U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/06/97 - 05/07/97 ** EVENT NUMBERS ** 32258 32271 32280 32281 32282 32283 32284 32285 32286 32287 32288 32289 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/01/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:20 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:50[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/06/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MARK RING RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE INSTALLED ACTUATORS ON AUTOCLAVES ARE RATED AT 40 PSIG INSTEAD OF BEING | | RATED AT 80 PSIG. | | | | ON 05/01/97, DURING AN INVESTIGATION INTO NRC EVENT NOTIFICATION #32224, | | THE XV-532 AND CV-533 VALVES ON AUTOCLAVE 2 NORTH AND 2 SOUTH IN BUILDING | | C-333-A (FEED VAPORIZATION FACILITY) AND AUTOCLAVE 1 EAST AT BUILDING | | C-337-A (FEED VAPORIZATION FACILITY) AND THE CV-533 VALVE ON AUTOCLAVE 1 | | WEST AT C-337-A WERE DISCOVERED TO HAVE ACTUATORS THAT MAY NOT BE CAPABLE | | OF SERVING THEIR CONTAINMENT SAFETY FUNCTION. SPECIFICALLY, THE INSTALLED | | AIR ACTUATORS (DESIGNED TO CLOSE ON LOSS OF AIR) ARE RATED AT A 40-PSIG | | OPERATING PRESSURE, ALTHOUGH THE MANUFACTURER STATED THAT AN 80-PSIG | | ACTUATOR IS REQUIRED. THE XV-532 AND CV-533 VALVES ARE THE INNER AND OUTER | | CONTAINMENT VALVES ON THE STEAM SAMPLE HEADER AND ARE REQUIRED BY THE | | TECHNICAL SPECIFICATION REQUIREMENT (TSR) TO CLOSE WITHIN 10 SECONDS. | | | | AUTOCLAVES 2 NORTH AND 2 SOUTH IN BUILDING C-333-A WERE IN MODE 6 (OUT OF | | SERVICE) AND INOPERABLE AT THE TIME OF DISCOVERY. AUTOCLAVES 1 EAST AND 1 | | WEST IN BUILDING C-337-A WERE IN MODE 5 (HEATING) AT THE TIME OF DISCOVERY. | | AUTOCLAVE 1 EAST WAS PLACED IN MODE 2 (AUTOCLAVE OPEN) WITHIN 1 HOUR AS | | REQUIRED BY TSR 2.2.3.1B. AUTOCLAVE WEST WILL FINISH THE EXISTING OPERATING | | CYCLE AND THEN BE PLACED IN MODE 2 AS REQUIRED BY TSR 2.2.3.1A. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1414 ON 05/06/97, FROM UNDERWOOD TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE FOLLOWING TEXT IS FROM A | | FACSIMILE SUBMITTED BY THE CERTIFICATE HOLDER: | | | | "THIS WORK SHEET IS PROVIDED TO DOCUMENT OUR RETRACTION OF NRC REPORT NO. | | 32258 MADE ON 05/01/97. THIS NOTIFICATION REPORTED THAT SAFETY SYSTEM VALVE | | OPERATORS WERE DISCOVERED IN FEED AUTOCLAVE POSITIONS WHICH MAY NOT BE ABLE | | TO PERFORM THEIR INTENDED FUNCTION. THIS DISCOVERY WAS MADE AS A PART OF | | OUR ONGOING INVESTIGATION OF A PREVIOUS FINDING REPORTED ON 04/24/97 | | (REFERENCE NRC REPORT NO. 32224). THE REFERENCED NOTIFICATION REPORTED TWO | | REDUNDANT VALVES WHICH FAILED TO CLOSE UPON OPERATOR DEMAND WHEN REQUIRED | | BY TSR TO BE OPERABLE. OUR REVIEW OF NRC REPORT NO. 32258 HAS REVEALED THAT | | THE SUSPECT VALVES FOUND IN OTHER AUTOCLAVE POSITIONS, ALTHOUGH SUSPECT, | | HAD NOT FAILED TO OPERATE WHEN REQUIRED. THUS, NRC REPORT NO. 32258 IS NOT | | REPORTABLE UNDER 10 CFR 76.120(c)(2), 'SAFETY EQUIPMENT FAILURE.' NRC | | REPORT NO. 32258 IS THEREFORE RETRACTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. THE NRC OPERATIONS CENTER | | NOTIFIED THE R3DO (JORDAN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 05/03/97 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 15:45 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 05/03/97 | +------------------------------------------------+EVENT TIME: 15:04[EDT]| |NRC NOTIFIED BY: NOEL CLARKSON |LAST UPDATE DATE: 05/06/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DICK WESSMAN EO | | |CARR FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO TWO OF THREE HIGH PRESSURE INJECTION PUMPS | | BEING INOPERABLE. | | | | THE LICENSEE SUSPECTS THAT THE LETDOWN STORAGE TANK WATER LEVEL INDICATIONS | | ARE NOT INDICATING PROPER LEVEL. THE LETDOWN STORAGE TANK SUPPLIES WATER | | TO THE SUCTION OF THE THREE HIGH PRESSURE INJECTION (HPI) PUMPS. | | | | PRESENT REACTOR COOLANT SYSTEM (RCS) PARAMETERS: TEMPERATURE IS 210øF AND | | PRESSURE IS 270 PSIG. THE LOW PRESSURE INJECTION PUMPS ARE TAKING SUCTION | | FROM THE RCS AND DISCHARGING BACK TO THE RCS COLD LEG. THE '3B1' REACTOR | | COOLANT PUMP (RCP) IS THE ONLY OPERATING RCP. CONDENSATE BOOSTER PUMPS ARE | | SUPPLYING WATER TO THE ONCE-THROUGH STEAM GENERATORS, AND STEAM IS BEING | | DUMPED TO THE MAIN CONDENSER. | | | | AT 0930, LOW DISCHARGE PRESSURE WAS INDICATED ON THE '3B' HPI PUMP. THE | | RCP SEAL INJECTION CONTROL VALVE WAS PLACED IN 'HAND' (i.e., MANUAL). THE | | STANDBY HPI PUMP ('3A') STARTED AUTOMATICALLY ON LOW RCP SEAL INJECTION | | FLOW. HPI PUMP DISCHARGE PRESSURE RETURNED TO NORMAL, AND RCP SEAL | | INJECTION FLOW INDICATED HIGH. THE '3A' HPI PUMP WAS SECURED. RCP SEAL | | INJECTION WAS ADJUSTED TO A NORMAL VALUE. | | | | HPI HEADER DISCHARGE PRESSURE AGAIN INDICATED LOW. THE '3A' HPI PUMP | | AUTOMATICALLY STARTED, AND AMPS WERE CYCLING HIGH. THE '3B' HPI PUMP AMPS | | INDICATED LOW, AND THE '3B' HPI PUMP WAS SECURED. THE '3A' HPI PUMP AMPS | | CONTINUED TO CYCLE HIGH. THE INDICATED LETDOWN STORAGE TANK LEVEL | | INCREASED. THE '3A' HPI PUMP AMPS INDICATED LOW, AND THE '3A' HPI PUMP WAS | | SECURED. | | | | THE LICENSEE SUSPECTS THAT THE LETDOWN STORAGE TANK LEVEL INDICATIONS ARE | | ERRONEOUS AND IS INVESTIGATING THE CAUSE AND DEVELOPING RECOVERY ACTIONS. | | | | THE NRC RESIDENT INSPECTORS ARE ON SITE. | | | | AT 1350, NRC HEADQUARTERS AND REGION 2 ENTERED THE MONITORING PHASE OF | | NORMAL EMERGENCY RESPONSE MODE. THE NRC RESPONSE COORDINATION TEAM MEMBER | | NOTIFIED FEMA (BAGWELL), DOE (DUNKIN), EPA (HUDSPETH), USDA (BICKERTON), | | AND HHS (RABB). | | | | AT 1504, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO TWO OF THREE HPI | | PUMPS BEING INOPERABLE. THIS SITUATION IS A POTENTIAL DEGRADATION IN THE | | LEVEL OF SAFETY TO UNIT 3. