U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/04/98 - 03/05/98 ** EVENT NUMBERS ** 33545 33650 33663 33825 33826 33827 33828 33829 33830 33831 33832 33833 33834 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33545 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 16:25[EST]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR WATER HAMMER IN HPCI OR RCIC TURBINE EXHAUST LINES DURING | | OPERATION WITH ELEVATED SUPPRESSION POOL PRESSURE | | | | THE LICENSEE HAS DETERMINED THAT ELEVATED PRESSURE (>5 PSIG) WITHIN THE | | SUPPRESSION POOL COULD PERMIT WATER TO BE DRAWN INTO THE HIGH PRESSURE | | COOLANT INJECTION (HPCI) OR REACTOR CORE ISOLATION COOLING (RCIC) EXHAUST | | LINES FOLLOWING SYSTEM OPERATION. FOR EXAMPLE, FOLLOWING A REACTOR SCRAM, | | WITH TURBINE EXHAUST PRESSURE INITIALLY GREATER THAN SUPPRESSION POOL | | PRESSURE, AND SUPPRESSION POOL PRESSURE GREATER THAN REACTOR BUILDING | | PRESSURE, AS EXHAUST LINE PRESSURE DECREASES BELOW SUPPRESSION POOL | | PRESSURE, WATER WILL BE FORCED INTO THE EXHAUST LINE BY SUPPRESSION POOL | | OVERPRESSURE. THE VACUUM RELIEF VALVES TO THE REACTOR BUILDING WILL REMAIN | | CLOSED UNTIL EXHAUST LINE PRESSURE DECREASES BELOW REACTOR BUILDING | | PRESSURE. OPERATION OF EITHER SYSTEM WHILE IN THIS CONDITION COULD LEAD TO | | WATER HAMMER AND POSSIBLE DAMAGE TO COMPONENTS SUCH AS CHECK VALVES AND | | RUPTURE DISKS. SUCH FAILURES COULD CHALLENGE FURTHER HPCI OR RCIC OPERATION | | AND CONTAINMENT INTEGRITY. | | | | IN 1973, VACUUM BREAKERS WERE INSTALLED ONTO THE HPCI AND RCIC TURBINE | | EXHAUST LINES AFTER THE HPCI TURBINE EXHAUST LINE EXPERIENCED SEVERE | | VIBRATION CAUSED BY STEAM CONDENSING IN THE EXHAUST LINE AND DRAWING COLD | | WATER INTO THE HOT PIPING. THE VACUUM BREAKERS WERE INITIALLY INSTALLED ON | | PIPING INSIDE OF THE SUPPRESSION POOL, BUT WERE RELOCATED TO PIPING OUTSIDE | | OF THE SUPPRESSION POOL DUE TO CONCERNS REGARDING CONTAINMENT LEAKAGE | | TESTING. THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | * * * 3/4/97 1113 RETRACTION FROM WISNIEWSKI TAKEN BY STRANSKY * * * | | | | AS A RESULT OF AN ENGINEERING EVALUATION, THE LICENSEE HAS DETERMINED THAT | | PIPING STRESSES WILL REMAIN WITHIN ACCEPTABLE LIMITS. THEREFORE, BOTH THE | | HPCI AND RCIC SYSTEMS REMAIN OPERABLE. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED BY THE LICENSEE. NOTIFIED R1DO (BELLAMY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33650 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/04/98 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 13:50 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/04/98 | +------------------------------------------------+EVENT TIME: 13:50[EST]| |NRC NOTIFIED BY: KENNO LAMPMAN |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERN HODGE (PCEB) NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21: LOCKUP OF WESTRONICS RECORDERS DUE TO SERVO AMPLIFIER | | BOARD OVERRANGE FEATURE - THIS PROBLEM WAS CORRECTED IN THE FALL OF 1997. | | | | DESCRIPTION OF CONDITION: | | | | THE DEVIATION DESCRIBED IN THE REFERENCED DEVIATION EVENT REPORTS (DER) | | AFFECTS THE FIVE SAFETY-RELATED (SR) RECORDERS. RECORDERS 