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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| | |
| | |
| | |
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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| preventing personnel from opening the device with the source withdrawn.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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021