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Event Notification Report for October 9, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/08/2002 - 10/09/2002

                              ** EVENT NUMBERS **

39229  39244  39256  39257  39258  39259  39260  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   39229       |
+------------------------------------------------------------------------------+
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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 09/29/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 13:11[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/29/2002|
+------------------------------------------------+EVENT TIME:        05:02[EDT]|
| NRC NOTIFIED BY:  HOFFMAN                      |LAST UPDATE DATE:  10/08/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |GEORGE MCDONALD      R2      |
|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     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP SIGNAL DUE TO LOW-LOW STEAM GENERATOR LEVEL.                    |
|                                                                              |
| While draining the 1"D" steam generator, a reactor trip signal was generated |
| due to a low-low steam generator level.  One train of the reactor protection |
| system was being tested, so one trip breaker opened in response to the trip  |
| signal.  The low-low steam generator level was due to a planned evolution    |
| and was a valid signal.  There was no safety significance because all        |
| control rods were already inserted into the fuel assemblies, the control     |
| rods were not latched to the control rod drive system, and the motor         |
| generator sets were shutdown by procedure.  Although the reactor trip        |
| breaker was closed during testing, at no point was control rod withdrawal    |
| possible.  They are investigating the cause.                                 |
|                                                                              |
| The NRC Resident Inspector will be notified                                  |
|                                                                              |
| **** RETRACTION ON 8/28/02 @08:58 BY THAD REAMES  TO ARLON COSTA ****        |
|                                                                              |
| "On September 29, 2002, McGuire Nuclear Station notified the NRC of an       |
| inadvertent actuation of the Unit. 1 reactor protection system (RPS) while   |
| the unit was shutdown for a refueling outage. This occurred when reactor     |
| trip breakers unexpectedly opened as a result of a low-low steam generator   |
| level reactor trip signal. This event was reported as a valid actuation of   |
| the RPS in accordance with 10 CFR 50.72(b) (3) (iv) (A). Reference Event     |
| Report 39229.                                                                |
|                                                                              |
| Further evaluation determined that the reactor trip signal which opened the  |
| reactor trip breakers was an invalid signal since it was not initiated in    |
| response to plant conditions or parameters satisfying the requirements for   |
| initiation of the RPS safety function. Therefore, this represented an        |
| invalid actuation which is not reportable per 10 CFR 5Q.72(b)(3)(iv)(A). As  |
| a result, McGuire is retracting Event Report 39229. Note that McGuire will   |
| report this event in accordance with the requirements of 10CFR 50.73."       |
|                                                                              |
| The Licensee will notify the NRC Resident Inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39244       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 10/03/2002|
|LICENSEE:  JIM TAYLOR                           |NOTIFICATION TIME: 09:35[EDT]|
|    CITY:  STOCKTON                 REGION:  4  |EVENT DATE:        10/01/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:        09:30[PDT]|
|LICENSE#:  4900                  AGREEMENT:  Y  |LAST UPDATE DATE:  10/03/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  R. GREGER                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING CPN GAUGE                                                            |
|                                                                              |
| The Licensee had a CPN moisture density gauge in a box of his ATV he uses    |
| for transport in the agriculture fields.  He stopped at a porta-potty on     |
| Duncan Road near Stockton, CA.  When he came out of the porta potty the      |
| gauge was missing.                                                           |
|                                                                              |
| The gauge is a CPN Hydroprobe model No. 503DR. Serial No: H36107151.  Gauge  |
| contains 10 millicuries of Cs-137 and 30 millicuries of Am-241.              |
|                                                                              |
| The Licensee will inform the local police of the missing gauge and he will   |
| run an offer of a reward in a local newspaper for the recovery of the gauge. |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39256       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 10/08/2002|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 07:22[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        10/08/2002|
+------------------------------------------------+EVENT TIME:        04:21[CST]|
| NRC NOTIFIED BY:  BRUCE FRANZEN                |LAST UPDATE DATE:  10/08/2002|
|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       15       Power Operation  |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| T. S. REQUIRED SHUTDOWN DUE TO PRESSURE BOUNDARY LEAKAGE                     |
|                                                                              |
| "During drywell entry prior to D3R17 refueling outage discovered primary     |
| system leak on 3A Reactor Recirculation pump discharge loop flow instrument  |
| line, this required entry into T.S. 3.4.4 which requires that there is No    |
| pressure boundary leakage. This requires that the unit be in MODE 3 in 12    |
| hours and MODE 4 in 36 hours, which is a TS required shutdown."              |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39257       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 10/08/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 09:03[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/29/2002|
+------------------------------------------------+EVENT TIME:        05:02[EDT]|
| NRC NOTIFIED BY:  THAD REAMES                  |LAST UPDATE DATE:  10/08/2002|
|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GEORGE MCDONALD      R2      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RPS ACTIVATION WHILE SHUTDOWN DUE TO LO-LO STEAM GENERATOR WATER LEVEL       |
|                                                                              |
| "On September 29, 2002, McGuire Nuclear Station experienced an inadvertent   |
| actuation of the Unit 1 reactor protection system (RPS) while the unit was   |
| shutdown for a refueling outage. This occurred when the "A" and "B" train    |
| main reactor trip breakers opened as a result of an unplanned low-low steam  |
| generator level reactor trip signal.                                         |
|                                                                              |
