Event Notification Report for March 6, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/05/2002 - 03/06/2002
** EVENT NUMBERS **
38610 38634 38732
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38610 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/06/2002|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 08:43[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 01/06/2002|
+------------------------------------------------+EVENT TIME: 05:15[CST]|
| NRC NOTIFIED BY: HUBBARD |LAST UPDATE DATE: 03/05/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 |
|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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| EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE |
| |
| At 1347 on 1/4/2002, the "A" emergency diesel generator (EDG) was declared |
| inoperable due to tube degradation identified in the lube oil, intercooler |
| and jacket water heat exchangers. Technical Specification 3.8.1 was |
| entered, the affected heat exchanger tubes were plugged and the "A" EDG was |
| restored to operable status at 1134 on 1/5/2002. |
| |
| At 1301 on 1/5/2002, the "B" EDG was taken out of service to perform |
| inspections of its lube oil, intercooler, and jacket water heat exchangers. |
| Inspection of the heat exchanger tubes and analysis of the inspection data |
| found similar results, subsequently resulting in the need to plug heat |
| exchanger tubes to restore the "B" EDG to operable status. |
| |
| Based upon the similarity and extent of the tube degradation in both the "A" |
| and "B" EDG heat exchangers, prior to implanting the tube plugging |
| corrective action, the possibility exists that the degradation of the EDG |
| heat exchangers' tubes could have prevented the fulfillment of the safety |
| function of the onsite standby class 1E power source following a design |
| basis earthquake. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE ON 01/06/02 AT 1927 EST BY HUBBARD TAKEN BY MACKINNON * * * |
| |
| "B" EDG was restored to operable status. R4DO (B. Spitzberg) notified. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * RETRACTED AT 1826 EST ON 3/5/02 BY STEVE HENRY TO FANGIE JONES * * * |
| |
| Subsequent evaluation of the heat exchangers by the licensee determined that |
| the degradation was not severe enough to interfere with the proper operation |
| of the EDGs. The licensee is retracting the event notification, as the EDGs |
| were operational and fully available. |
| |
| The licensee notified the NRC Resident Inspector. The R4DO (Linda Smith) |
| was notified. |
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|Power Reactor |Event Number: 38634 |
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| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 01/17/2002|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 13:07[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 01/17/2002|
+------------------------------------------------+EVENT TIME: 11:45[EST]|
| NRC NOTIFIED BY: KELLY KORTH |LAST UPDATE DATE: 03/05/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION INVOLVING RECOVERED SEA TURTLE FROM INTAKE CANAL
|
| |
| At approximately 1130 EST on 01/17/02, a green sea turtle was retrieved from |
| the intake canal and a determination was made that it was in need of |
| rehabilitation. As required by the Plant's Sea Turtle Permit, the Florida |
| Fish and Wildlife Conservation Commission (FFWCC) was notified at 1145 EST. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| See EN #38513 for 2001 occurrences. |
| |
| * * * UPDATE ON 1/28/02 @ 1243 BY KORTH TO GOULD * * * |
| |
| At approximately 1115 on 1/28/02 a loggerhead turtle was retrieved from the |
| plant's intake canal. The turtle was determined to be in need of |
| rehabilitation. Per the licensee's turtle permit, the Florida Fish and |
| Wildlife Conservation Commission (FWCC) was notified at 1125. |
| |
| The NRC Resident Inspector was notified. Notified Reg 2 RDO (Ninh) |
| |
| * * * UPDATE ON 2/6/02 @ 0853 BY MERRILL TO GOULD * * * |
| |
| At approximately 0745 on 2/6/02 an injured green sea turtle was rescued from |
| the plant's intake canal. The turtle was alive, but in need of |
| rehabilitation. The turtle will be transported to a facility in Clearwater |
| for treatment. The Florida Department of Environmental Protection has been |
| notified of the event. |
| |
| The NRC Resident Inspector was notified. |
| |
| Notified Reg 2 RDO(Fredrickson) |
| |
| * * * UPDATE 1025 3/2/2002 BY R. DIEHL TAKEN BY R. STRANSKY * * * |
| |
| "At approximately 0830 3/2/02 a Loggerhead turtle was retrieved from the |
| plant's intake canal. The turtle was determined to be in need of |
| rehabilitation. Per the plant's turtle permit, the Florida Fish and Wildlife |
| Conservation Commission (FWCC) was notified at 0845." |
| |
| The NRC resident inspector has been informed of this report. HOO notified |
| R2DO (Julian). |
| |
| * * * UPDATE 1040EST ON 3/5/02 FROM GEORGE TULLIDGE TO S. SANDIN * * * |
| |
| "At Approximately 1000 on 3/5/02, a Loggerhead turtle was retrieved from the |
| plant intake canal. The turtle was determined to be in need of |
| rehabilitation. Per the plant's turtle permit, the Florida Fish and |
| Wildlife Conservation Commission (FWCC) was notified." |
| |
| The NRC resident inspector has been informed of this report. HOO notified |
| R2DO (Julian). |
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|Power Reactor |Event Number: 38732 |
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| FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 02/27/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 15:42[EST]|
| RXTYPE: [1] B&W-R-LP |EVENT DATE: 02/27/2002|
+------------------------------------------------+EVENT TIME: 13:30[EST]|
| NRC NOTIFIED BY: DALE MILLER |LAST UPDATE DATE: 03/05/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHRISTINE LIPA R3 |
|10 CFR SECTION: |TOM KOSHY NRR |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION |JOSEPH HOLONICH IRO |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| IDENTIFICATION OF AXIAL THROUGH-WELD INDICATIONS (REACTOR COOLANT
SYSTEM |
| PRESSURE BOUNDARY LEAKAGE) ON ONE CONTROL ROD DRIVE MECHANISM
NOZZLE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On February 26, 2002, following shutdown for a scheduled refueling outage, |
| the Davis-Besse Nuclear Power Station performed a qualified visual |
| examination of the Reactor Vessel head per NRC Bulletin 2001-01. This |
| examination revealed evidence of boric acid build up around Control Rod |
| Drive Mechanism (CRDM) nozzles but was inconclusive due to the previous |
| known boric acid deposits. At approximately 1330 hours on February 27, |
| 2002, Ultrasonic Testing (UT) data identified axial through weld indications |
| on one CRDM. Engineering evaluation of this data confirmed Reactor Coolant |
| System pressure boundary leakage exists. Technical Specification 3.4.6.2.a |
| states that Reactor Coolant System leakage shall be limited to no pressure |
| boundary leakage. As a result this is being reported as a non-emergency, |
| 8-hour report in accordance with 10CFR50.72(b)(3)(ii)(a), a condition that |
| resulted in the nuclear power plant, including its principal safety barriers |
| being seriously degraded." |
| |
| The licensee stated that UT inspections are continuing on other nozzles. |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| * * * UPDATED AT 1921 EST ON 3/5/02 BY TERRY PLOEGER TO FANGIE JONES * * * |
| |
| "All inspections have been completed at this time. UT data for CRDM nozzles |
| 1 and 2 (locations H-8 and G-7, respectively) has been evaluated to exhibit |
| axial indications that represent pressure boundary leakage. This completes |
| evaluation of the extent of the condition for the report communicated on |
| February 27." |
| |
| The licensee notified the NRC Resident Inspector. The R3DO (John Madera), |
| NRR EO (David Matthews), and IRO (Tim McGinty) have been informed. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021