Event Notification Report for January 24, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/23/2001 - 01/24/2001
** EVENT NUMBERS **
37676 37677 37678 37679 37680 37681
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|Power Reactor |Event Number: 37676 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/23/2001|
| UNIT: [1] [] [] STATE: VA |NOTIFICATION TIME: 02:24[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/23/2001|
+------------------------------------------------+EVENT TIME: 01:46[EST]|
| NRC NOTIFIED BY: JOHN VOISSEM |LAST UPDATE DATE: 01/23/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: |JOHN HANNON NRR |
|*AEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH GIITTER IRO |
| |BELCHER FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED ON LOSS OF ALL ANNUNCIATORS FOR GREATER THAN 15 |
| MINUTES |
| |
| The licensee was conducting daily light checks of annunciators when they did |
| not clear when the test signal was reset. The declaration of Unusual Event |
| was made at 0146 EST in accordance with the Emergency Action Level procedure |
| and entry was also made into the abnormal procedure for the loss of |
| annunciators. |
| |
| The plant computer was still available for alarm monitoring and 2 operators |
| were placed at the control panels for close monitoring of plant conditions. |
| The plant was maintained at stable conditions. The watch stations outside |
| of the control room were augmented to provide additional monitoring of |
| outside control panel alarms which would not be received in the control |
| room. Electricians and Instrumentation Technicians have started |
| investigating the problem. |
| |
| The licensee notified the NRC Resident Inspector and the state and local |
| authorities. |
| |
| * * * UPDATED AT 0242 EST ON O1/23/01 BY JOHN VOISSEM TO FANGIE JONES * * * |
| |
| |
| The Unusual Event was terminated at 0237 EST. The alarm lights cleared on |
| their own and subsequent test of alarm function was satisfactory. |
| Additional personnel are in transit to the site to conduct further testing. |
| |
| The licensee will notify the NRC Resident Inspector as well as state and |
| local authorities. Notified the R2DO (Rudolph Bernhard), NRR EO ( John |
| Hannon), IRO Manager (Joseph Giitter), and FEMA (Belcher). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37677 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/23/2001|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 09:00[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/23/2001|
+------------------------------------------------+EVENT TIME: 06:19[EST]|
| NRC NOTIFIED BY: LEE JOHNSON |LAST UPDATE DATE: 01/23/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 29 Power Operation |27 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED DUE TO FAILURE OF SHUTDOWN BANK "D" TO FULLY |
| WITHDRAW DURING SURVEILLANCE TESTING |
| |
| The licensee was performing rod surveillance testing when shutdown bank "D" |
| failed to withdraw. Entry was made to Technical Specification 3.0.3 at 0619 |
| CST as more than one rod failed to withdraw. The plant commenced shutdown |
| at 0712 CST. See related event #37675. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37678 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 01/23/2001|
| UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 09:41[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 01/22/2001|
+------------------------------------------------+EVENT TIME: 13:50[EST]|
| NRC NOTIFIED BY: PAULENE BAATEY |LAST UPDATE DATE: 01/23/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RUDOLPH BERNHARD R2 |
|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 |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY |
| |
| A nonlicensed employee was determined to have used an illegal drug during a |
| random test. The employee's access to the plant has been suspended. |
| |
| Contact the Headquarters Operation Officer for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37679 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 01/23/2001|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 18:16[EST]|
| RXTYPE: [2] GE-5 |EVENT DATE: 01/23/2001|
+------------------------------------------------+EVENT TIME: 13:20[PST]|
| NRC NOTIFIED BY: BOB SHERMAN |LAST UPDATE DATE: 01/23/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTRACT SUPERVISOR CONFIRMED POSITIVE FOR ILLEGAL DRUG USE DURING RANDOM |
| TEST |
| |
| A contract supervisor was determined to be under the influence of an |
| illegal drug during a random test. The individual's access to the plant has |
| been terminated. The licensee informed the NRC resident inspector. |
| |
| Contact the Headquarter Operation Officer for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37680 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/23/2001|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 19:03[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/23/2001|
+------------------------------------------------+EVENT TIME: 11:09[CST]|
| NRC NOTIFIED BY: MIKE MacLENNAN |LAST UPDATE DATE: 01/23/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|*IND 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROL ROOM EMERGENCY VENTILATION SYSTEM DECLARED INOP ON LOW FLOW |
| |
| "On January 23, 2001, while performing the Control Room Emergency Filtration |
| System (CREVS) monthly surveillance, the system flow was found to be 1741 |
| SCFM [standard cubic feet per minute]. The required Technical Specification |
| flow is 2000 SCFM +/- 10%. |
| |
| "The CREVS system was declared inoperable per Technical Specification 3.8.D |
| and both Units entered a 7 day shutdown LCO. |
| |
| "This is being reported in accordance with 10CFR50.72(b)(3)(v)(D). |
| |
| "The initial flow measured was 1741 SCFM. Approximately 15 minutes later |
| the flow was measured to be within Technical Specification limits. The |
| station is continuing an evaluation of this issue." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37681 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/23/2001|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 20:47[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/23/2001|
+------------------------------------------------+EVENT TIME: 15:10[EST]|
| NRC NOTIFIED BY: DEAN BRUCK |LAST UPDATE DATE: 01/23/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|*INC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF CONTAINMENT INTEGRITY INVOLVING PERSONNEL AIRLOCK INTERLOCK FAILURE |
| |
| "On 23 January 2001, at 1510 hours, during the removal of radiation survey |
| equipment from the lower containment personnel airlock, the airlock doors |
| interlock failed. This allowed the inadvertent opening of both containment |
| airlock doors at the same time for less than one minute. This resulted in a |
| short entry into Technical Specification 3.6.1.1, for Primary Containment |
| integrity and entry into Technical Specification 3.6.1.3, for inoperable |
| Containment Airlock Doors. There was no radioactive release as the result of |
| this event." |
| |
| The cause of the interlock failure is under investigation. Currently the |
| licensee is controlling entry administratively. The licensee informed the |
| NRC resident inspector. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021