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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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. |
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|General Information or Other |Event Number: 39244 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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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