United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2002

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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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)       |
+------------------------------------------------------------------------------+