2ISC*LR1623A/B | | AND 2ISC*PR1623A/B WERE SUPPLIED TO GENERAL ELECTRIC (GE) BY WESTRONICS AS | | NON-SAFETY-RELATED INSTRUMENTS (NSR) AND WERE UPGRADED TO SR BY GE | | (PURCHASE ORDER/SPEC. P800A). FUEL ZONE LEVEL RECORDER 2ISC*LR1615 WAS | | SUPPLIED AS SR EQUIPMENT AND IS FED FROM TRANSMITTER 2ISC*LT13B. THE WIDE | | RANGE LEVEL RECORDERS 2ISC*LR1623A/B ARE FED FROM TRANSMITTERS 2ISC*LT9A/B. | | THE LATTER RECORDERS EACH ALSO DISPLAY VESSEL PRESSURE ON A SECOND CHANNEL | | AND PEN. THE PRESSURE CHANNELS 2ISC*PR1623A/B ARE FED FROM PRESSURE | | TRANSMITTERS 2ISC*PT16A/B. ALL OF THE AFFECTED RECORDERS ARE ON MAIN | | CONTROL ROOM PANEL 2CEC*PNL601. ALL OF THESE RECORDERS ARE SR TECHNICAL | | SPECIFICATIONS POST-ACCIDENT MONITORING INSTRUMENTS. THEY ARE IDENTIFIED | | ON THE NMP2 MASTER EQUIPMENT LIST AS REGULATORY GUIDE 1.97 MONITORING | | EQUIPMENT. ALL OF THE ABOVE MENTIONED RECORDERS WERE INSTALLED WHEN THE | | PLANT WAS INITIALLY LICENSED. | | | | DERs 2-97-1662 AND 2-97-3030 DESCRIBE FAILURES OF THE AFFECTED VESSEL | | PRESSURE AND LEVEL RECORDERS LISTED ABOVE SUCH THAT THE AFFECTED RECORDER | | CHANNEL LOCKS UP TEMPORARILY UNDER CONDITIONS WHERE THEY EXPERIENCE A LARGE | | STEP CHANGE IN THE PROCESS VARIABLE MONITORED OR WHEN THE RECORDERS HAVE | | THE PEN MANUALLY MOVED FROM THE POSITION TO WHICH IT WAS DRIVEN BY THE | | SERVO AMPLIFIER BOARD (WESTRONICS PART NUMBER CB100124N04). | | | | ALL OF THE POTENTIALLY AFFECTED RECORDERS NOW ARE (AS OF THE FALL OF 1997) | | NOW EQUIPPED WITH THE NEWER SERVO AMPLIFIER BOARDS. THESE BOARDS HAVE AN | | INHERENT TIME DELAY THAT ALLOWS THE BOARD TO FUNCTION UNDER TRANSIENT | | CONDITIONS WITHOUT LOCKING UP. THERE HAVE BEEN NO FURTHER FAILURES (OF THE | | TYPE DESCRIBED) EXPERIENCED SINCE THE INSTALLATION OF THE NEW BOARDS. | | THEREFORE, NO FURTHER MAINTENANCE ACTION IS REQUIRED WITH RESPECT TO THESE | | RECORDERS. | | | | PROCUREMENT PERSONNEL HAVE VERIFIED THAT NONE OF THE OLDER MODEL BOARDS ARE | | BEING UTILIZED AT NINE MILE POINT UNIT 1 OR ARE BEING MAINTAINED AS SPARES. | | | | ***RETRACTION ON 03/04/98 @ 1500 EST BY LAMPMAN TAKEN BY MACKINNON*** | | | | NIAGARA MOHAWK POWER CORPORATION (NMPC) HAS CONCLUDED, BASED UPON FURTHER | | INVESTIGATION AND TESTING OF THE EARLIER AND LATER REVISIONS OF THE SUBJECT | | SERVO AMPLIFIER BOARDS, (1) THAT MISOPERATION OF THE OVER-RANGE SHUTDOWN | | CIRCUIT WAS NOT RESPONSIBLE FOR THE ANOMALY IDENTIFIED IN THE ABOVE | | NOTIFICATION, AND (2) THAT THE CRITERIA FOR REPORTABILITY UNDER 10 CFR 21 | | WERE THEREFORE NOT MET. R1DO (RON BELLAMY) AND NRR PCEB (VERN HODGE) WERE | | NOTIFIED. | | | | NMPC HEREBY RETRACTS ITS FEBRUARY 4, 1998, NOTIFICATION OF A PART 21 | | REPORTABLE CONDITION INVOLVING THE SUBJECT CIRCUIT BOARDS. | | | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33663 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/05/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 17:40 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/05/98 | +------------------------------------------------+EVENT TIME: 17:23[EST]| |NRC NOTIFIED BY: WILL HOFFNER |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS VULNERABILITY