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THE DECLARATION OF THE | | UNUSUAL EVENT. | | | | * * * UPDATE AT 1900 ON 05/03/97, BY MacKINNON * * * | | | | AT 1900 ON 05/03/97, A COMMISSIONERS' ASSISTANTS BRIEFING WAS HELD. THE | | BRIEFER WAS CHUCK CASTO. PARTICIPANTS INCLUDED (* INDICATES OFFICE DID | | NOT PARTICIPATE): AEOD (BAILEY, ROSENTHAL, AND QUISSELL), JACKSON (LEE), | | ROGERS (FLEISHMAN), DICUS (LUBENAU), DIAZ (RADDATZ), McGAFFIGAN (BEALL), | | EDO (TRACY), DEDO (JORDAN), EAB (CHAFFEE AND GOODWIN), NRR EO (WESSMAN), | | R2DO (CASTO), PAO (BEECHER), CAO (KEELING), SECY (*BATES), OSP (*BANGART), | | AND OIP (*HAUBER). | | | | * * * UPDATE AT 1500 ON 05/04/97, BY MacKINNON * * * | | | | AT 1445 ON 05/04/97, NRC HEADQUARTERS AND NRC REGION 2 EXITED THE | | MONITORING PHASE OF NORMAL EMERGENCY RESPONSE MODE AFTER THE LICENSEE | | SUCCESSFULLY RAN THE '3C' HPI PUMP TAKING SUCTION FROM THE BORATED WATER | | STORAGE TANK. THE OPERATIONS OFFICER NOTIFIED THE R2DO (CASTO), IRD | | (BARRETT), FEMA (RISHE), DOE (DUNKIN), EPA (CHECKAN), USDA (BICKERTON), | | AND HHS (GRAY). | | | | AT 1500 ON 05/04/97, A COMMISSIONERS' ASSISTANTS BRIEFING WAS HELD. THE | | BRIEFER WAS CHUCK CASTO. PARTICIPANTS INCLUDED (* INDICATED OFFICE DID | | NOT PARTICIPATE): JACKSON (LEE), ROGERS (SORENSEN), DICUS (LUBENAU), | | DIAZ (RADDATZ), McGAFFIGAN (BEALL), NRR (MIRAGLIA), NRR EO (WESSMAN), | | EAB (CHAFFEE), PAO (BEECHER), OSP (BANGART), NRR PM (LaBARGE), SRI (SCOTT), | | REGION 2 (HOLLAND AND CHRISTENSEN), AEOD (*ROSS AND *BARRETT), OIP | | (*HAUBER), EDO (*TRACY), DEDO (*JORDAN), SECY (*HART), AND CAO (*COMBS). | | | | * * * UPDATE AT 1952 ON 05/05/97, FROM LEGETTE TAKEN BY STRANSKY * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 1946 ON 05/05/97. UNIT 3 IS | | IN MODE 5 (COLD SHUTDOWN), AND THE LOW PRESSURE INJECTION PUMPS ARE CAPABLE | | OF INJECTING TO THE RCS IF NECESSARY. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. THE HOO NOTIFIED THE R2DO (CASTO), NRR EO (WESSMAN), AND FEMA | | (BAGWELL). | | | | * * * UPDATE AT 1856 ON 05/06/97, FROM NIX TAKEN BY STRANSKY * * * | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THIS REPORT PROVIDES SUPPLEMENTARY INFORMATION TO EVENT #32271, REPORTED | | ON 05/03/97, AT 1545. | | | | WHILE SHUTTING OCONEE UNIT 3 DOWN, HPI PUMPS '3A' AND '3B' DID NOT HAVE AN | | ADEQUATE NET POSITIVE SUCTION HEAD (NPSH). THE INADEQUATE NPSH RESULTED | | FROM INACCURATE [LETDOWN STORAGE TANK (LDST)] LEVEL INDICATION. THE LDST | | LEVEL INDICATION CONTAINED A DISCREPANCY OF APPROXIMATELY 54 INCHES BETWEEN | | THE CONTROL ROOM INDICATOR AND THE LDST LEVEL. | | | | AT 1515 ON 05/05/97, AN ENGINEERING EVALUATION OF THE INACCURATE LDST LEVEL | | INDICATION DETERMINED THAT THE OCONEE UNIT 3 HPI SYSTEM WOULD NOT HAVE BEEN | | ABLE TO PERFORM ITS INTENDED SAFETY FUNCTION DURING POWER OPERATING | | CONDITIONS FROM 02/22/97, UNTIL 05/03/97 (WHEN THE UNIT WAS SHUT DOWN). IN | | THE EVENT OF A SMALL BREAK [LOSS OF COOLANT ACCIDENT], THE POTENTIAL | | EXISTED FOR HYDROGEN TO BE DRAWN INTO THE SUCTION OF THE HPI PUMPS AS THE | | [BORATED WATER STORAGE TANK] VOLUME WAS DEPLETED. ADDITIONAL INFORMATION | | WILL BE INCLUDED IN THE LICENSEE EVENT REPORT." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R2DO (CHRISTENSEN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: OVERLOOK HOSPITAL |NOTIFICATION DATE: 05/06/97 | | CITY: SUMMIT REGION: 1 |NOTIFICATION TIME: 09:24 [ET]| | COUNTY: UNION STATE: NJ |EVENT DATE: 05/05/97 | |LICENSE#: 29-03308-01 AGREEMENT: N |EVENT TIME: 10:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM TRAPP RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JAMES DONLAN (RSO) | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PATIENT GIVEN 7 mCi OF IODINE-131 (I-131) INSTEAD OF 2 mCi. | | | | A PATIENT WAS INADVERTENTLY GIVEN 7 mCi OF I-131 INSTEAD OF 2 mCi OF I-131 | | DURING A FOLLOWUP EXAMINATION TO CHECK FOR THYROID CANCER CELLS. THE | | PATIENT'S THYROID WAS SURGICALLY REMOVED IN 1996, AND IN JANUARY OF 1997, | | THE PATIENT WAS GIVEN 134 mCi OF I-131 TO ABLATE THE CANCER CELLS THAT MAY | | HAVE BEEN STILL PRESENT AFTER THE THYROID HAD BEEN REMOVED. | | | | THE PATIENT'S PHYSICIAN REALIZED RIGHT AFTER GIVING THE PATIENT THE 7 mCi | | OF I-131 THAT HE SHOULD HAVE GIVEN THE PATIENT 2 mCi OF I-131. THE | | PHYSICIAN IMMEDIATELY INFORMED THE PATIENT THAT THE INCORRECT DOSE OF I-131 | | WAS GIVEN TO HER. THE EXTRA 5 mCi OF I-131 POSES NO PHYSICAL/MEDICAL | | THREAT TO THE PATIENT. THE RADIATION SAFETY OFFICER SAID THAT THE EXTRA 5 | | mCI OF I-131 WOULD HAVE MADE IT EASIER TO SEE ANY CANCEROUS CELLS THAT HAD | | NOT BEEN ABLATED IN JANUARY OF 1997. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY (ROCK ISLAND, ILLINOIS) |NOTIFICATION DATE: 05/06/97 | | CITY: ROCK ISLAND REGION: 3 |NOTIFICATION TIME: 09:33 [ET]| | COUNTY: STATE: IL |EVENT DATE: 05/05/97 | |LICENSE#: 12-00722-06 AGREEMENT: Y |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MICHAEL J. JORDAN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TIM MHOS | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -MUZZLE REFERENCE SENSOR WITH A 10-CURIE TRITIUM SOURCE FOUND IN A LANDFILL | | | | ON 05/01/97, A REPRESENTATIVE FROM THE SAVANNAH LANDFILL REPORTED THE | | DISCOVERY OF A "MILITARY SMOKE DETECTOR" AT THE LANDFILL TO A | | REPRESENTATIVE OF THE HUNTER ARMY AIR FIELD, GA, WHO REPORTED IT TO THE | | RADIATION PROTECTION OFFICER (RPO) AT FT. STEWART, GA. | | | | ON 05/02/97, THE FT. STEWART RPO HAD THE 'ITEM' RECOVERED FROM THE | | LANDFILL. THE 'ITEM' TURNED OUT TO BE AN ARMY TANK GUN MUZZLE REFERENCE | | SENSOR (MRS) 3 INCHES IN DIAMETER BY 8 INCHES LONG CONTAINING A RADIOACTIVE | | SOURCE OF 10 CURIES OF TRITIUM GAS. THE MRS AND ITS SOURCE ARE UNDAMAGED. | | THE MRS WAS DOUBLE BAGGED AT THE LANDFILL AND TRANSPORTED TO FT. STEWART. | | THE MRS IS NOW IN A CONTROLLED AREA AT FT. STEWART. | | | | ON 05/05/97, WIPES OF THE MRS WERE TAKEN AND SENT TO AN OFFSITE LAB FOR | | ANALYSIS. | | | | FT. STEWART PERSONNEL ARE INVESTIGATING HOW THE MRS ENDED UP AT THE | | LANDFILL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32282 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/06/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 13:13 