERVICES LOCATED IN LAFAYETTE, LA. WAS NOTIFIED BY | | AMOCO PRODUCTION COMPANY THAT EFFORTS TO RETRIEVE TWO SOURCES OVER THE PAST | | FIVE DAYS WERE UNSUCCESSFUL. THE LICENSEE IS REQUESTING IMMEDIATE NRC | | APPROVAL TO IMPLEMENT WELL LOGGING SOURCE ABANDONMENT PROCEDURES. | | | | SPECIFIC INFORMATION ON SOURCE IDENTIFICATION AND LOCATION: | | | | SOURCES (2): 3 Ci Am241-Be AND 2 Ci Cs-137 | | WELL IDENTIFICATION: 0CSG5504A-8 LOCATED ON EUGENE ISLAND, BLOCK 224, | | OFFSHORE LA. | | | | THE NEUTRON AND DENSITY SOURCES ARE LOCATED AT 14,298 AND 14,257 FT. DEPTH, | | RESPECTIVELY. THE WELL DEPTH IS 14,365 FT. THE TOP OF THE PIPE IS 13,400 | | FT. WITH THE PLUG POURED TO 13,250 FT. | | | | ESTABLISHED A CONFERENCE BETWEEN R4(HOWELL) AND THE LICENSEE. | +------------------------------------------------------------------------------+