Event Notification Report for May 15, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/14/2003 - 05/15/2003
** EVENT NUMBERS **
39844 39845 39846 39847 39848 39849
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|Power Reactor |Event Number: 39844 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/14/2003|
| UNIT: [] [3] [] STATE: PA |NOTIFICATION TIME: 11:43[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/14/2003|
+------------------------------------------------+EVENT TIME: 04:10[EDT]|
| NRC NOTIFIED BY: JAMES VASH |LAST UPDATE DATE: 05/14/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KENNETH JENISON R1 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| APPENDIX "R" ISSUE AT PEACH BOTTOM 3 |
| |
| "On May 14, 2003, at approximately 0410, the shift supervisor determined |
| that the Alternate Shutdown Panel on Unit 3 was not operable following |
| discovery of a de-energized power supply. The panel provides the capability |
| to maintain a safe shutdown path for a fire in the cable spreading room, |
| main control room or main control room fan room. Therefore, operators would |
| have been prevented from implementing required actions for a fire in those |
| areas. The apparent cause of the loss of power was a broken wire, which was |
| discovered during routine testing of the panel. |
| |
| "Power was restored to the Alternate Shutdown Panel at approximately 1030 on |
| May 14, 2003 and further investigation is in progress to determine the cause |
| of the broken wire and full extent and effect of the de-energization of the |
| panel." |
| |
| The NRC Resident Inspector was notified. |
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|Hospital |Event Number: 39845 |
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| REP ORG: UNIVERSITY WISCONSIN-MADISON |NOTIFICATION DATE: 05/14/2003|
|LICENSEE: UNIVERSITY WISCONSIN-MADISON |NOTIFICATION TIME: 12:35[EDT]|
| CITY: MADISON REGION: 3 |EVENT DATE: 05/13/2003|
| COUNTY: STATE: WI |EVENT TIME: 14:00[CDT]|
|LICENSE#: 4809843-18 AGREEMENT: N |LAST UPDATE DATE: 05/14/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |SONIA BURGESS R3 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RONALD BRESELLS | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|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 AT UNIVERSITY WISCONSIN-MADISON |
| |
| A significant under-exposure occurred on a patient undergoing therapy for |
| liver cancer. The source was an SIR-SPHERE using .058 curies of Y-90 |
| isotope. The Y-90 isotope was in semi-liquid form. The prescribed dose was |
| 58 milli-curies and the patient was delivered only 2 milli-curies. The |
| vendor of the machine has been contacted and will repair the equipment. The |
| hospital speculated that the delivery tube may have had air leaks resulting |
| in the source not being fully inserted. The patient has been rescheduled for |
| the therapy on May 28, 2003. |
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|Power Reactor |Event Number: 39846 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/14/2003|
| UNIT: [2] [3] [] STATE: NY |NOTIFICATION TIME: 15:46[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/14/2003|
+------------------------------------------------+EVENT TIME: [EDT]|
| NRC NOTIFIED BY: JOHN BAKER |LAST UPDATE DATE: 05/14/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KENNETH JENISON R1 |
|10 CFR SECTION: |MICHAEL CASE 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 99 Power Operation |99 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LOSS OF SIRENS |
| |
| "Indian Point Energy Center (IPEC) Units 2 and 3 are making an eight-hour |
| non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii). |
| |
| "On May 14, 2003 at 1035 [EDT], Rockland County notified Emergency Planning |
| (EP) that while attempting to perform a 'Cancel Test' of the counties sirens |
| a communication failure was recorded on all Rockland County sirens. EP |
| performed a review of the status of the system and determined that a |
| communication loss was experienced that prevented transmittal of |
| instructions to all sirens in the four counties. Communication between the |
| Indian Point Energy Center Emergency Operations Facility (EOF) and the 154 |
| sirens was re-established as of 1251 [EDT]. Personnel will continuously man |
| the EOF to initiate sirens if needed, until control can be re-established |
| from the affected counties. Route alerting was available during the loss of |
| sirens. |
| |
| "The NRC resident inspector, County and State were notified of this event." |
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|Power Reactor |Event Number: 39847 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/14/2003|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 17:22[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/14/2003|
+------------------------------------------------+EVENT TIME: 09:45[EDT]|
| NRC NOTIFIED BY: PETE GARDNER |LAST UPDATE DATE: 05/14/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KENNETH JENISON R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| FITNESS FOR DUTY |
| |
| A licensed employee was determined to be under the influence of alcohol |
| during a random drug test. The employee's access to the plant has been |
| removed. Contact the HOO for additional details. |
| |
| The licensee informed the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39848 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/14/2003|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 18:44[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/14/2003|
+------------------------------------------------+EVENT TIME: 09:45[EDT]|
| NRC NOTIFIED BY: RICK LLEWELLYN |LAST UPDATE DATE: 05/14/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KENNETH JENISON R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY |
| |
| A licensed employee was determined to be under the influence of alcohol |
| during a random drug test given at the Limerick Generating Station. |
| Employee was dual-licensed at both Limerick and Peach Bottom. (Refer to |
| Event Notification #39847). The employee's access to the plant has been |
| removed. Contact the Headquarters Operations Officer for additional |
| details. |
| |
| The NRC Resident Inspector has been notified by the licensee. |
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|Power Reactor |Event Number: 39849 |
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| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/15/2003|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 05:27[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/15/2003|
+------------------------------------------------+EVENT TIME: 02:52[CDT]|
| NRC NOTIFIED BY: HALL |LAST UPDATE DATE: 05/15/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JOHNSON R4 |
|10 CFR SECTION: |MICHAEL CASE NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|RICHARD WESSMAN IRO |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR TRIP FROM 100% POWER ON BOTH UNITS DUE TO TURBINE TRIP ON BOTH |
| UNITS |
| |
| The licensee reported that a loss of power on the 345KV grid caused a |
| turbine trip on both units which resulted in a reactor trip from 100% on |
| both units. All rods fully inserted and no ECCS was actuated. Both units |
| are currently at Mode 3 in natural circulation and stable. The auxiliary |
| feed water systems started on both units to maintain steam generator levels. |
| The reactor coolant temperature is being controlled by using the steam |
| generator atmospheric relief valves. Since the safety systems were powered |
| by an alternate offsite power supply, the 4 emergency diesels did not auto |
| start, but they are operable. The licensee is investigating why they lost |
| the 345KV grid. |
| |
| |
| 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