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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        |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| 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.                            |
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