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 09:02[CDT]| |NRC NOTIFIED BY: KELLY |LAST UPDATE DATE: 05/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TAPIA RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 99 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DUE TO LOSS OF FEEDWATER FLOW | | | | AT 0902 CDT, OPERATORS MANUALLY SCRAMMED THE PLANT AFTER TWO OF THE THREE | | REACTOR FEEDWATER PUMPS TRIPPED. ALL CONTROL RODS INSERTED, AND ALL SYSTEMS | | FUNCTIONED AS EXPECTED FOLLOWING THE SCRAM. THE UNIT IS CURRENTLY STABLE IN | | MODE 3. | | | | THE LICENSEE REPORTED THAT THREE NON-VITAL AC BUSSES (NPS-1B, NNS-1B, AND | | NNS-1C) AND VITAL AC BUS (ENS-1B) WERE LOST FOR AN AS YET UNKNOWN REASON. | | WHEN POWER WAS LOST, TWO OF THE THREE OPERATING FEEDWATER PUMPS TRIPPED. | | OPERATORS RESPONDED TO THE EVENT, AND MANUALLY SCRAMMED THE PLANT IN | | ANTICIPATION OF AN AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR VESSEL WATER | | LEVEL. REACTOR PROTECTION SYSTEM BUS 'B' WAS DEENERGIZED DUE TO THE LOSS OF | | VITAL AC BUS ENS-1B. THIS RESULTED IN A DIVISION 2 BALANCE OF PLANT | | ISOLATION. THE DIVISION 2 AND 3 EMERGENCY DIESEL GENERATORS AUTOMATICALLY | | STARTED DUE TO THE LOSS OF POWER. AT 1141 CDT, AN INBOARD MAIN STEAM LINE | | ISOLATION OCCURRED DUE TO A HIGH TEMPERATURE IN THE STEAM TUNNEL. THE | | LICENSEE REPORTED THAT THE CHILL WATER SYSTEM TO THE TURBINE BUILDING WAS | | ALSO LOST AS A RESULT OF THE POWER LOSS. | | | | THE LICENSEE PLANS TO CONTACT THE STATE OF LOUISIANA DUE TO OVERFLOW IN THE | | CIRCULATING WATER BASIN CAUSED BY THE LOSS OF TWO CIRCULATING WATER PUMPS. | | THE LICENSEE ALSO PLANS TO MAKE A DRYWELL ENTRY TO IDENTIFY A PREVIOUSLY | | EXISTING SOURCE OF UNIDENTIFIED LEAKAGE. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/06/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:37 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 13:25[EDT]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 05/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TRAPP 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 +------------------------------------------------------------------------------+ | FAN COOLER UNIT VALVES AUTOMATICALLY REALIGNED TO INCIDENT MODE | | | | WHILE TESTING THE PLACEMENT OF A JUMPER ON THE INSTRUMENT AIR SYSTEM IN | | PREPARATION FOR PERFORMANCE OF A SURVEILLANCE TEST, VALVES FOR THE FIVE FAN | | COOLER UNITS AUTOMATICALLY SWAPPED INTO INCIDENT MODE. FOUR OF THE FAN | | COOLERS ARE CURRENTLY SHUT DOWN, AND THE SERVICE WATER SUPPLY TO ALL FAN | | COOLERS IS CLOSED OFF DUE TO THE OUTAGE. AFTER CONFIRMING THE CAUSE OF THE | | REALIGNMENT, TECHNICIANS RESUPPLIED INSTRUMENT AIR TO THE VALVES RETURNING | | THEM TO THEIR INITIAL POSITIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32284 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 05/06/97 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 19:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 16:45[PDT]| |NRC NOTIFIED BY: HIETT |LAST UPDATE DATE: 05/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TAPIA RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GREATER THAN 1% OF INSPECTED STEAM GENERATOR TUBES HAVE DEFECTS. | | | | ON MAY 6, 1997, DURING THE EIGHTH UNIT 1 REFUELING OUTAGE, ANALYSIS OF EDDY | | CURRENT DATA ON STEAM GENERATOR (SG) 1-2 INDICATED THAT GREATER THAN ONE | | PERCENT OF THE TOTAL TUBES INSPECTED IN SG 1-2 WERE DEFECTIVE. SIXTY-THREE | | PLUGGABLE TUBES IN SG 1-2 HAVE BEEN IDENTIFIED TO DATE. MOST OF THE | | PLUGGABLE INDICATIONS ARE DUE TO PRIMARY WATER STRESS CORROSION CRACKING AT | | DENTED TUBE SUPPORT PLATE INTERSECTIONS. EDDY CURRENT INSPECTIONS ARE STILL | | IN PROGRESS. RESULTS OF THE STEAM GENERATOR TUBE INSPECTIONS FALL INTO | | CATEGORY C-3, WHICH REQUIRES A 4-HOUR NON-EMERGENCY REPORT IN ACCORDANCE | | WITH TECHNICAL SPECIFICATION (TS) TABLE 4.4-2 AND 10CFR50.72(b)(2)(iii)(C), | | A 30-DAY SPECIAL REPORT IN ACCORDANCE WITH TS 4.4.5.5c, AND A 30-DAY | | LICENSEE EVENT REPORT IN ACCORDANCE WITH 10CFR50.73(a)(2)(v)(C). | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32285 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/06/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 20:24 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: WISNIEWSKI |LAST UPDATE DATE: 05/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TRAPP RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR INADEQUATE RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM FLOW | | DUE TO INSTRUMENT UNCERTAINTIES | | | | A POTENTIAL EXISTS FOR INADEQUATE SYSTEM FLOW THROUGH THE RESIDUAL HEAT | | REMOVAL SERVICE WATER (RHRSW) SYSTEM DUE TO THE LICENSEE'S FAILURE TO | | ACCOUNT FOR INSTRUMENT UNCERTAINTIES IN PLANT PROCEDURES. THE FINAL SAFETY | | ANALYSIS REPORT ASSUMES AN RHRSW HEAT EXCHANGER DESIGN FLOW RATE OF 2,700 | | GPM WITH NO TOLERANCE. PLANT PROCEDURE OP-2124 INSTRUCTS OPERATORS TO LIMIT | | RHRSW SYSTEM FLOW TO A MAXIMUM OF 2,700 GPM. HOWEVER, A LICENSEE REVIEW HAS | | DETERMINED THAT THE 2,700-GPM MAXIMUM FLOW VALUE USED IN THE PROCEDURE DOES | | NOT TAKE INTO ACCOUNT THE RHRSW FLOW INSTRUMENT UNCERTAINTY OF ñ200 GPM. | | | | THE LICENSEE HAS DETERMINED THAT THE CURRENT PROCEDURE IS ADEQUATE AS LONG | | AS THE RIVER TEMPERATURE REMAINS BELOW 70øF. A DETAILED ENGINEERING | | ANALYSIS WILL BE PERFORMED, AND A BASIS FOR MAINTAINING OPERATION WILL BE | | PREPARED FOR THIS ISSUE TO SUPPORT THE CURRENT PLANT STARTUP. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32286 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/06/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 21:05 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 16:30[CDT]| |NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 05/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TAPIA 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNISOLABLE LEAK FOUND ON REACTOR RECIRCULATION SYSTEM. | | | | DURING A DRYWELL ENTRY MADE TO IDENTIFY THE SOURCE OF LEAKAGE INSIDE THE | | CONTAINMENT, THE LICENSEE DISCOVERED A CRACKED WELD ON A VENT VALVE FOR THE | | 'B' REACTOR RECIRCULATION FLOW CONTROL VALVE (FCV). THE CRACK IS LOCATED AT | | THE POINT WHERE THE HIGH POINT VENT VALVE ATTACHES TO A PIECE OF 3/4" | | PIPING AT THE TOP OF THE FCV. THE LICENSEE CONSIDERS THIS LEAK TO BE | | UNISOLABLE DUE TO EXCESSIVE LEAKAGE PAST THE 20" DIAMETER ISOLATION VALVES | | FOR THE 'B' RECIRCULATION LOOP. THE LICENSEE REPORTED THAT TOTAL | | UNIDENTIFIED DRYWELL LEAKAGE IS CURRENTLY 2 GPM. THE LICENSEE INTENDS TO | | REPAIR THE WELD BEFORE UNIT STARTUP. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32287 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR RADIOPHARMACEUTICALS |NOTIFICATION DATE: 05/06/97 | | CITY: ST. LOUIS REGION: 3 |NOTIFICATION TIME: 21:12 [ET]| | COUNTY: STATE: MO |EVENT DATE: 05/06/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 15:30[CDT]| | DOCKET: |LAST UPDATE DATE: 05/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JORDAN R3 RDO | | | | +------------------------------------------------+TAPIA R4 RDO | |NRC NOTIFIED BY: D. PELLICCIARINI | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |FFFF 20.402 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PACKAGE RECEIVED WITH EXCESSIVE LOOSE EXTERNAL CONTAMINATION. | | | | A SYNCOR DRIVER FROM THE ST. LOUIS, MO, RADIOPHARMACY PICKED UP AN AMMO BOX | | (CONTAINER USED TO TRANSPORT RADIOPHARMACEUTICALS) FROM THE BARNES HOSPITAL | | IN ST. LOUIS FOR RETURN TO THE SYNCOR FACILITY. UPON THE DRIVER'S RETURN TO | | THE SYNCOR FACILITY, THE LICENSEE DETECTED REMOVABLE CONTAMINATION ON THE | | OUTSIDE OF THE AMMO BOX OF 1,400,000 DPM. THE RADIOACTIVE MATERIAL WAS | | DETERMINED TO BE Tc-99m. THE DRIVER WAS CHECKED, AND CONTAMINATION WAS | | DETECTED ON HIS HANDS AND CLOTHING. THE INDIVIDUAL WAS DECONTAMINATED, AND | | HIS PANTS WERE REMOVED FOR RADIONUCLIDE DECAY. SOME CONTAMINATION WAS | | DETECTED THROUGHOUT THE SYNCOR FACILITY (PRIMARILY DOORKNOBS), AND IT WAS | | REMOVED. THE DELIVERY VEHICLE WAS ALSO CONTAMINATED (PRIMARILY THE STEERING | | WHEEL), BUT THE CALLER DID NOT KNOW WHETHER THE VEHICLE WOULD BE | | DECONTAMINATED OR ISOLATED UNTIL THE RADIONUCLIDE HAS DECAYED. | | | | THE LICENSEE HAS HAD SOME DIFFICULTY IN CONTACTING THE HOSPITAL BECAUSE OF | | THE TIME OF DAY; HOWEVER, DETAILS OF THIS EVENT HAVE BEEN PROVIDED TO THE | | TECHNICIAN ON CALL IN THE NUCLEAR PHARMACY. THE LICENSEE PLANS TO CONTACT | | NRC REGIONS 3 AND 4 TOMORROW MORNING. (THE SYNCOR LICENSE IS HELD BY THE | | CORPORATE OFFICE IN LOS ANGELES, CA.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32288 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 00:13 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 23:00[CDT]| |NRC NOTIFIED BY: STEVE GORTON |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED INOPERABLE | | (BUT AVAILABLE) DUE TO A 250-VOLT DC MOTOR CONTROL CENTER UNDERVOLTAGE | | ALARM FOR UNKNOWN REASONS. | | | | THE RCIC 250-VOLT DC MOTOR CONTROL CENTER UNDERVOLTAGE ALARM