DISCOVERED | | | | THE LICENSEE DISCOVERED A VULNERABILITY IN THEIR SAFEGUARDS SYSTEM FOR | | UNITS 2 & 3 WHICH COULD HAVE ALLOWED UNAUTHORIZED OR UNDETECTED ACCESS INTO | | VITAL AREAS. COMPENSATORY MEASURES HAVE BEEN IMPLEMENTED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE. | | | | * * * 1130EST 3/4/98 FROM PATRICK ANHALT TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT AFTER CONCLUDING THAT A SAFEGUARDS | | VULNERABILITY WAS NOT POSSIBLE. THE LICENSEE INFORMED THE REGION 1 | | SAFEGUARDS INSPECTOR AND WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | R1DO(BELLAMY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 33825 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST. BARNABAS |NOTIFICATION DATE: 03/04/98 | | CITY: LIVINGSTON REGION: 1 |NOTIFICATION TIME: 09:30 [ET]| | COUNTY: ESSEX STATE: NJ |EVENT DATE: 10/29/97 | |LICENSE#: 29-0160803 AGREEMENT: N |EVENT TIME: 08:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/04/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RONALD BELLAMY RDO | | |DON COOL EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DR. DAVID STERDLEY | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN NRC REGION 1 INSPECTOR DURING A ROUTINE INSPECTION AT THE ST. BARNABAS | | HOSPITAL LOCATED IN LIVINGSTON, NJ., LAST WEEK IDENTIFIED A MEDICAL | | MISADMINISTRATION DURING A REVIEW OF THE FACILITIES RADIATION SAFETY | | COMMITTEE'S MINUTES. | | | | ON 10/28/97 AN ELDERLY FEMALE PATIENT UNDERGOING TREATMENT FOR CERVICAL | | CANCER HAD A TANDEM APPARATUS CONTAINING A 25mGRAM RADIUM EQUIVALENT OF | | Cs-137 INSERTED AT 1300 HOURS. BETWEEN 0730 AND 0800 HOURS THE FOLLOWING | | MORNING THE PATIENT WAS CHECKED AND THE APPARATUS WAS APPARENTLY STILL IN | | PLACE. AT APPROXIMATELY 0830 HOURS A NURSE ENTERED THE ROOM AND FOUND THE | | PATIENT STANDING WITH THE TANDEM APPARATUS IN HER HAND. THE NURSE | | INSTRUCTED THE PATIENT TO DROP THE SOURCE AND RETURN TO BED. THE PATIENT | | RETURNED TO BED STILL HOLDING THE SOURCE SEVERAL ADDITIONAL MINUTES BEFORE | | RELEASING IT. HOSPITAL PERSONNEL WERE SUMMONED TO ASSESS THE SITUATION AND | | THE TANDEM APPARATUS WAS REINSERTED IN ORDER TO COMPLETE THE 50 HOUR | | SCHEDULED EXPOSURE. | | | | DURING THE ESTIMATED 30-60 MINUTES THAT THE PATIENT HELD THE SOURCE, SHE | | COULD HAVE POTENTIALLY RECEIVED AN ESTIMATED DOSE OF 300-500 MREM TO THE | | HAND. THE RADIATION SAFETY COMMITTEE CONCLUDED THAT THIS WAS NOT A MEDICAL | | MISADMINISTRATION IN THAT DURING THE PLANNED 50 HOUR EXPOSURE WITH THE | | SOURCE IN PLACE THE HANDS AT THE PATIENT'S SIDE WOULD NORMALLY RECEIVE A | | DOSE OF 4000 MREM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33826 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 03/04/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 14:36 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/05/96 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: WILSON |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HIGH DRYWELL PRESSURE INSTRUMENTS LOG READINGS WERE NOT TAKEN FROM OCTOBER | | 5-10, 1996, AS REQUIRED BY TECH SPECS. | | | | TECHNICAL SPECIFICATION 3.4.B.1 REQUIRES ADS TO BE OPERABLE WHEN | | TEMPERATURE IS GREATER THAN 212 DEGREES F AND REACTOR PRESSURE IS GREATER | | THAN 110 psig. THESE CONDITIONS EXISTED DURING THE NSSS LEAK TEST DURING | | THE PERIOD OF OCTOBER 5 - OCTOBER 10, 1996. TECHNICAL SPECIFICATION TABLE | | 3.1.1, ITEM G1 REQUIRES HIGH DRYWELL PRESSURE INSTRUMENTS TO BE OPERABLE. | | TECHNICAL SPECIFICATION 4.1.1, ITEM 9 REQUIRES THE HIGH DRYWELL PRESSURE | | INSTRUMENTS TO BE CHANNEL CHECKED ONCE PER DAY. THIS CHANNEL CHECK IS | | ACCOMPLISHED BY A TECHNICAL SPECIFICATION INSTRUMENT LOG READING. THE | | REQUIRED LOG READING WERE NOT PERFORMED. THIS IS A VIOLATION OF SECTION 2 | | (C) OF THE OPERATING LICENSE. THIS EVENT NOTIFICATION WILL BE FOLLOWED UP | | WITH AN LER. CORRECTIVE ACTIONS ARE BEING LOOKED INTO. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33827 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SEYMOUR JOHNSON AIR FORCE BASE |NOTIFICATION DATE: 03/04/98 | | CITY: GOLDSBORO REGION: 2 |NOTIFICATION TIME: 15:42 [ET]| | COUNTY: WAYNE STATE: NC |EVENT DATE: 02/04/98 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/04/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | |FRED COMBS EO | +------------------------------------------------+AL BELISLE REG2 | |NRC NOTIFIED BY: MAJOR HICKS |RICH BARRETT IRD | |HQ OPS OFFICER: JOHN MacKINNON |FEMA, DOE, DOA, HHS FAX | +------------------------------------------------+EPA, DOT (NRC) FAX | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAD2 20.2202(a)(2) EXCESSIVE RELEASE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO CIVILIAN WORKERS MAY HAVE BEEN EXPOSED TO TRITIUM FROM A DAMAGED EXIT | | SIGN. | | | | THIS EVENT WAS REPORTED BY THE USAF RADIOISOTOPE COMMITTEE. | | | | TWO CIVILIAN WORKERS WERE SENT BY CIVIL ENGINEERING TO REMOVE "EXIT SIGNS" | | FROM A CONDEMNED BUILDING. IT WAS DISCOVERED THAT ONE OF THE EXIT SIGNS | | THAT THEY WERE SUPPOSED TO REMOVE HAD BEEN TAMPERED WITH AND THE VIALS | | (CONTAINING TRITIUM) HAD BEEN REMOVED. THE LABEL ON THE SIGN STATED | | "RADIOACTIVE". THE EXIT SIGN WAS MADE BY SAFETY LIGHT CORPORATION. THE EXIT | | SIGN (MODEL # 2040 AND SERIAL # D65748) ORIGINALLY CONTAINED 15 CURIES OF | | TRITIUM. THERE WAS SOME BROKEN GLASS INSIDE THE SIGN AND THE WORKERS WERE | | NOT SURE IF THEY HADN'T BROKEN A VIAL. THE WORKERS WERE FRISKED WITH A | | ADM-300 METER WITH A BETA PROBE (IT WAS LEARNED LATER THAT THIS METER WILL | | NOT GIVE A PROPER READING FOR BETA PARTICLES EMITTED FROM TRITIUM). SWIPES | | WERE TAKEN AND THE SWIPES WERE SENT OUT FOR ANALYSIS (ANALYSIS OF SWIPES | | UNKNOWN). THE EXIT SIGN APPEARED TO BE OLD. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33828 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/04/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:54 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/04/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/04/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |RON GARDNER RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+RICH BARRETT IRD | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF ONE (1) CONTROL ON ENRICHMENT | | | | NRC BULLETIN 91-01 4 HOUR NOTIFICATION | | | | IT WAS DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) | | REQUIREMENT WAS NOT BEING MAINTAINED IN THE X-334A VAULT. | | NCSA-0344A005.A02, PART B, REQUIREMENT # 1 STATES: "THE MAXIMUM ENRICHMENT | | PERMITTED IN THE VAULT AND THE OLD HIGH ASSAY SAMPLING AREA (HASA) ROOM IS | | TEN (10) WEIGHT PERCENT URANIUM-235." AN EMPTY FIVE INCH CYLINDER | | (#5B5N0030) CONTAINING 2 GRAMS OF URANIUM-235 HEEL AT 19.91% VIOLATED THIS | | REQUIREMENT. THIS VIOLATION OF ENRICHMENT CONSTITUTES A LOSS OF ONE CONTROL | | (CONTROL "B") IN THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY EVENT 4a. | | CONTROL "A" (INTERACTION/SPACING) WAS MAINTAINED THROUGHOUT THIS EVENT. THE | | DEFICIENCY (LOSS OF CONTROL "B") WAS IMMEDIATELY CORRECTED BY MOVING | | "5B5N0030" CYLINDER TO AN APPROVED STORAGE AREA (DOE BUILDING X-345). | | | | ON JULY 1, 1997 AT 1300 HOURS, PROBLEM REPORT # PR-PRT-97-6074 WAS WRITTEN | | IDENTIFYING A URANIUM ACCOUNTABILITY CONCERN ON CYLINDER # 5B5N0030. IT WAS | | NOT RECOGNIZED THAT A NCSA REQUIREMENT WAS VIOLATED IN THE X-334A VAULT AT | | THAT TIME. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33829 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NC STATE DIVISION OF RAD PROTECTION |NOTIFICATION DATE: 03/04/98 | | CITY: GREENSBORO REGION: 2 |NOTIFICATION TIME: 16:41 [ET]| | COUNTY: STATE: NC |EVENT DATE: 03/04/98 | |LICENSE#: 041-0021-1 AGREEMENT: Y |EVENT TIME: 13:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/04/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |AL BELISLE RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+RICH BARRETT IRD | |NRC NOTIFIED BY: MARION EADDY |JOSE PICCONE, NMSS EO | |HQ OPS OFFICER: JOHN MacKINNON |FEMA, DOE, DOA, HHS FAX | +------------------------------------------------+EPA, DOT (NRC) FAX | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 19 CESIUM-137 BRACHYTHERAPY SOURCES MISSING | | | | THE FOLLOWING INFORMATION WAS PROVIDED BY THE NORTH CAROLINA DIVISION OF | | RADIATION PROTECTION: | | | | THE NORTH CAROLINA DIVISION OF RADIATION PROTECTION WAS NOTIFIED ON | | 03/04/98 AT 1500 HOURS THAT 19 CESIUM-137 BRACHYTHERAPY SOURCES RANGING | | FROM 12 MILLICURIES TO 60 MILLICURIES WERE MISSING FROM A HOSPITAL LOCATED | | IN THE GREENSBORO AREA. THE TOTAL ACTIVITY OF THE 19 MISSING SOURCES IS | | 603.6 MILLICURIES. THEY WERE DISCOVERED MISSING ON 03/04/98 DURING A | | QUARTERLY INVENTORY PHYSICAL CHECK. THE SAFE WAS OPENED AND THE SOURCES | | WERE MISSING. THE LAST TIME THAT THE SOURCES WERE SEEN WAS WHEN A LEAK TEST | | OF THE SOURCES WAS PERFORMED IN LATE DECEMBER 1997. THE HOSPITAL DID NOT | | HAVE ANY PATIENTS NEEDING BRACHYTHERAPY SINCE DECEMBER SO THE SOURCES | | SHOULD NOT HAVE BEEN REMOVED FROM THE SAFE. THE STATE OF NORTH CAROLINA IS | | STILL GATHERING INFORMATION ON THIS EVENT. THE LICENSEE NOTIFIED THE | | HOSPITAL'S SECURITY AND THEY ARE ACTIVELY LOOKING FOR THE 19 MISSING | | CESIUM-137 SOURCES. THE STATE OF NORTH CAROLINA INCIDENT REPORT NUMBER FOR | | THIS EVENT IS "ICD-98A-07." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33830 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/04/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 18:14 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/04/98 | +------------------------------------------------+EVENT TIME: 15:40[CST]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED THAT INCORRECT TEMPERATURES HAD BEEN USED TO | | CALCULATE THE QUALIFIED LIFE OF COMPONENTS INSIDE THE POST ACCIDENT | | CONTAINMENT HYDROGEN ANALYZER PANELS. | | | | WHILE REVIEWING INDUSTRY OPERATING EXPERIENCE AND THE ORIGINAL QUALIFIED | | LIFE CALCULATION, IT WAS DETERMINED THAT INCORRECT TEMPERATURES HAD BEEN | | USED TO CALCULATE THE QUALIFIED LIFE OF THE COMPONENTS INSIDE THE POST | | ACCIDENT CONTAINMENT HYDROGEN ANALYZER PANELS. THE PANELS ARE LOCATED IN | | WHAT COULD BE A HARSH ENVIRONMENT WITHIN THE AUXILIARY BUILDING. ON FEB. | | 26, 1998, THE INTERNAL PANEL TEMPERATURES WERE DETERMINED TO BE HIGHER THAN | | THOSE USED IN THE ORIGINAL CALCULATIONS DUE TO AN INTERNAL PANEL HEAT | | SOURCE. | | | | FCT DETERMINED, BY CALCULATION AND REVIEW OF MAINTENANCE HISTORY, THAT THE | | ENVIRONMENTAL QUALIFICATION LIVES HAVE EXPIRED FOR SOME COMPONENTS LOCATED | | IN THE POST ACCIDENT CONTAINMENT HYDROGEN ANALYZER SYSTEM. SOLENOID VALVES, | | SV-1, SV-2, AND SV-3, ARE REQUIRED SUB-COMPONENTS IN THE POST-ACCIDENT | | HYDROGEN ANALYZER SYSTEM PANELS. BASED ON ORIGINAL CALCULATIONS, THE | | THERMAL QUALIFICATION LIVES FOR THE THREE SOLENOID VALVES ON EACH HYDROGEN | | ANALYZER PANEL IS 40 YEARS. BASED ON THE UPDATED CALCULATION, THE THERMAL | | QUALIFIED LIVES FOR THESE COMPONENTS ARE REDUCED TO APPROXIMATELY EIGHT (8) | | YEARS. QUALIFICATION EXPIRATION DATES ARE BASED FOR THESE COMPONENTS IS | | ESTIMATED TO BE OCTOBER OF 1989. | | | | WITH BOTH HYDROGEN ANALYZER PANELS INOPERABLE FCS TECHNICAL SPECIFICATION | | (TS) HAVE A LIMITING CONDITION FOR OPERATION (LCO) OF 72 HOURS. WITH ONE | | HYDROGEN ANALYZER PANEL INOPERABLE FCS TS HAVE A LCO OF 30 DAYS. BOTH | | PANELS WERE DECLARED INOPERABLE ON FEB. 26, 1998, BASED ON THE PRELIMINARY | | ANALYSIS. THIS PLACED THE PLANT IN A 72 HOUR LCO. THE "A" HYDROGEN ANALYZER | | PANEL WAS REPAIRED AND RETURNED TO SERVICE ON FEB. 27, 1998, LEAVING THE | | PLANT IN THE 30 DAY LCO. THE "B" HYDROGEN ANALYZER IS BEING REPAIRED AND IT | | IS ANTICIPATED THAT IT WILL BE RETURNED TO SERVICE ON MARCH 5, 1998. ON | | MARCH 3, 998, THE ANALYSIS WAS COMPLETED WHICH VERIFIED THE OPERABILITY OF | | THE OTHER COMPONENTS IN THE PANELS AND CONFIRMED THAT THE THREE VALVES ON | | EACH PANEL PREVIOUSLY MENTIONED WERE INOPERABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33831 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/04/98 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 18:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/04/98 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: DEPUYDT |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON GARDNER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 2 OF 3 PRESSURIZER CODE SAFETY VALVES EXCEEDED THEIR LIFT SETPOINT | | TOLERANCE OF 1%. | | | | TECHNICAL SPECIFICATION 4.4.3 FOR THE PRESSURIZER SAFETY VALVES REQUIRES | | THAT THE VALVES BE TESTED IN ACCORDANCE WITH TECH SPEC 4.0.5 FOR INSERVICE | | TESTING