The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for July 1, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/28/2002 - 07/01/2002

                              ** EVENT NUMBERS **

38953  39019  39024  39025  39026  39027  39028  39029  39030  39031  39032  
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38953       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 05/31/2002|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 01:08[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        05/30/2002|
+------------------------------------------------+EVENT TIME:        20:30[CDT]|
| NRC NOTIFIED BY:  JOHN B. REIS, JR.            |LAST UPDATE DATE:  05/31/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCS DECLARED INOPERABLE FOLLOWING FAILURE OF ASSOCIATED EDG DURING
POST     |
| MAINT TESTING                                                                |
|                                                                              |
| "This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D), Event or    |
| Condition That Could Have Prevented Fulfillment of a Safety Function needed  |
| to Mitigate the Consequences of an Accident.  During a post maintenance test |
| run of the 2B Diesel Generator following a planned maintenance window, the   |
| Diesel Generator reactive load (VARs) was identified to be extremely erratic |
| as the Diesel Generator was loaded. At 20:30 Central Daylight Savings Time,  |
| it was discovered that a potentiometer in the voltage regulating circuit had |
| failed. This potentiometer was not worked on during the planned maintenance  |
| window. Because this component failure could have prevented the Diesel       |
| Generator from performing its design function, and because the 2B Diesel     |
| generator is the emergency power supply for the High Pressure Core Spray     |
| System (HPCS), which is a single train safety system, it has been determined |
| that this failure is reportable as an 8 hour ENS notification.  The failed   |
| component has currently been replaced and further testing of the Diesel      |
| Generator is in progress. The required actions of Technical Specification    |
| 3.5.1 were entered when the system was made Inoperable for the maintenance   |
| window, and are continuing to be followed for the Inoperable HPCS system     |
| until the Diesel Generator is restored to Operable status."                  |
|                                                                              |
| The licensee anticipates completing testing by the end of dayshift on        |
| 5/31/02 and has informed the NRC Resident Inspector.                         |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39019       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TENNESSEE DIV OF RAD HEALTH          |NOTIFICATION DATE: 06/26/2002|
|LICENSEE:  TENNESSEE DEPT OF TRANSPORTATION     |NOTIFICATION TIME:
10:20[EDT]|
|    CITY:  CORRYTON                 REGION:  2  |EVENT DATE:        06/25/2002|
|  COUNTY:  KNOX                      STATE:  TN |EVENT TIME:        21:00[EDT]|
|LICENSE#:  R-19017               AGREEMENT:  Y  |LAST UPDATE DATE:  06/26/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LEONARD WERT         R2      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DEBRA SHULTS                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE                                |
|                                                                              |
| The following is taken from a faxed report:                                  |
|                                                                              |
| Event Report ID No.:  TN-02-083                                              |
|                                                                              |
| License No:  TN-02-083                                                       |
|                                                                              |
| Licensee:  Tennessee Division of Radiological Health                         |
|                                                                              |
| Event date and time:  June 25, 2002, 2100 EDT                                |
|                                                                              |
| Event location:  R-19017                                                     |
|                                                                              |
| Event type:  Stolen moisture density gauge                                   |
|                                                                              |
| Notifications:  USNRC Region II, Knox County Sheriffs Department             |
|                                                                              |
| Event description: Tennessee Department of Transportation, Region 1, called  |
| the Division at 0818 CDT to report a stolen moisture density gauge. The      |
| gauge is a Troxler model 3430, serial number 23117 containing 8 millicuries  |
| of Cesium-137, serial number 75-4928 and 40 millicuries of Am-241:Be, serial |
| number 47-18934. The gauge was inside a white Ford Aerostar van. License     |
| number S4-PE83, owned by the State. The van was parked at the operator's     |
| home on McGinnis Road in Corryton, TN.                                       |
|                                                                              |
| Media attention:  None at this time. A press release will be issued by TDEC. |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39024       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/27/2002|
|    UNIT:  [2] [3] []                STATE:  NY |NOTIFICATION TIME: 15:20[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/27/2002|