WAS RECEIVED | | IN THE CONTROL ROOM AT 2205 CDT. UPON INVESTIGATION, NO READILY APPARENT | | CAUSE WAS FOUND. WITH NO UNDERVOLTAGE ALARM AVAILABLE, FOUR 250-VOLT DC | | BREAKERS ARE AFFECTED. AS A RESULT, THE LICENSEE DECLARED THE RCIC SYSTEM | | INOPERABLE (BUT AVAILABLE) AT 2300 CDT, AND A 14-DAY LIMITING CONDITION FOR | | OPERATION WAS ENTERED. THE LICENSEE'S INVESTIGATION IS CURRENTLY ONGOING. | | ALL EMERGENCY CORE COOLING SYSTEMS ARE CURRENTLY OPERABLE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32289 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 03:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 22:48[CDT]| |NRC NOTIFIED BY: JOHN MYERS |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO AUTOMATIC SCRAMS WITH NO ROD MOTION; GROUP 2, 3, AND 6 ISOLATIONS; AND | | TEMPORARY LOSS OF SHUTDOWN COOLING DUE TO A FALSE INDICATION OF LOW WATER | | LEVEL | | | | AT 2248 CDT ON MAY 6, 1997, A FULL SCRAM AND GROUP 2 (SHUTDOWN COOLING AND | | DRYWELL), 3 (REACTOR WATER CLEANUP), AND 6 (SECONDARY CONTAINMENT AND | | STANDBY GAS TREATMENT) ISOLATIONS OCCURRED DUE TO AN APPARENT LOW WATER | | LEVEL SIGNAL. AT THE TIME, THE PLANT WAS SHUTDOWN FOR A REFUELING OUTAGE | | WHICH BEGAN ON MARCH 29, 1997 (39 DAYS AGO). THERE WAS NO CONTROL ROD | | MOVEMENT BECAUSE THE CONTROL RODS WERE ALREADY INSERTED. THE GROUP 2 | | ISOLATION RESULTED IN THE LOSS OF SHUTDOWN COOLING. REACTOR WATER | | TEMPERATURE AT THE TIME OF THE EVENT WAS 104øF WITH A CONSERVATIVE | | ESTIMATED TIME TO BOILING OF 7 HOURS PER THE LOSS OF SHUTDOWN COOLING | | PROCEDURE. THE REACTOR VESSEL WAS RE-ASSEMBLED WITH THE HEAD INSTALLED AND | | TENSIONED. WATER LEVEL AT THE TIME OF THE EVENT WAS APPROXIMATELY 185 | | INCHES (BETWEEN THE MAIN STEAM LINES AND THE VESSEL FLANGE). | | | | THE SCRAM INSTRUMENTS WERE RETURNED TO SERVICE AT 0041 CDT ON MAY 7, 1997, | | AND THE GROUP 2 ISOLATION WAS RESET AT 0109 CDT. REACTOR WATER TEMPERATURE | | WAS 123øF AT THE TIME SHUTDOWN COOLING WAS RESTORED TO SERVICE INDICATING A | | HEATUP RATE OF 6øF PER HOUR. | | | | THE LICENSEE BELIEVES THAT THE LOW WATER LEVEL SIGNAL WAS THE APPARENT | | RESULT OF AIR INTRODUCED INTO THE LEVEL INSTRUMENT VARIABLE LEG BY THE AIR | | LOADING ON THE FLOODUP INSTRUMENT. THE AIR LOADING ALLOWS INSTALLED LEVEL | | INDICATION TO BE USED FOR FLOODUP FOR REFUELING. AT THE TIME OF THE EVENT, | | INSTRUMENTATION AND CONTROL (I&C) PERSONNEL WERE BACKFILLING THE REFERENCE | | LEG AS PART OF THE PROCESS OF REMOVING THE AIR LOADING DURING DRAIN DOWN OF | | THE REACTOR VESSEL. THE PROCESS USED FOR THE BACKFILLING ALLOWED AIR TO BE | | DISPERSED THROUGH THE LEVEL INSTRUMENTS RESULTING IN A FALSE INDICATION OF | | LOW LEVEL. I&C PERSONNEL HAVE FLUSHED THE INSTRUMENT LEGS TO REMOVE THE | | ENTRAINED AIR AND RESTORE THE INSTRUMENTS TO SERVICE. DURING THIS FLUSHING | | PROCESS, A SECOND REACTOR SCRAM OCCURRED AT 0051 CDT ON MAY 7, 1997 (PRIOR | | TO THE RESTORATION OF SHUTDOWN COOLING). | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+