U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/18/1998 - 12/21/1998 ** EVENT NUMBERS ** 35169 35170 35171 35172 35173 35174 35175 35176 35177 35178 35179 35180 +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35169 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/18/1998| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 04:53[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/17/1998| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/18/1998| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JOHN JACOBSON R3 | | DOCKET: 0707002 |JOSIE PICCONE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEITH WILLIAMSON | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NRC BULLETIN 91-01 REPORT - 24 HOUR REPORT - LOSS OF ENRICHMENT CONTROL - | | | | AT 1830 ON 12/17/98, PORTSMOUTH GASEOUS DIFFUSION PLANT NUCLEAR CRITICALITY | | SAFETY DEPARTMENT PERSONNEL DETERMINED THAT A NUCLEAR CRITICALITY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED WITHIN THE X-333 | | PROCESS BUILDING. NCSA PLANT-033.A01 REQUIREMENT #6 STATES "THE ENRICHMENT | | IN THE X-333 SURGE DRUMS IS LIMITED TO 3.0% U-235". THIS REQUIREMENT WAS | | NOT MAINTAINED, THUS VIOLATING CONTROL "A" (ENRICHMENT) OF THE DOUBLE | | CONTINGENCY MATRIX A/B.5.1. ENRICHMENT SAMPLE RESULTS INDICATED 3.46% | | U-235. | | | | AT 2133, CONTROL "A" WAS REESTABLISHED BY CALCULATED DILUTION. | | | | AT 2206, ENRICHMENT SAMPLE RESULTS (1.45% U-235) CONFIRMED THE ADEQUACY OF | | THIS DILUTION. | | | | CONTROL "B" (MODERATION) WAS MAINTAINED THROUGHOUT THIS EVENT. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL NOR RADIOACTIVE OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35170 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: STATE OF MISSISSIPPI |NOTIFICATION DATE: 12/18/1998| |LICENSEE: PERF-O-LOG |NOTIFICATION TIME: 13:56[EST]| | CITY: SEMINARY REGION: 4 |EVENT DATE: 12/17/1998| | COUNTY: STATE: MS |EVENT TIME: 16:00[CST]| |LICENSE#: MS-66401 AGREEMENT: Y |LAST UPDATE DATE: 12/18/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | | | +------------------------------------------------+ | | NRC NOTIFIED BY: BOB GOFF | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - ABANDONED WELL LOGGING SOURCE | | | | A well logging source containing a 23 mCi Co-60 source was being used to log | | a salt cavern when it fell to the bottom of the cavern and was lost. The | | source cannot be recovered, and has been abandoned by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35171 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: U.S ARMY (ACALA) |NOTIFICATION DATE: 12/18/1998| |LICENSEE: U.S. ARMY (ACALA) |NOTIFICATION TIME: 15:59[EST]| | CITY: FT. IRWIN REGION: 4 |EVENT DATE: 12/14/1998| | COUNTY: STATE: CA |EVENT TIME: 12:00[PST]| |LICENSE#: 12-0072206 AGREEMENT: Y |LAST UPDATE DATE: 12/18/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |IAN BARNES R4 | | |JOHN JACOBSON R3 | +------------------------------------------------+WILLIAM KANE NMSS | | NRC NOTIFIED BY: TIM MOHS | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISSING M43A1 CHEMICAL AGENT DETECTOR | | | | The 3rd Brigade, stationed at Ft. Carson, CO, lost a model M43A1 Chemical | | Agent Detector while training at Ft. Irwin, CA in October of 1998. The | | detector contains one 250 mCi Am-241 source. The Army is attempting to | | locate the detector, and reported that these items are sometimes picked up | | by the incorrect unit while on training. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35172 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/18/1998| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 20:59[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 12/18/1998| +------------------------------------------------+EVENT TIME: 16:15[CST]| | NRC NOTIFIED BY: BART CROW |LAST UPDATE DATE: 12/18/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |10 CFR SECTION: | | |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 10 Power Operation |10 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM STEAM LEAK DUE TO IMPROPERLY TIGHTENED BOLTS | | | | "While performing the High Pressure Coolant Injection (HPCI) System | | surveillance procedure 6.HPCI.103, personnel in the room reported a steam | | leak , after the turbine was started, on the downstream flange on | | HPCI-MOV-MO14 (Steam Supply to Turbine). The Control Room tripped the | | turbine and isolated the steam line. No injuries were received and HPCI Room | | temperatures remained normal. A subsequent investigation revealed the valve | | flange bolts had not been properly tightened. | | | | "HPCI is a single train system and this event was determined to be | | reportable under 10CFR 50.72(b)(2)(iii)(D) Accident Mitigation." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35173 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 12/18/1998| | UNIT: [1] [] [] STATE: CA |NOTIFICATION TIME: 22:42[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/18/1998| +------------------------------------------------+EVENT TIME: 18:00[PST]| | NRC NOTIFIED BY: JOY SKAGGS |LAST UPDATE DATE: 12/18/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |10 CFR SECTION: | | |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 Standby |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCS PRESSURE BOUNDARY LEAKAGE DISCOVERED | | | | "On 12/17/98, at 0611 hours, Unit 1 was placed in Hot Standby in order to | | perform repairs on a lube oil cooler for Reactor Coolant Pump ( RCP) 1-3. On | | 12/18/98, during routine inspections of the work area, a buildup of boric | | acid was discovered. At 1800 hours on 12/18/98, the source of the boric acid | | was determined to be RCS leakage from the lower radial bearing RTD | | thermowell on RCP 1-3. In addition, the leakage was determined to be RCS | | pressure boundary leakage. In accordance with plant Technical | | Specifications, preparations are being made to place the Unit in Cold | | Shutdown. The magnitude of the leakage is significantly less than 1 gpm." | | | | The NRC resident inspector will be informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35174 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 12/19/1998| | UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 01:30[EST]| | RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 12/18/1998| +------------------------------------------------+EVENT TIME: 22:42[MST]| | NRC NOTIFIED BY: JOHN GUNN |LAST UPDATE DATE: 12/19/1998| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |10 CFR SECTION: | | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 | |3 N Y 100 Power Operation |100 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 39 SIRENS FOUND INOPERABLE IN THE EMERGENCY PLANNING ZONE | | | | At 2244 MST on 12/18/98, PVNGS Unit 1 was informed by the Maricopa County | | Sheriff's Department that a routine Siren Interrogation Test conducted at | | 2242 on 12/18/98 had failed for 39 offsite sirens in the emergency planning | | zone. Appropriate personnel have been dispatched to troubleshoot and | | repair. Although the cause is currently unknown, there are no adverse | | weather conditions in the vicinity. Contingency procedures are in place to | | compensate for a failure of the offsite siren system. | | | | The licensee plans to inform the NRC Resident Inspector. | | | | * * * UPDATE AT 0250 EST 0N 12/19/98 BY JOHN GUNN TO FANGIE JONES * * * | | | | Troubleshooting personnel found dirty contacts in the control switches, | | cleaned them, and tested sirens with satisfactory results. All offsite | | sirens have been restored to operable status as of 0050 MST. | | | | The licensee plans to inform the NRC Resident Inspector. The NRC Operations | | Officer informed the R4DO (Ian Barnes). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35175 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/19/1998| | UNIT: [] [2] [] STATE: MN |NOTIFICATION TIME: 12:20[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/19/1998| +------------------------------------------------+EVENT TIME: 10:56[CST]| | NRC NOTIFIED BY: WILLIAM BODIN |LAST UPDATE DATE: 12/19/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN JACOBSON R3 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | ERROR DURING TEST CAUSES MOMENTARY LOSS OF SHUTDOWN COOLING | | | | "During the performance of a turbine building cooling water header isolation | | valve safety injection relay test, the wrong relay was depressed causing a | | trip of the running RHR pump and component cooling pump. The standby | | component cooling pump autostarted on low pressure and the standby RHR pump | | was manually started to restore shutdown cooling. This is considered to be | | reportable due to an unplanned or manual/auto actuation of ESF equipment. | | The wrong relay being depressed caused a load rejection signal." | | | | The licensee reported that shutdown cooling was lost for approximately one | | minute, with no measurable increase in RCS temperature during that time. | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35176 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 12/19/1998| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 18:19[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/19/1998| +------------------------------------------------+EVENT TIME: 14:20[EST]| | NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 12/19/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |HAROLD GRAY R1 | |10 CFR SECTION: | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL STRUCTURE BOUNDARY DOOR INOPERABLE | | | | "At 1420 on 12/19/98, a Control Structure boundary door was discovered | | inoperable. The boundary door affected Control Room Emergency Outside Air | | Supply (CREAOS) operability. LCO 3.0.3 was entered. Per Technical | | Specification bases, B 3.7.3, the control structure boundary must be | | maintained, including access doors for the CREOAS system to be operable. The | | failure of the access boundary door rendered both CREOAS subsystems | | inoperable. Per Technical Specification section 3.7.3. Action D, (CREOAS): | | With 2 CREOAS subsystems inoperable in mode 1, 2 or 3 enter LCO 3.0.3 | | immediately. This constitutes a loss of a Safety Function per 10 CFR 50.72 | | (b)(2)(iii)(C), control of radiation release. | | | | "The CREOAS boundary was reestablished at 14:50 at which time LCO 3.0.3 was | | exited." