U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/27/2003 - 01/28/2003
** EVENT NUMBERS **
39480 39538 39540
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39480 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 12/31/2002|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 01:34[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 12/30/2002|
+------------------------------------------------+EVENT TIME: 20:10[CST]|
| NRC NOTIFIED BY: JAMES McKAY |LAST UPDATE DATE: 01/27/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
|AINC 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| MONTICELLO INITIATED TS REQUIRED PLANT SHUTDOWN DUE TO INOPERABILITY OF BOTH |
| EDGs |
| |
| "With #12 EDG inoperable due to a maintenance issue [on 12/29/02 at 2330 |
| CST] , it is required to test #11 EDG within 24 hours. Testing causes #11 |
| EDG to be inoperable, therefore both EDGs are inoperable requiring [the |
| initiation of] a plant shutdown per T.S. 3.9.B.3.a.2 and a non-emergency |
| notification per 10 CFR 50.72/8 hour. #11 EDG subequently tested operable |
| and the plant exited T.S. shutdown requirement at 2300 on 12/30/02." |
| |
| The licensee stated that the period of time both EDGs were inoperable was |
| from 2010 to 2300 on 12/30/02. The inoperablity of the #12 EDG was due to |
| an equipment problem with the DC fuel oil pump. After fixing the DC fuel |
| oil pump on the #12 EDG, the EDG was restarted and the "failure-to-start" |
| alarm lit and the "cranking" alarm lit and stayed in for 5 minutes. The |
| licensee is currently evaluating these problems. The #12 EDG remains in a 7 |
| day limiting LCO action statement. The #11 EDG started and tested |
| satisfactorily with no problems. The inoperability of the #11 EDG was due to |
| some of the set up conditions for testing when the EDG is considered to be |
| inoperable per procedure. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * RETRACTED ON 1/27/03 AT 1714 EST BY DAVID BARNETT TO GERRY WAIG * * * |
| |
| |
| "On 12/29/02 at 2330 CST, the Monticello nuclear power plant notified the |
| NRC operations center of the #12 EDG being declared inoperable when |
| personnel noted an equipment problem during surveillance testing. In |
| addition, the #11 EDG was declared inoperable due to station Technical |
| Specification required surveillance testing to prove operability of the #11 |
| EDG while the #12 EDG was inoperable. The report was made pursuant to |
| 10CFR50.72(b)(3)(v) under Event Notification number 39480. |
| |
| "Upon further review, Monticello is retracting the event reported based on |
| the information in NUREG-1022, Rev. 2, page 56, which states, 'The following |
| types of events or conditions generally are not reportable under these |
| conditions. Sub-item 3 states: removal of a system or part of a system from |
| service as part of a planned evolution for maintenance or surveillance |
| testing when done in accordance with an approved procedure and the plant's |
| TS (unless a condition is discovered that could have prevented the system |
| from performing its function).' |
| |
| "The station condition reported in Event Report #39480 was determined not to |
| be reportable based on the following: |
| 1) #11 EDG was inoperable due to the performance of a surveillance test in |
| accordance with the station's Technical Specifications and an approved |
| procedure; and |
| 2) #11 EDG successfully passed the surveillance test to prove operability. |
| Additionally, the required TS LCO action statement requiring plant shutdown |
| was entered. The appropriate procedure was entered. However the station was |
| not required to reduce power or initiate shutdown by inserting negative |
| reactivity and additionally the shutdown was not imminent, since the #11 EDG |
| was confirmed to be operable." |
| |
| The licensee has notified the NRC Resident Inspector, State of Minnesota, |
| and Local Government of this retraction. |
| |
| Notified R3DO (Mark Ring) |
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|Power Reactor |Event Number: 39538 |
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| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 01/27/2003|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 10:05[EST]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 01/27/2003|
+------------------------------------------------+EVENT TIME: 08:44[EST]|
| NRC NOTIFIED BY: JEFF DEAL |LAST UPDATE DATE: 01/27/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| UNIT 3 MANUALLY TRIPPED DUE TO LOW STEAM GENERATOR LEVELS |
| |
| The following information was submitted via facsimile: |
| |
| "Manual reactor trip on Unit 3 due to low steam generator levels caused by a |
| loss of instrument air pressure. Instrument air pressure has been |
| restored." |
| |
| Operators manually tripped Unit 3 following the loss of instrument air (IA) |
| pressure which resulted in closing of the main feedwater regulating valves. |
| IA can be supplied from one of four compressors; two motor driven and two |
| diesel driven. When the operating motor driven air compressor breaker |
| tripped, both diesel driven compressors received a start signal (the other |
| motor driven compressor had been previously removed from service). One of |
| the diesel driven compressors failed to start while the other started and |
| tripped. IA pressure was restored by manually starting one of the diesel |
| units. The licensee has the cause of the IA loss under investigation. |
| |
| Following the manual reactor trip, all three turbine driven auxiliary |
| feedwater pumps started as expected. The licensee is in the process of |
| restoring normal feedwater and returning the auxiliary feedwater pumps to |
| standby. The atmospheric steam dumps are currently in service to remove |
| decay heat (no known primary-secondary leakage). All control rods fully |
| inserted. |
| |
| The licensee will notify the resident inspector and does not plan a press |
| release. |
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|Power Reactor |Event Number: 39540 |
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| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 01/27/2003|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 17:40[EST]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 01/22/2003|
+------------------------------------------------+EVENT TIME: 21:51[CST]|
| NRC NOTIFIED BY: HAROLD VINYARD |LAST UPDATE DATE: 01/27/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK RING R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
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EVENT TEXT
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| INVALID AUTOMATIC START OF EMERGENCY DIESEL GENERATOR DURING TESTING |
| |
| "On January 22, 2003, at 2045 hours, with Unit 2 in Mode 5 (refuel), the 2B |
| Emergency Diesel Generator (DG) automatically started during the performance |
| of a Unit 2 High Pressure Excess Flow Check Valve Operability Test. The |
| apparent cause was an improper manipulation of instrument isolation valves |
| during the test, which caused the associated Reactor Vessel Water Level |
| Transmitters to sense a low level condition. This invalid low level signal |
| resulted in the automatic actuation of the 2B DG (Div. III) which is the |
| emergency power supply to the Unit 2 High Pressure Core Spray (HPCS) System. |
| The Unit 2 HPCS pump had been properly removed from service prior to the |
| event and therefore did not actuate. This system actuation is reportable |
| under 10CFR50.73 (a) (2) (iv) (A). |
| |
| "The 2B DG responded normally and reached normal speed and voltage. It was |
| run both loaded and unloaded successfully, and was secured at 0238 on |
| January 23, 2003. |
| |
| "This report is being made in accordance with 10CFR50.73 (a) (1), which |
| states that in the case of an invalid actuation reported under |
| 10CFR50.73(a)2)(iv), other than an actuation of the RPS when the reactor is |
| critical, the licensee may provide a telephone notification to the NRC |
| operations center within 60 days after discovery of the event Instead of |
| submitting a written LER." |
| |
| The licensee notified the NRC resident inspector. |
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