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