Event Notification Report for April 17, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/14/2000 - 04/17/2000 ** EVENT NUMBERS ** 36834 36890 36891 36892 36893 36894 36895 36896 36897 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36834 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 03/24/2000| |LICENSEE: HTS, INC CONSULTANTS |NOTIFICATION TIME: 17:25[EST]| | CITY: HOUSTON REGION: 4 |EVENT DATE: 02/08/2000| | COUNTY: STATE: TX |EVENT TIME: 12:00[CST]| |LICENSE#: TX-L-02757 AGREEMENT: Y |LAST UPDATE DATE: 04/14/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |LAWRENCE YANDELL R4 | | |LARRY CAMPER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JAMES OGDEN | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - STOLEN / RECOVERED CPN NUCLEAR GAUGE IN HOUSTON, | | TX | | | | The following text is from the facsimile received from the Texas Department | | of Health: | | | | "Theft/Recovery of a nuclear gauge - licensee notified the agency [Texas | | Department of Health] Feb 8, 2000. Reports lost in mail. Faxed information | | today at request of Incident Investigation. Gauge recovered intact Feb 14, | | 2000. Leak tested Feb 15, 2000 was fully satisfactory." | | | | * * * UPDATE AT 1255 ON 03/28/00 BY JAMES OGDEN TO JOLLIFFE * * * | | | | The following is a more detailed version of the above Agreement State | | Report: | | | | Texas Licensee #TX-L-02757, HTS, Inc. Consultants, Houston, Texas, reported | | to Texas Department of Health, Bureau of Radiation Control, the theft of a | | nuclear gauge in it's transport box from the bed of a company pickup truck | | on February 8, 2000. Gauge Manufacturer: CPN, Model: MC-3. Serial Number: | | M35116369. Two sealed sources: 1) Cs-137, maximum activity 10 millicuries | | and 2) Am-241/Be, maximum activity 50 millicuries. The gauge was stolen | | between 5:45 a.m. and 1:45 p.m. from a jobsite. Incident Report Number | | 16656300-H was filed with the Houston Police Department on February 8, 2000. | | Ten local pawn shops were notified by the licensee. The stolen gauge was | | discovered in a lot adjacent to Hemmi Autoworks, Houston, TX by the | | facility owner, Richard "Butch" Hemmi and reported to the City of Houston, | | Bureau of Occupational Health and Radiation Control. This organization | | recovered all components of the gauge intact on February 14, 2000 (Gauge, | | Transport box, Calibration Block, Guide Pin, Guide Plate, and paperwork of | | the last leak test.) The gauge was satisfactorily leak tested on February | | 15, 2000. The gauge was returned to storage and to service with the Texas | | licensee. | | | | The NRC Operations Officer notified the R4DO Kriss Kennedy and NMSS EO Brian | | Smith. | | | | | | * * * UPDATE AT 1206 ET ON 04/14/00 BY HELEN WATKINS TO MACKINNON * * * | | | | The licensee does not believe rad exposures to the public occurred. The | | Agency (BRC) is investigating the incident to obtain further information. | | R4DO (Chuck Paulk) & NMSS EO (Brian Smith) notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36890 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: DRESSER EQUIPMENT GROUP, INC. |NOTIFICATION DATE: 04/14/2000| |LICENSEE: DRESSER VALVE DIVISION |NOTIFICATION TIME: 15:48[EDT]| | CITY: Alexandria REGION: 4 |EVENT DATE: 04/11/2000| | COUNTY: STATE: LA |EVENT TIME: 12:00[CDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/14/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CHARLES PAULK R4 | | |CHRIS CHRISTENSEN R2 | +------------------------------------------------+PATRICK HILAND R3 | | NRC NOTIFIED BY: J. R. FENTERN |VERN HODGE NRR | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VALVE BONNETS PRODUCED FROM IMPROPERLY UPGRADED CASTINGS. | | | | The following noncompliance has been determined to be reportable within the | | requirements of 10 CFR Part | | 21. The noncompliance situation involves the delivery of two Safety Relief | | Valves to Nuclear Utilities for | | Nuclear Safety Related service that had Valve Bonnets produced from | | improperly upgraded castings. The | | valves affected by this situation are as follows: | | | | 1) Safety Relief Valve, SN TL-89763 - 1" 1970-2 (1-1-1-2)-XNC3116 (Code | | Stamped as Section VIII, Safety Related Service) | | | | This valve was supplied to Commonwealth Edison Company per their Purchase | | Order 42I091(Dresser S0 18-56188-0) for their Quad Cities Station #4 in | | October 1999. | | | | 2) Safety Relief Valve, SN TL-66815-1" 1970-2(3-1-3-2)-XFL9-NC3090 (Code | | Stamped as Section III, Class 2) | | | | This valve was supplied to Duke Energy Corporation per their Purchase Order | | MN39136 (Dresser SO 18-45913-0) for their McGuire Nuclear Station in April | | 1999. | | | | Noncompliance Situation and Brief History | | | | On Monday afternoon, April 10, 2000, during the review of documentation for | | a Nuclear Safety Related valve in process at our facility, we discovered | | that our casting supplier did not properly upgrade the