| Further evaluation determined that the reactor trip signal which opened the  |
| reactor trip breakers was an invalid signal since it was not initiated in    |
| response to plant conditions or parameters satisfying the requirements for   |
| initiation of the RPS safety function. Therefore, this represented an        |
| invalid actuation reportable per the requirements of 10 CFR                  |
| 50.73(a)(2)(iv)(A). However, as per 10 CFR 50.73(a) (1), McGuire is          |
| providing a telephone notification of this invalid actuation instead of      |
| submitting a written LER.                                                    |
|                                                                              |
| The following additional information is being provided as part of the        |
| telephone notification of this event:                                        |
|                                                                              |
| -The Unit 1 RPS system including the "A" and "B" train main reactor trip     |
| breakers functioned successfully and completely."                            |
|                                                                              |
| The Licensee will notify the NRC Resident Inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39258       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 10/08/2002|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 15:20[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        10/05/2002|
+------------------------------------------------+EVENT TIME:             [CDT]|
| NRC NOTIFIED BY:  Chris Garbe                  |LAST UPDATE DATE:            |
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |
|10 CFR SECTION:                                 |CHRIS GRIMES         NRR     |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEGRADATION OF RCS PRESSURE BOUNDARY AT ARKANSAS NUCLEAR ONE UNIT 1          |
|                                                                              |
| "With the Reactor Coolant System (RCS) In Mode 3 (Hot Standby) conditions at |
| the start of a scheduled refueling outage on October 5, 2002, a leaking weld |
| was discovered at the connection of a drain line to a High Pressure          |
| Injection (HPI) line inside the Reactor Building. The leak rate was          |
| approximately 0.2 gpm. The immediate evaluation concluded that this leak did |
| not result in the HPI System being inoperable. Subsequent evaluation of the  |
| condition on October 8, 2002. determined that the leak was from the RCS      |
| pressure boundary. Between the RCS and leak location are a normally open     |
| manual isolation valve and a check valve. Weld repair is complete. This      |
| condition is being reported as a serious degradation of a principal safety   |
| barrier in accordance with 10CFR5O.72(b)(3)(ii)(A)."                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39259       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 10/08/2002|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 16:57[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        10/08/2002|
+------------------------------------------------+EVENT TIME:        13:30[EDT]|
| NRC NOTIFIED BY:  LEONE                        |LAST UPDATE DATE:  10/08/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| THE CENTRAL CONTROL ROOM WALL IDENTIFIED AS BEING IN NON-CONFORMANCE WITH    |
| DESIGN DRAWINGS                                                              |
|                                                                              |
| Indian Point Energy Center (Unit .2) is making an eight hour non-emergency   |
| notification in accordance with 10 CFR 50.72(b)(3)(v)(D).  The Central       |
| Control Room (CCR) south masonry wall was identified as inoperable because a |
| seismic event could cause breaches in the wall that could prevent the        |
| Control Room Air Filtration System from performing its design function of    |
| limiting operator dose.                                                      |
|                                                                              |
| The as found condition of the CCR south wall was identified as being in      |
| non-conformance with the design drawings.   At the top portion of the wall,  |
| just above the upper steel channel beam, there are steel angles welded to    |
| the lower cord of the CCR roof truss that extend about 1.5 feet towards the  |
| south wall.   A shelf angle is welded to the ends of the angles that support |
| part of the south wall.   This as found condition creates a seismic          |
| interaction with the superheater building which transfers load to the south  |
| wall through the steel support.   Initial analysis indicates that the CCR    |
| south wall will remain structurally intact except for several areas in the   |
| upper 6 feet of the wall where localized failure could occur.  The analysis  |
| indicates these localized failures will not cause damage to safety related   |
| equipment but may cause loss of the CCR pressure boundary.  Corrective       |
| action has been initiated to repair the south masonry wall locally and cut   |
| the steel causing building interaction between the superheater and control   |
| buildings.  Corrective action is expected to be complete within              |
| approximately 24 hours.                                                      |
|                                                                              |
| Loss of the CCR pressure boundary renders the Control Room Air Filtration    |
| System incapable of performing its safety function because it relies on the  |
| pressure boundary to limit in-leakage.   The Control Room Air Filtration     |
| System was declared inoperable and the action statement of Technical         |
| Specification 3.3.H was entered at 1330 hours.  The action statement allows  |
| 3.5 days of continued operation.                                             |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39260       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 10/09/2002|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 03:31[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/09/2002|
+------------------------------------------------+EVENT TIME:        03:07[EDT]|
| NRC NOTIFIED BY:  LOU GAREAU                   |LAST UPDATE DATE:  10/09/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |NADER MAMISH         IRO     |
|                                                |JIM DUNKER           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 DUE TO FIRE IN PROTECTED AREA LASTING GREATER THAN 10 |
| MINUTES                                                                      |
|                                                                              |
| "Unusual event was classified based on a fire in the protected area lasting  |
| > 10 minutes.  The fire started in the motor of the 'B' circulating water    |
| pump.  It was 'contained' to that location (the CW pump motor).  Motor       |
| [is]still smoldering, [but] it is controlled and contained.  Steam Generator |
| Blowdown system isolated due to high flash tank level.  Multiple rad         |
| monitors went into alarm due to voltage surge."                              |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| The Licensee reported that no offsite assistance was requested and that the  |
| State (NH) was notified.                                                     |
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