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Event Notification Report for July 8, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/05/2002 - 07/08/2002

                              ** EVENT NUMBERS **

39042  39043 39045  
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|Other Nuclear Material                           |Event Number:   39042       |
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| REP ORG:  GEORGE WASHINGTON UNIVERSITY         |NOTIFICATION DATE: 07/05/2002|
|LICENSEE:  GEORGE WASHINGTON UNIVERSITY         |NOTIFICATION TIME: 17:45[EDT]|
|    CITY:  WASHINGTON               REGION:  1  |EVENT DATE:        07/05/2002|
|  COUNTY:                            STATE:  DC |EVENT TIME:        17:00[EDT]|
|LICENSE#:  08-00216-23           AGREEMENT:  N  |LAST UPDATE DATE:  07/05/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PETE ESELGROTH       R1      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY JOHNSON                |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| CONDITION OF LICENSE REPORT INVOLVING A STUCK IRRADIATOR SOURCE              |
|                                                                              |
| The RSO at George Washington University discovered during testing that the   |
| nominal 5,000 Ci Cs-137 source (measured 8/24/1986) used in their J.L.       |
| Shepherd Mk I irradiator had stuck in the up position.  Radiation readings   |
| were immediately taken which indicated no excess personnel exposures were    |
| involved.  The highest lateral reading at a distance of 30cm was             |
| approximately 0.18mr/hr.  The door interlock is functioning properly         |
| preventing personnel from opening the device with the source withdrawn.  As  |
| a precaution, access had been restricted to the area.  The licensee will     |
| continue their efforts to contact the manufacturer or his service            |
| representative.                                                              |
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|Power Reactor                                    |Event Number:   39043       |
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| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 07/07/2002|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 04:50[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/07/2002|
+------------------------------------------------+EVENT TIME:        00:15[EDT]|
| NRC NOTIFIED BY:  JOHN MACDONALD               |LAST UPDATE DATE:  07/07/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PETE ESELGROTH       R1      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HPCI BECAME INOPERABLE WHILE REPLACING AN INDICATING LIGHT BULB AT
PILGRIM   |
|                                                                              |
| "On 07 July 2002, at 0015 hrs, HPCI was declared inoperable when it was      |
| discovered that the control power fuses for the HPCI pump discharge valve,   |
| MO-2301-8 had blown. The MO-2301-8 is a normally closed direct current (DC)  |
| motor operated valve. At the time of the event, control room operators were  |
| attempting to replace a burned out main control room light bulb for the      |
| closed indication for the valve. The operators reported that the light       |
| socket was loose. The newly installed bulb failed to illuminate. A field     |
| operator was dispatched to the alternate shutdown panel (ASP) for HPCI and   |
| reported that there was no light indication for the MO-2301-8 at the ASP as  |
| well. Qualified personnel then inspected the control power fuses within the  |
| DC breaker for the valve. It was determined that an instantaneous short      |
| circuit occurred due to the loose light socket when the light bulb was       |
| replaced, causing the control power fuses to blow. The light socket was      |
| tightened, the control power fuses were replaced, proper MO-2301-8 position  |
| indication was verified, and HPCI was declared operable at 0045 hrs."        |
|                                                                              |
| The USNRC Resident Inspector has been notified.                              |
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|Power Reactor                                    |Event Number:   39045       |
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| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 07/08/2002|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 02:57[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        07/07/2002|
+------------------------------------------------+EVENT TIME:        23:12[CDT]|
| NRC NOTIFIED BY:  STEVEN KASPER                |LAST UPDATE DATE:  07/08/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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      |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| AUTOMATIC REACTOR TRIP                                                       |
|                                                                              |
| "At 2312 on 07/07/2002 Unit 2 Reactor automatically tripped from full power  |
| due to a high high Steam Generator Level In the 2B Steam Generator. Prior to |
| the trip Vital distribution panel 1202 lost power when it's normal power     |
| supply inverter failed. All of the controlling channels of Steam Generator   |
| level were powered from this distribution panel and failed low on the loss   |
| of power. Operators were in the process of taking manual control of all Feed |
| Water Regulating valves when the Main Turbine trip was actuated due to the   |
| high high level in Steam Generator 28. A Reactor Trip occurred due to        |
| Turbine Trip above 50% power. The unit is stable in Mode 3 with RCS          |
| temperature at 567 degrees Fahrenheit, and RCS pressure of 2235 pslg.        |
|                                                                              |
| "We also make the following report per 10CFR50.72(b)(3)(iv): Following the   |
| Reactor Trip the Auxiliary Feed Water System automatically actuated on low   |
| Steam Generator level. This is normal for a trip in Unit 2 from full power   |
| with the Model E Steam Generators.                                           |
|                                                                              |
| "The following information is also provided:                                 |
|                                                                              |
| "Did the control rods fully insert? Yes                                      |
|                                                                              |
| "Did steam bypass to the condenser or to atmosphere? The Steam Dump system   |
| automatically operated to maintain temperature. No steam bypass to           |
| atmosphere occurred.                                                         |
|                                                                              |
| "Did any primary/secondary relief valve lift? NO                             |
|                                                                              |
| "Any significant TS LCOs entered? TS 3.8.3.1 Action b. was entered due to    |
| vital DP 1202 not being powered from its normal power supply inverter. We    |
| must reenergize the AC distribution panel from its associated inverter       |
| connected to its associated D.C. bus within 24 hours or be in at least HOT   |
| Standby within the next 6 hours and in Cold Shutdown within the following 30 |
| hours.                                                                       |
|                                                                              |
| "Item not understood: Channel 1 of P-13 Reactor Trip System interlock status |
| light is currently blinking. This condition must be understood and corrected |
| prior to restart."                                                           |
|                                                                              |
| The NRC resident inspector was notified.                                     |
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