U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/07/2003 - 01/08/2003
** EVENT NUMBERS **
39491 39492 39493
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|Power Reactor |Event Number: 39491 |
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| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 01/07/2003|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 06:05[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/07/2003|
+------------------------------------------------+EVENT TIME: 03:20[EST]|
| NRC NOTIFIED BY: JOHN DUFF |LAST UPDATE DATE: 01/07/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS) |
| |
| "At 0220 hours on 01/07/03, the Safety Parameter Display System (SPDS) |
| portion of the Emergency Response Facility Computer System (ERFCS) was noted |
| to be inoperable, due to all outputs being displayed in 'magenta' color. |
| |
| "Troubleshooting of the ERFCS determined that the 'B' train of the ERFCS had |
| failed and prevented the 'A' train from booting as required. This resulted |
| in the failure of both trains of ERFCS and SPDS. Instrumentation & Controls |
| personnel were able to restore the 'A' train ERFCS and at 0450 hours on |
| 01/07/03 the ERFCS and SPDS were returned to service. |
| |
| "SPDS was out of service for greater than 1 hour, which is considered a |
| major loss of emergency assessment capability. |
| |
| "This report is being made in accordance with 10CFR50.72(b)(3)(xiii). |
| |
| "NRC, Mr. Crouch notified. Faxed to NRC # 301-816-5161 at 0618 hours." |
| |
| The NRC Resident Inspector was notified of this event by the Licensee. |
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|Power Reactor |Event Number: 39492 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/07/2003|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 11:00[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/22/2002|
+------------------------------------------------+EVENT TIME: 09:43[EST]|
| NRC NOTIFIED BY: RICHARD LOUIE |LAST UPDATE DATE: 01/07/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|10 CFR SECTION: |JOHN HANNON NRR |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| 60 - DAY OPTIONAL 10 CFR 50.73 REPORT - INVALID ACTUATION OF THE RPS SYSTEM |
| |
| "The following notification is provided by [Entergy Nuclear Operations] ENO |
| regarding Indian Point Unit 2 pursuant to 10 CFR 50.73(a)(2)(iv)(A) as 'Any |
| event or condition that resulted in manual or automatic actuation of the |
| reactor protection system (RPS) including: reactor scram or reactor trip.' |
| This notification is provided in lieu of submitting a written LER for a RPS |
| actuation that was invalid and occurred while the reactor was subcritical. |
| |
| "On November 22, 2002, at approximately 0943 hours, a reactor trip signal |
| occurred and the reactor trip breakers opened. The plant was in Hot Shutdown |
| Condition following the completion of 2R15 refueling activities with the |
| reactor subcritical (100 cps), and the Reactor Coolant System (RCS) |
| temperature and pressure at 548 F and 2195 psig, respectively. Control rod |
| testing was in progress with Control Rod Shutdown Bank 'A' withdrawn at two |
| steps. All other control rods were at zero steps. |
| |
| "An invalid RPS actuation was initiated while in this condition due to |
| ongoing work. At approximately 0930 hours, in preparation for control rod |
| drop testing the reactor trip breakers were closed. At approximately the |
| same time, technicians were in the process of re-terminating previously |
| de-termed RCS narrow range [Resistance Temperature Detector] RTD's. At |
| approximately 0940 hours, Control Rod Shutdown Bank 'A' was withdrawn at two |
| steps to support control rod drop testing. At approximately 0943 hours, |
| technicians landed a lead on loop 1 cold leg RTD, generating an Over |
| Temperature Delta Temperature (OTDT) signal. This resulted in a reactor trip |
| due to a 2/4 channel OTDT trip logic. OTDT channel 2 was previously placed |
| in trip due to nuclear flux power range channel N-42 connected to the |
| reactivity computer in support of low power physics testing. The reactor |
| trip breakers opened, inserting Shutdown Bank 'A' rods. All other rods were |
| already fully inserted. Plant response was as expected. This trip did not |
| cause a primary or secondary transient. Plant recovery was achieved in |
| accordance with existing operating procedures." |
| |
| Licensee will notify the NRC Resident Inspector. |
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|Hospital |Event Number: 39493 |
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| REP ORG: MIDMICHIGAN MEDICAL CENTER |NOTIFICATION DATE: 01/07/2003|
|LICENSEE: MIDMICHIGAN MEDICAL CENTER |NOTIFICATION TIME: 12:33[EST]|
| CITY: MIDLAND REGION: 3 |EVENT DATE: 01/06/2003|
| COUNTY: MIDLAND STATE: MI |EVENT TIME: 16:45[EST]|
|LICENSE#: 21-01549-02 AGREEMENT: N |LAST UPDATE DATE: 01/07/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RONALD GARDNER R3 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LARRY LANGRILL | |
| HQ OPS OFFICER: MIKE NORRIS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LDIF 35.3045(a)(1) DOSE <> PRESCRIBED DOSA| |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MEDICAL EVENT < 50 % OF PRESCRIBED DOSE |
| |
| At 0830 on 1/7/03, it was discovered that a patient receiving braqchytherapy |
| to the right lung using a high dose remote afterloader, received an actual |
| dose less than the prescribed dose. The source was a 5.2 curie Ir-192 and |
| the prescribed dose was 2000 cGy, which was to be administered in four 500 |
| cGy increments. The computer was programmed for the four increments, but the |
| total prescribed dose was set for 500 cGy, resulting in an actual dose |
| delivered of 125 cGy. The patient was informed that the dose received was |
| lower than intended and they would be receiving the total prescribed dose in |
| the remaining three increments. The attending Physician will be notified. |
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