AND INSPECTION (ISI). THIS TESTING IS DONE TO VERIFY THAT THEIR | | LIFT SETPOINTS ARE WITHIN 1% OF THE SETPOINT STATED IN TECH SPECs. THE | | SURVEILLANCE IS ACCOMPLISHED BY REMOVING THE SAFETY VALVES FROM THE SYSTEM | | DURING A REFUELING OUTAGE AND SHIPPING THEM TO AN INDEPENDENT TESTING LAB | | FOR ISI TESTING. | | | | THE 3 UNIT 2 PRESSURIZER SAFETY VALVES WERE REMOVED AND SHIPPED TO WYLIE | | LABS FOR TESTING DURING THE RECENT OUTAGE. THE TESTING REPORT HAS BEEN | | RECEIVED FROM WYLIE LABS AND INDICATES THAT 2 OF THE 3 SAFETY VALVES | | EXCEEDED THEIR LIFT SETPOINT TOLERANCE OF 1%. 2-SV-45A LIFTED AT 2523 | | POUNDS, WHICH IS 1.52% ABOVE THE LIFT SETPOINT OF 2485 POUNDS. 2-SV-45B | | LIFTED AT 2570 POUNDS, WHICH IS 3.42% ABOVE HE LIFT SETPOINT. 2-SV-45C | | LIFTED WITHIN THE 1% TOLERANCE. | | | | GIVEN THE PREVIOUS HISTORY OF THESE SAFETY VALVES AND THE GUIDANCE | | CONTAINED IN THE NEW REVISION OF NUREG 1022, REVISION 1, THE OUT OF | | TOLERANCE LIFT SETPOINTS ARE CONSIDERED TO REPRESENT AN UNANALYZED | | CONDITION FOR THE PERIOD OF TIME WHEN THEY WERE OUT OF TOLERANCE. THE | | SPECIFIC LENGTH OF THIS TIME PERIOD IS UNKNOWN, AS IT IS NOT POSSIBLE TO | | DETERMINE WHEN THE SETPOINTS CHANGED. | | | | ALL 3 SAFETY VALVES WERE REPLACED DURING THE RECENT REFUELING OUTAGE. | | BECAUSE THE VALVES WERE REPLACED, THERE ARE NO FURTHER REQUIREMENTS UNDER | | THE ISI PROGRAM. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33832 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/04/98 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 18:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/04/98 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: PTACEK |LAST UPDATE DATE: 03/04/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON GARDNER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESSURIZER POWER OPERATED RELIEF VALVE (PORV) "2-NRV-152" COULD HAVE | | POTENTIALLY BEEN INOPERABLE DUE TO A LEAKING SYSTEM CHECK VALVE IN THE | | PAST. | | | | TECHNICAL SPECIFICATION 3.4.11, REACTOR COOLANT SYSTEM, RELIEF VALVES - | | OPERATING; MODES 1, 2, AND 3, CONTAINS A SURVEILLANCE (4.4.1.1c) THAT | | VERIFIES THE OPERATION OF THE SOLENOID AIR CONTROL VALVES AND CHECK VALVES | | IN THE PRESSURIZER POWER OPERATED RELIEF VALVE (PORV) CONTROL SYSTEM. | | PERFORMANCE OF THIS SURVEILLANCE ENSURES THAT THE PORVs CAN BE OPERATED | | USING NORMAL OR EMERGENCY BACKUP AIR SYSTEMS. DURING THE FALL OF 1996, IT | | WAS IDENTIFIED THAT PRESSURIZER PORV "2-NRV-152" COULD HAVE POTENTIALLY | | BEEN INOPERABLE DUE TO A LEAKING SYSTEM CHECK VALVE IN THE PAST. THE | | LEAKING CHECK VALVE COULD HAVE RESULTED IN THE EMERGENCY BACKUP AIR SUPPLY | | BEING DEPLETED IN THE EVENT THE NORMAL AIR SUPPLY DEPRESSURIZED CHALLENGING | | THE ABILITY OF 2-NRV-152 TO OPERATE. | | | | HISTORICALLY, COOK NUCLEAR PLANT HAS CONSIDERED THE REQUIREMENT FOR THE | | EMERGENCY BACKUP AIR SYSTEM TO APPLY ONLY WHEN THE PORVs ARE SUPPORTING | | OPERATIONS WITH REACTOR COOLANT SYSTEM IN A LOW TEMPERATURE OVERPRESSURE | | PROTECTION (LTOP) CONDITION (PRIMARILY MODES 4, AND 5) AND NOT DURING MODES | | 1, 2, OR 3. | | | | ON MARCH 4, 1998, AEPNG NUCLEAR LICENSING