+------------------------------------------------+EVENT TIME:        12:10[EDT]|
| NRC NOTIFIED BY:  MARK LEONE                   |LAST UPDATE DATE:  06/28/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHAEL MODES        R1      |
|10 CFR SECTION:                                 |CHRIS GRIMES         NRR     |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OPERABLE EP SIRENS  BELOW MINIMUM NUMBER AT INDIAN POINT                     |
|                                                                              |
| Two counties located in the emergency planning zone went below the minimum   |
| number of operable EP sirens.  Westchester County had 12 sirens inoperable   |
| out of a total of 77 sirens.  Orange County had approximately 8 sirens not   |
| working out of a total of 16.  The minimum number operable criteria is 90%   |
| operating out of the total number in each county. The licensee attributed    |
| the inoperable sirens due to a storm that passed through the area yesterday. |
| Compensatory measures were in place including route alerting.                |
|                                                                              |
| The NRC resident inspector was notified.                                     |
|                                                                              |
| *****UPDATE LEONE TO LAURA ON 6/28/02 AT 13:48*****                          |
|                                                                              |
| The licensee reported that Westchester County had greater than 90% of their  |
| sirens working by 18:20 on 6/27/02.  All EP sirens in the 4 counties within  |
| the EPZ were working as of 11:28 on 6/28/02.                                 |
|                                                                              |
| The NRC resident inspector was notified.  Notified R1DO (M. Modes).          |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39025       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 06/28/2002|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 09:47[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        06/28/2002|
+------------------------------------------------+EVENT TIME:        01:52[EDT]|
| NRC NOTIFIED BY:  HARRY GILES                  |LAST UPDATE DATE:  06/28/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHRISTINE LIPA       R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL LOSS OF CONTROL CENTER HVAC ACCIDENT MITIGATION CAPABILITY
DURING  |
| MAINTENANCE ACTIVITIES                                                       |
|                                                                              |
| " Control Center HVAC access panel opened at 2152 hours on 6-27-02,          |
| unfiltered air in-leakage potentially allowed into the operating division of |
| [the] Control Center HVAC , potentially affecting post accident dose         |
| assessment per 10 CFR 50.72 (b) (3)(v)(D).                                   |
|                                                                              |
| " Control Center access panel closed at 2222 hours on 6-27-02, maintenance   |
| activities halted on CCHVAC.                                                 |
|                                                                              |
| "Tech Spec 3.0.3 entry recognized at 0152 hours 6-28-02.  Tech Spec exited   |
| within 30 minutes, no actions taken to commence plant shutdown."             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39026       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  US ARMY                              |NOTIFICATION DATE: 06/28/2002|
|LICENSEE:  US ARMY                              |NOTIFICATION TIME: 10:20[EDT]|
|    CITY:  ABERDEEN                 REGION:  1  |EVENT DATE:        06/26/2002|
|  COUNTY:                            STATE:  MD |EVENT TIME:             [EDT]|
|LICENSE#:  19-30563-01           AGREEMENT:  Y  |LAST UPDATE DATE:  06/28/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL MODES        R1      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOYCE KUYKENDALL             |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF A CHEMICAL AGENT DETECTOR IN KOREA                                   |
|                                                                              |
| A chemical agent detector (model M43A1) containing 300 microcuries was lost  |
| by an Army unit in Korea.  Aberdeen was notified on 06/26/02 and there are   |
| no further details at this time.  The unit will investigate and send in a    |
| report to Aberdeen.  The detector posses little or no threat to the public.  |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39027       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 06/28/2002|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 13:43[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/27/2002|
+------------------------------------------------+EVENT TIME:        18:00[EDT]|
| NRC NOTIFIED BY:  RITA BRADDICK                |LAST UPDATE DATE:  06/28/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHAEL MODES        R1      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       24       Power Operation  |24       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
|  LICENSED THERMAL POWER LIMIT EXCEEDED AT HOPE CREEK                         |
|                                                                              |
| The following is taken from a facsimile sent by the licensee:                |
|                                                                              |
| "On May 26, 2002, an equipment failure related to the feedwater crossflow    |
| correction factor resulted in the Hope Creek Generating Station operating    |
