Event Notification Report for December 27, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/26/2002 - 12/27/2002
** EVENT NUMBERS **
39421 39469 39473
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39421 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 12/03/2002|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 17:13[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 12/03/2002|
+------------------------------------------------+EVENT TIME: 13:30[EST]|
| NRC NOTIFIED BY: VICTOR WALZ |LAST UPDATE DATE: 12/26/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHELE EVANS 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 SYSTEM DECLARED INOPERABLE DURING QUARTERLY PERFORMANCE TESTING |
| |
| "During scheduled High Pressure Coolant Injection [HPCI] system quarterly |
| performance testing, the HPCI system was declared inoperable when it was |
| determined that the HPCI turbine steam admission valve (23MOV-14) failed |
| ASME Section XI, Inservice Testing Stroke Time Criteria. During Testing the |
| steam admission valve opened only 35-38% of full stroke. However, with this |
| deficiency the HPCI system met required test acceptance criteria for flow |
| control, injection capacity, and injection time. It was determined that the |
| steam admission valve partially opened due to a broken wiring connection in |
| the valve operator. The broken connection was repaired and HPCI testing was |
| completed satisfactorily. The HPCI system was declared operable at 1630 EST |
| (12/3/02)." |
| |
| The licensee intends to notify NRC Region of this event. |
| |
| * * * EVENT RETRACTION FROM ANDY HALLIDAY TO ARLON COSTA ON 12/26/02 AT |
| 14:56 * * * |
| |
| "Event Notification Retraction |
| |
| "On 12/3/02 at 1330 EST, the James A. Fitzpatrick nuclear power plant |
| notified the NRC operations center of the High Pressure Coolant Injection |
| (HPCI) System being declared inoperable when the HPCI turbine steam |
| admission valve (23MOV-14) failed ASME Section XI lnservice Testing stroke |
| time criteria. During testing, the steam admission valve opened only |
| approximately 39% of full stroke due to a broken wiring connection in the |
| valve operator, The report was made pursuant to 10CFR50.72(b)(3)(v)(D) under |
| Event Notification number 39421. |
| |
| "Based upon further review, it has been determined that, despite the problem |
| noted, HPCI would have performed its safety function, With this deficiency |
| (at 1040 psig reactor pressure), the HPCI system still met the required test |
| acceptance criteria for flow control, injection capacity and injection time, |
| as the HPCI control valve, located in series in the steam flow, compensated |
| for the partial closure of the steam admission valve. An engineering |
| evaluation showed that the HPCI System would have continued to meet its |
| design basis requirements over the full operational pressure range (150 psi |
| to 1195 psig). |
| |
| "The failure of 23M0V-14 to fully open was immediately corrected. The cause |
| of the failure and its applicability to other safety related components will |
| be determined through the JAF corrective action system. |
| |
| "Based upon the ability of the HPCI System to perform its safety function, |
| the above notification, number 39421 is being retracted." |
| |
| The Licensee has notified the NRC Resident Inspector. Notified R1DO |
| (Jenison). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39469 |
+------------------------------------------------------------------------------+
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| REP ORG: NEW MEXICO RAD CONTROL PROGRAM |NOTIFICATION DATE: 12/23/2002|
|LICENSEE: P & M CONSTRUCTION INC. |NOTIFICATION TIME: 15:07[EST]|
| CITY: PONDEROSA REGION: 4 |EVENT DATE: 12/12/2002|
| COUNTY: STATE: NM |EVENT TIME: [MST]|
|LICENSE#: DM159-03 AGREEMENT: Y |LAST UPDATE DATE: 12/23/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |CHARLES COX NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MILLER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| STOLEN TROXLER DENSITY MOISTURE GAUGE |
| |
| P & M Construction, Inc notified the state on 12/12/02 that a Troxler model |
| 3411B (serial # 12073) density moisture gauge was stolen from their shop in |
| Ponderosa, New Mexico sometime in September or October of this year. The |
| gauge contained a 9 millicurie Cs-137 source (serial # 409584) and a 50 |
| millicurie Am-241: Be source (serial # 477368). The gauge was locked in its |
| transport container with a locked chain securing the container. This chain |
| was cut and the locked container was removed from the shop. A police report |
| was made. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39473 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 12/26/2002|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 17:47[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/26/2002|
+------------------------------------------------+EVENT TIME: 16:20[EST]|
| NRC NOTIFIED BY: JEFF EPPERSON |LAST UPDATE DATE: 12/26/2002|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |STEPHEN CAHILL R2 |
|10 CFR SECTION: |GENE IMBRO NRR |
|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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RPS ACTUATION FOLLOWED BY AUTOMATIC REACTOR TRIP |
| |
| "At 16:20 EST, Unit 2 #3 Reactor Coolant Pump Tripped due to actuation of |
| its 6.9 KV Circuit Breaker's Toroidal Ground Relay (Device 50G). The trip of |
| the RCP resulted in an automatic reactor trip from 100% rated thermal |
| power. |
| |
| "All support equipment operated as designed. No primary or secondary safety |
| valves opened. The Unit is stable. Mode 3 conditions are being maintained." |
| |
| The reactor was shutdown with all control rods fully inserted. The remaining |
| 3 RCPs are in operation and transferring decay heat to the steam |
| generators. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE FROM MITCH TAGGART TO ARLON COSTA ON 12/26/02 AT 21:43 * * * |
| |
| Actuation of RPS System (Reactor Trip) and Auxiliary Feedwater as expected |
| from reactor trip in accordance with 10CFR50.72(b)(3)(iv)(A)(1) RPS and (6) |
| Auxiliary Feedwater. |
| |
| The Licensee will notify the NRC Resident Inspector. |
| |
| The Headquarters Operations Officer notified NRC R2DO (Stephen Cahill) |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021