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35177 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/19/1998| | UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 18:29[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/19/1998| +------------------------------------------------+EVENT TIME: 18:00[EST]| | NRC NOTIFIED BY: M. GWIRTZ |LAST UPDATE DATE: 12/19/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |HAROLD GRAY R1 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | UNIT OUTSIDE OF DESIGN BASIS DUE TO LEAKING DRAIN VALVE | | | | "Due to the discovery and verification of leakage of approximately 1/2 gpm | | from the 21 Residual Heat Removal (RHR) loop to its respective sump, it has | | been determined that Salem Unit 2 was in a condition outside its design | | basis. The leakage was from the Refueling Water Storage Tank through a | | cracked open drain valve to the RHR sump. The drain valve has been closed | | and leakage verified to be less than 1200 cc/hour, which is below the design | | value of 7680 cc/hour. Total Auxiliary Building leakage is presently 25829 | | cc/hour, which is still acceptable. Plans are to continue to work to reduce | | RHR leakage to as low a value as possible and to monitor and quantify | | leakage." | | | | The NRC resident inspector will be informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35178 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/20/1998| | UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 06:19[EST]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 12/20/1998| +------------------------------------------------+EVENT TIME: 02:53[EST]| | NRC NOTIFIED BY: HILL |LAST UPDATE DATE: 12/20/1998| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 | |10 CFR SECTION: | | |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 Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN ENGINEERED SAFEGUARDS ACTUATION DURING A SURVEILLANCE. | | | | WHILE PERFORMING IP/O/A/0310/012B(ENGINEERED SAFEGUARDS SYSTEMS LOGIC | | SUBSYSTEM 1 LOW PRESSURE INJECTION CHANNEL 3 ON LINE TEST) UNIT 2 RECEIVED A | | SPURIOUS/PARTIAL ACTION OF ES CHANNEL 3. THE "2A" LOW PRESSURE INJECTION | | PUMP AND THE "C" LOW PRESSURE SERVICE WATER PUMP STARTED AUTOMATICALLY. | | THESE COMPONENTS WERE SECURED WITHIN 2 MINUTES AND 4 MINUTES RESPECTIVELY AT | | THE DIRECTION OF THE CONTROL ROOM SRO. THE REASON FOR THE SPURIOUS ACTION | | IS UNKNOWN AT THIS TIME AND IS BEING INVESTIGATED. THERE WAS NO INDICATION | | OF HUMAN ERROR AND THEY SUSPECT IT MAY HAVE BEEN A FAULTY RELAY. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35179 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 12/20/1998| | UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 10:56[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/20/1998| +------------------------------------------------+EVENT TIME: 09:56[EST]| | NRC NOTIFIED BY: YODER |LAST UPDATE DATE: 12/20/1998| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 DECLARED BOTH TRAINS OF ANNULUS VENTILATION INOPERABLE AND | | ENTERED T.S. 3.0.3 LCO ACTION STATEMENT. | | | | BOTH TRAINS OF ANNULUS VENTILATION WERE INOPERABLE DUE TO COMPENSATORY | | ACTIONS NOT TAKEN WHEN ANNULUS DOORS WERE OPENED FOR ENTRY INTO THE ANNULUS. | | COMPENSATORY ACTIONS REQUIRE SECURITY TO STAND-BY AND NOTIFY THE CONTROL | | ROOM WHEN THE DOORS ARE OPENED. SECURITY WAS IN FACT STANDING BY THE DOORS, | | BUT THE CONTROL ROOM WAS NOT NOTIFIED WHILE THE ENTRY WAS MADE. THE CONTROL | | ROOM IS REQUIRED TO NOTIFY SECURITY TO CLOSE THE DOORS IN THE EVENT OF AN | | ANNULUS VENTILATION SYSTEM ACTUATION. THE LICENSEE HAS EXITED T.S. 3.0.3 | | ACTION STATEMENT. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED OF THE EVENT. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35180 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 12/20/1998| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 18:25[EST]| | RXTYPE: [1] GE-3 |EVENT DATE: 12/20/1998| +------------------------------------------------+EVENT TIME: 16:35[CST]| | NRC NOTIFIED BY: KEVIN PEDERSON |LAST UPDATE DATE: 12/20/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN JACOBSON R3 | |10 CFR SECTION: | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS | | | | "Battery charger D-13 shows no load. This battery charger supplies charging | | to the Division I 24 volt battery system. This places the unit in a 24-hour | | Technical Specification required shutdown per T.S. 3.9.B. Engineering is | | evaluating the status of charger D-13." | | | | The NRC resident inspector has been informed of this event by the licensee. | | | | * * * Update 2201 12/20/98 from Walsh taken by Stransky * * * | | | | The battery charger has been repaired, and the shutdown has been terminated. | | Reactor power remained at 100% throughout the event. The NRC resident | | inspector has been informed by the licensee. Notified R3DO (John Jacobson). | +------------------------------------------------------------------------------+