| above its' Licensed Power Limit of 3339 megawatts thermal for a period of    |
| approximately 8 hours. Upon identification of an anomalous indication        |
| associated with the crossflow indication, operators conservatively lowered   |
| Reactor power to a value below the station's licensed limit pending          |
| evaluation of the condition. Subsequent detailed evaluation has since        |
| confirmed that a malfunction of the crossflow instrumentation correction     |
| factor caused an overpower condition. The event date and time coincide with  |
| the completion of the evaluation. Contrary to regulatory guidance for power  |
| maintenance, the facility operated at approximately 100.25% for greater than |
| 2 hours. However, at no time did the station power level exceed 100.47%, nor |
| was the shift average power level limit exceeded. This 24 hour report is     |
| being made for violation of the requirements contained in the Operating      |
| License (Hope Creek Operating License Number NPF-57, section 2.F,            |
| specifically Section 2.C (1)-exceeding the maximum power level of 3339       |
| megawatts thermal.[)]"                                                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39028       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 06/28/2002|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 21:12[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/28/2002|
+------------------------------------------------+EVENT TIME:        18:30[EDT]|
| NRC NOTIFIED BY:  BUD HINCKLEY                 |LAST UPDATE DATE:  06/28/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |ANNE MARIE STONE     R3      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     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 OF OIL SPILL AT DC COOK DURING SWITCHYARD
MAINTENANCE   |
|                                                                              |
| "At 18:30 EDT on 6/28/2002, while transporting the 1-TR-N1-CT2, Unit 1       |
| Palisades to 345 KV Bus #1 Air Blast Breaker 52-Ni Phase #2 Current          |
| Transformer, the insulator dropped off the forklift and cracked, causing an  |
| oil leak of approximately 25 gallons onto the ground. The Michigan           |
| Department of Environmental Quality Pollution Emergency Alert System was     |
| notified at 20:15 on 6/28/02, requiring 4-Hr Non-Emergency 10 CFR 50.72      |
| (b)(2)(xi) event notification to be made. There is no impact to plant        |
| personnel or operating equipment. A permit has been generated to allow       |
| removal of the affected soil for proper disposals"                           |
|                                                                              |
| The licensee was performing maintenance in the switchyard at the time. The   |
| current transformer was the old one which was replaced. The oil spill did    |
| not directly impact the ongoing maintenance activity.                        |
|                                                                              |
| The NRC resident inspector was notified.                                     |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39029       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 06/29/2002|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 05:51[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        06/29/2002|
+------------------------------------------------+EVENT TIME:        02:00[EDT]|
| NRC NOTIFIED BY:  JAMES VOUGLITOIS             |LAST UPDATE DATE:  06/29/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHAEL MODES        R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION                                                         |
|                                                                              |
| KEMP'S RIDLEY SEA TURTLE CAUGHT AND GIVEN TO THE MARINE MAMMAL
STRANDING     |
| CENTER.  OFFSITE NOTIFICATION MADE TO THE NATIONAL MARINE FISHERY
SERVICES.  |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT  BY THE
LICENSEE.  |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39030       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 06/29/2002|
|    UNIT:  [1] [2] [3]               STATE:  AL |NOTIFICATION TIME: 12:44[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        06/29/2002|
+------------------------------------------------+EVENT TIME:        08:52[CDT]|
| NRC NOTIFIED BY:  DONALD SMITH                 |LAST UPDATE DATE:  06/29/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LEONARD WERT         R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BROWNS FERRY SPURIOUS ACTUATION OF OFFSITE EMERGENCY NOTIFICATION
SIRENS     |
|                                                                              |
| "At 0852 on 06/29/02, the Operations Duty Specialist (ODS) notified the      |
| Browns Ferry Shift Manager of a spurious actuation of the Off Site Emergency |
| Notification Sirens for a duration of less than 3 minutes in Lawrence        |
| County, Alabama. A TVA news release is not planned at this time, however,    |
| the event is being reported due to inquires from county representatives to   |
| the TVA ODS regarding the siren activation. A review of the cause of the     |
| actuation is in progress.                                                    |
|                                                                              |
| "This event is reportable per 10CFR50.72 (b)(2)(xi) as  'Any event or        |
| situation, related to the health and safety of the public or onsite          |
| personnel, or protection of the environment for which a news release is      |
| planned or notification to other government agencies has been or will be     |