COMPLETED A REVIEW OF AN OFFICE | | OF NUCLEAR REACTOR REGULATION (NRR) POSITION RELATIVE TO THIS ISSUE. AS A | | RESULT, "2-NRV-152" WAS DETERMINED TO BE INOPERABLE. SINCE THE TECHNICAL | | SPECIFICATION ACTION STATEMENT 3.4.11 b WAS NOT ENTERED DUE TO THE ORIGINAL | | POSITION REGARDING THE EMERGENCY AIR SUPPLY SYSTEM, UNIT 2 WAS IN TS 3.0.3 | | CONDITION DURING THE PERIOD "2-NRV-152" WAS INOPERABLE. | | | | | | "2-NRV-152" WAS REPLACED AND RESTORED TO OPERABLE STATUS IN OCTOBER OF | | 1994. THEREFORE, THE CONDITION BEING REPORTED NO LONGER EXISTS. THE | | LICENSEE IS CURRENTLY EVALUATING THIS EVENT TO DETERMINE APPROPRIATE | | ACTIONS. LICENSEE EVALUATION OF THE TECHNICAL ISSUES ASSOCIATED WITH THIS | | EVENT ARE ON GOING. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33833 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NEB DIV OF RADIOACTIVE MATERIALS |NOTIFICATION DATE: 03/04/98 | | CITY: NORFOLK REGION: 4 |NOTIFICATION TIME: 19:00 [ET]| | COUNTY: MADISON STATE: NE |EVENT DATE: 03/04/98 | |LICENSE#: 07-04-01NE AGREEMENT: Y |EVENT TIME: 10:30[CST]| | DOCKET: |LAST UPDATE DATE: 03/04/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | |JOSE PICCONE, NMSS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: BRIAN HEARTY |FEMA, DOE, DOA, HHS FAX | |HQ OPS OFFICER: JOHN MacKINNON |EPA, DOT (NRC) FAX | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE OUTER HOUSING OF A SOURCE SEPARATED AT ITS WELD POINT AND DROPPED | | APPROXIMATELY 8 INCHES. | | | | THE FOLLOWING EVENT WAS SENT VIA FACSIMILE TO THE OPERATIONS CENTER FROM | | THE NEBRASKA DEPARTMENT OF HEALTH AND HUMAN SERVICES REGULATION AND | | LICENSURE PUBLIC HEALTH ASSESSMENT DIVISION RADIOACTIVE MATERIALS PROGRAM. | | | | THE NEBRASKA ASSIGNED EVENT REPORT NUMBER IS "NE-98-003" | | | | NUCOR STEEL USES EG & G BERTHOLD MODEL LB300 ML MOLD CONTROL SYSTEMS. THE | | ROD SOURCE CONTAINS 1.7 MILLICURIES OF COBALT-60. A MOLD GAUGE DEVICE WAS | | PHYSICALLY DAMAGED DURING A MOLD EXCHANGE OPERATION. THE GAUGE DEVICE | | SEPARATED AT THE WELD POINT DROPPING THE OUTER HOUSING SHIELDING | | APPROXIMATELY EIGHT INCHES. THE HIGHEST READING DETECTED WAS 2.4 | | MILLIREMS/HOUR AT 14 INCHES FROM THE GAUGE. THE GAUGE WAS PLACED IN THE | | LOCKED-OUT POSITION, A "DO NOT OPERATE" TAG APPLIED, AND THE CASTER HOUSING | | COVER PLACED BACK ON TOP OF THE MOLD TO FURTHER RESTRICT ACCESS TO THE | | DEVICE. THE STATE WAS CALLED AND AN ON-SITE INVESTIGATION IS IN PROGRESS. | | THE LICENSEE'S CONTRACTED RADIATION SAFETY CONSULTANT AND THE DISTRIBUTOR'S | | REPRESENTATIVE WERE NOTIFIED AND WILL ARRIVE ON SITE AROUND MIDNIGHT. | | | | SITE OF THE EVENT NUCOR STEEL, NE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33834 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 03/05/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 02:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/05/98 | +------------------------------------------------+EVENT TIME: 00:59[CST]| |NRC NOTIFIED BY: LANE OBEREMBT |LAST UPDATE DATE: 03/05/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO PERIMETER MONITORING. IMMEDIATE | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+