bonnet staged for | | assembly of this valve. The mechanical properties of the steel were not | | verified after the heat treatment phase of the upgrading process. | | | | We began our investigation and found the following circumstances that | | contributed to this situation: | | | | 1) The supplier of these castings approved for producing and upgrading | | castings for Nuclear Safety Related Service quit producing castings by the | | shell molding process and the casting patterns were transferred to a | | commercial foundry. | | | | 2) Commercial castings were then sent by the Dresser Valve Division, | | Alexandria facility to the supplier approved for producing and upgrading | | Nuclear Safety Related Castings with instructions for the castings to be | | upgraded. | | | | 3) The purchase orders for these castings did not reflect instructions for | | upgrade, but rather read as if we were buying the Nuclear Class castings | | from this supplier. The castings used for this effort were not certifiable | | as being free of weld repairs nor were they supported by test bars for use | | in verifying the mechanical properties after final heat treatment. | | | | 4) The Alexandria Inspection department received and inspected the castings | | but failed to detect the discrepancy during the production operations prior | | to Monday, April 10, 2000. | | | | 5) On Tuesday, April 11, 2000, we determined that two valves referenced | | earlier in this report had been processed using these castings and were | | delivered to customers for use in Nuclear Safety Related Service. At this | | point, we opened an investigation per the requirements of US Code of Federal | | Regulations, Title 10 CFR, Part 21. | | | | We have conducted a full review of our records and have determined that this | | situation is isolated to the two valves referenced earlier in this report | | and have contacted the customers and are initiating recall actions as of | | this writing. Both valves in question were still in the customer's | | warehouses and had not been installed in the Safety Related Service | | applications. | | | | Corrective actions are being initiated to address the internal and external | | issues and the details will be provided in our closure report due upon | | completion of our investigation into the causes of this situation. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36891 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/14/2000| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 19:58[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 04/14/2000| +------------------------------------------------+EVENT TIME: 17:41[CDT]| | NRC NOTIFIED BY: TIM WITSCHEN |LAST UPDATE DATE: 04/14/2000| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND R3 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | BURNT SMELL FROM HIGH PRESSURE COOLANT INJECTION (HPCI) STEAM SUPPLY VALVE | | BREAKER. HPCI DECLARED INOPERABLE AND 14 DAY LIMITING CONDITION OF | | OPERATION ENTERED PER TECHNICAL SPECIFICATION. | | | | | | An undervoltage alarm was received in control room from HPCI Direct Current | | Motor Control Center (DCMCC) D312 which is located in the HPCI room. An | | operator was immediately dispatched to investigate the undervoltage | | condition on D312. The operator discovered that HPCI Steam Supply Valve, ( | | MOV-2036), breaker, (D31206), had a burnt smell. The breaker was opened and | | HPCI Steam Supply Inboard Isolation Valve was closed. HPCI was declared | | inoperable and a 14 day Limiting Condition of Operation was entered per | | their Technical Specification. Emergency Core Cooling Systems and Reactor | | Core Isolation Cooling are fully operable if needed. Their was no fire and | | the licensee is investigating. | | | | The NRC Resident Inspector will be notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36892 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/15/2000| | UNIT: [] [] [3] STATE: AL |NOTIFICATION TIME: 14:22[EDT]| | RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/15/2000| +------------------------------------------------+EVENT TIME: 12:26[CDT]| | NRC NOTIFIED BY: D. SMITH |LAST UPDATE DATE: 04/16/2000| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 | |10 CFR SECTION: | | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 A/R Y 70 Power Operation |0 Hot Shutdown | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL (RVWL) DUE TO 1 | | OF 2 REACTOR FEED PUMPS (RFP) TRIPPING. HPCI & RCIC INJECTED INTO THE | | REACTOR VESSEL FOR LESS THAN ONE MINUTE. | | | | Unit 3 was in coastdown planning to enter its scheduled refueling outage on | | 04/16/00. Reactor power level had been reduced from 82% to 70% to place RFP | | "3A" in service and remove RFP "3C" from service to investigate the pumps | | high EHC oil filter pressure. RFP "3C" tripped unexpectedly causing an | | automatic reactor scram on low RVWL. Two rods did not indicate fully | | inserted (digital indication for rods 22-47 & 18-47 indicated that they were | | not fully inserted but both rods had a green background indication on the | | scram pattern indicating that they were fully inserted) and the appropriated | | Emergency Operating Instructions EOIs ( 1& C5) were entered. An Alternate | | Rod Insertion (ARI) was initiated per the EOIs after which both rods | | indicated that they were fully inserted into the core. | | | | Due to low RVWL both Recirculation Pumps Tripped (RPT trip) and High | | Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) | | automatically actuated and discharged into the Reactor Vessel for less than | | one minute before they were secured. Primary Containment Isolation Systems | | Group 2 (Rad Waste), 3 (Reactor Water Cleanup), 6 (Containment) & 8 | | (Traversing in-core probe) were also received along with the auto start of | | the Control Room Ventilation System (CREVS) and the Standby Gas Treatment | | System (SBGT) as expected. All other system operated properly. | | | | The licensee is investigating why RFP "3C" tripped and why the digital rod | | position for rods 22-48 & 18-47 indicated that they had not fully inserted | | into the core. | | | | No work was being performed on RFP "3C" when it tripped. | | | | The NRC Resident Inspector was notified of this event by the licensee. | | | | * * * UPDATE ON 04/16/00 AT 1538 ET BY DON SMITH TAKEN BY MACKINNON * * * | | | | On 04/15/00, Browns Ferry Nuclear Plant reported that two control rods | | (22-47 and 18-47) did not indicate being fully inserted following the low | | Reactor water level scram at 1226 CT. This is corrected by this update as | | control rods 22-47 and 22-15. | | | | Subsequent review of process computer control rod data has confirmed that | | the two rods (22-47 and 22-15) did fully insert at the time if the scram as | | expected. R2DO (Chris Christensen) notified. | | | | The NRC Resident Inspector was notified of this event update by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36893 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/15/2000| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 19:22[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/2000| +------------------------------------------------+EVENT TIME: 17:14[CDT]| | NRC NOTIFIED BY: RAHRIG |LAST UPDATE DATE: 04/15/2000| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND R3 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 100 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP ON NEGATIVE FLUX RATE TRIP - DROPPED ROD. | | | | At 1714 CT Unit 2 tripped from a Nuclear Instrumentation (from all 4 Power | | Ranges) negative rate (coincidence with 2 of 4 Power Range Rate change of 5% | | in 2 seconds) signal. The initiating event appears to have been a dropped | | rod. Control Bank "B" P-10 Stationary Gripper Fuse has been found blown. | | Following the trip the Motor Driven and the Diesel Driven Auxiliary | | feedwater pumps actuated on low steam generator water level signals from all | | 4 steam generators. A P-14 (high 2 on 2 of 4 steam generator levels for | | Steam Generator "2C") was processed during the first second of the reactor | | trip. This is an ESF actuation but is considered an invalid signal, because | | Steam Generator "2C" did not have a high water level, but is reportable. All | | rods fully inserted into the core. The Unit is stable in Hot Standby with | | heat being removed via the steam dumps to the main condenser and main | | feedwater is being supplied to maintain proper steam generator water levels. | | Offsite power is available. Steam Generator atmospheric valves may have | | opened but there are no leaking steam generator tubes. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36894 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/15/2000| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 23:28[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 04/15/2000| +------------------------------------------------+EVENT TIME: 20:45[CDT]| | NRC NOTIFIED BY: TIM SMITH |LAST UPDATE DATE: 04/15/2000| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 97 Power Operation |97 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR BLOWDOWN AND BLOWDOWN SAMPLE ISOALTION VALVES CLOSED DUE TO | | RADIATION MONITOR R-15 FAILURE. | | | | Radiation Monitor R-15 air ejector exhaust failed indicating a detector no | | count failure. This failure caused steam generator blowdown isolation | | valves and steam generator blowdown sample isoaltion valves isolations to | | close. These valves have a containment isolation function for a main steam | | line rupture within containment. Their post Loss Of Coolant Accident | | function is to provide steam generator isolation. HS-17-1, Humidification | | steam inlet CV to office/warehouse ventilation also closed as designed. | | Offsite Dose Calculation Manual compensatory measures have been implemented. | | Instrument and control personnel have been called in to begin failure | | investigation. Chemistry Department personnel have been contacted | | concerning the steam generator blowdown isolation. | | | | Licensee thinks that Radiation Monitor R-15 air ejector exhaust failed | | because its chart recorder indicates erratic downscale counts for | | approximately 20 minutes. Per Radiation Monitor Logic a failure of the | | monitor will occur if no counts are detected for 5 minutes. The licensee | | also stated they have been having problems with this detector in the past | | and it had been recently replaced. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36895 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/16/2000| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 05:45[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/16/2000| +------------------------------------------------+EVENT TIME: 04:20[CDT]| | NRC NOTIFIED BY: RICK GAYHEART |LAST UPDATE DATE: 04/16/2000| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND R3 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 M/R N 0 Hot Standby |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP WITH ROD MOTION DUE TO A DIFFERENCE BETWEEN SHUTDOWN | | BANK 'B' GROUP DEMAND AND DIGITAL ROD POSITION INDICATION (DRPI) FOR ROD | | G-13 | | | | The following text is a portion of a facsimile received from the licensee: | | | | "At 0420 CDT, the Unit 2 reactor trip breakers were opened while withdrawing | | the shutdown banks. Shutdown bank 'B' was at 17 steps by group demand and | | indicated (rod G-13) 210 steps by DRPI. [Technical Reference Manual (TRM)] | | 3.1.g required [the reactor] trip [breakers] to be opened immediately. The | | unit is stable in Mode 3. All rods indicated on the bottom." | | | | The licensee stated that there was nothing unusual or not understood and | | that all systems functioned as required. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36896 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/16/2000| | UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 13:28[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/16/2000| +------------------------------------------------+EVENT TIME: 07:34[PDT]| | NRC NOTIFIED BY: RAAB |LAST UPDATE DATE: 04/16/2000| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHARLES PAULK R4 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION MADE TO THE NATIONAL MARINE FISHERIES | | | | The licensee made an offsite notification to the National Marine Fisheries | | that a green sea turtle was found inside their intake structure. The | | licensee will take the sea turtle out to sea and release it . As a courtesy | | the licensee will notified state and local officials. | | | | The NRC Resident Inspector was notified of this offsite notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36897 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/17/2000| | UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 04:57[EDT]| | RXTYPE: [2] GE-4 |EVENT DATE: 04/17/2000| +------------------------------------------------+EVENT TIME: 02:51[EDT]| | NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 04/17/2000| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND 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 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CLOSURE OF A RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING OUTBOARD ISOLATION | | VALVE RESULTING IN LOSS OF AN RHR PUMP AND SUBSEQUENT LOSS OF SHUTDOWN | | COOLING FOR 21 MINUTES | | | | The following text is a portion of a facsimile received from the licensee: | | | | "At 0251 on 04/17/00, the E1150-F008 'RHR Shutdown Cooling (SDC) Outboard | | Isolation Valve' closed causing the RHR 'B' pump to trip due to loss of | | suction flow path. At the time of the trip, the RHR 'B' pump was in | | operation for [SDC]." | | | | "[SDC] was restored at 0312. During the event, Unit 2 was in Mode 5 -- | | Refueling -- with the vessel cavity flooded up to greater than 20' 6" above | | the vessel flange with the fuel pool gates removed. No temperature rise in | | the vessel was noted during the time SDC was out of service. No core | | alterations were in progress at the time." | | | | "Prior to the closure of the E1150-F008 valve, [the] Division 2 core spray | | system was being tagged out of service for [refueling] outage maintenance. | | Part of the tag-out was to remove fuses for the core spray AC/DC inverter. | | Upon removing power to the inverter, a reactor high pressure signal caused a | | trip system B, group 4 -- Shutdown Cooling/Head Spray Isolation, which | | closes the E1150-F008 valve. After the isolation, the core spray AC/DC | | inverter was returned to service, the E1150-F008 valve opened, and RHR 'B' | | pump was placed back into [the] SDC mode." | | | | "This event is being reported under 10CFR50.72(b)(2)(ii), any event or | | condition that results in the manual or automatic actuation of any | | engineered safety feature." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021