| made. Such an event may include an onsite fatality or inadvertent release of |
| radioactive contaminated material'."                                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39031       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 06/29/2002|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 16:43[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/29/2002|
+------------------------------------------------+EVENT TIME:        14:38[CDT]|
| NRC NOTIFIED BY:  CRAIG JANAK                  |LAST UPDATE DATE:  06/29/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SOUTH TEXAS NUCLEAR PROJECT SPURIOUS ACTUATION OF OFFSITE NOTIFICATION 
     |
| SIREN                                                                        |
|                                                                              |
| "At 14:38 on 6/29/02, received notification that a South Texas Nuclear       |
| Project Offsite Emergency Notification siren located in the Tres Palacios    |
| Oaks subdivision was spuriously going off over the last 4 hours. This        |
| notification was from a resident in the subdivision. This siren is going off |
| while thunderstorms are moving through the area. The Matagorda County        |
| Sheriff's Department was informed by site personnel of these spurious alarms |
| and personnel have been dispatched to resolve the issue with the siren."     |
|                                                                              |
| The licensee has notified the NRC Resident Inspector.                        |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39032       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 07/01/2002|
|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 00:33[EDT]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        06/30/2002|
+------------------------------------------------+EVENT TIME:        18:58[PDT]|
| NRC NOTIFIED BY:  CONOSCENTI                   |LAST UPDATE DATE:  07/01/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       18       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
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| AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR PRESSURE DUE TO TWO
ADDITIONAL |
| STEAM DUMP VALVES FULLY OPENING DURING STARTUP.                              |
|                                                                              |
| System Affected                                                              |
| "Primary: Rx Trip, CEA, RCP's stayed on, PLCS"                               |
| "Secondary: SBCS Open, MSIV's, ADV, MFW, AFW"                                |
|                                                                              |
| Actuations and Their Initiating Signals                                      |
| "MSIS A & B @ 741 PSIA.  Lowest Seen = MSIS setpoint"                        |
|                                                                              |
| Causes                                                                       |
| "Prelim:  4 SBCS All Fast Open . . . "                                       |
|                                                                              |
| Effect Of Event Plant                                                        |
| "Low S/G Pressure Rx Trip, Turbine Trip, MSIS isolated secondary.  CVCS      |
| remained in service.  MSIS verified and rest, then AFW initiated. (Did not   |
| want cooldown from steam-driven AFW Pp. Adequate S/G water level maintained  |
| throughout. Approx. 50% NR)."                                                |
|                                                                              |
| Actions Taken or Planned                                                     |
| "EOI's: S023-12-1 (SPTA's), S023-12-2 (RTR), OI: S023-S-1.3.1 S0123-0-14  4  |
| Hour"                                                                        |
| "E-PLAN Review P S/G" [decreased])                                           |
|                                                                              |
| The licensee was going to bring the main turbine on line which was rolling   |
| at 1800 rpm. Two steam dump bypass valves were open dumping steam to the     |
| main condenser to help maintain reactor power at 18%. Unexpectedly two       |
| additional steam dump bypass valves opened.  When these two additional steam |
| dump bypass valves opened the first two open valves initial started to close |
| then they went full open.  Steam generator pressure decreased to the low     |
| steam generator pressure setpoint of 741 psia at which point an automatic    |
| reactor trip plus a main steam isolation signal (MSIS) was generated, main   |
| steam isolation valves (MSIV's) closed.   All rods fully inserted into the   |
| core.   Atmospheric steam dump valves were used to maintained proper reactor |
| coolant system temperature.  The licensee said that they did not have any    |
| leaking steam generator tubes.  Proper steam generator water inventory was   |
| verified at which time the MSIS signal was reset, then one Motor Driven      |
| Auxiliary Feedwater Pump was manually initiated to maintain proper steam     |
| generator water level.   Main feedwater system isolated due to the MSIS      |
| signal and the reactor trip.  All emergency core cooling systems, emergency  |
| diesel generators are fully operable if needed.  The electrical grid is      |
| stable.  The licensee is investigating why the two additional steam dump     |
| bypass valves opened.                                                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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Page Last Reviewed/Updated Thursday, March 25, 2021