Event Notification Report for September 7, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/06/2000 - 09/07/2000
** EVENT NUMBERS **
37253 37289 37293 37294 37295 37296
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37253 |
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 08/24/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 05:27[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/24/2000|
+------------------------------------------------+EVENT TIME: 04:35[EDT]|
| NRC NOTIFIED BY: SQUIRES |LAST UPDATE DATE: 09/06/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: |CHARLES MILLER IRO |
|AINT 50.72(b)(1)(vi) INTERNAL THREAT |TAD MARSH NRR |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |53 Power Operation |
| | |
| | |
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EVENT TEXT
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| SMOKE AND SMALL FLAMES FROM "B" REACTOR FEED PUMP (RFP) OUTBOARD BEARING. |
| FIRE LESS THAN 15 MINUTES. |
| |
| Control room plant received a high bearing temperature alarm from the "B" |
| RFP. Plant personnel were dispatched to investigate. Smoke and small flames |
| were seen around the outboard bearing of "B" RFP. Onsite fire brigade was |
| dispatched to extinguish the fire. Fire brigade was unsuccessful in |
| extinguishing the fire using carbon dioxide. Fire was extinguished using a |
| fire hose. No other electrical systems were wetted by the fire hose. |
| Reactor power was reduced from 100% to approximately 53% power at which time |
| the "B" RFP was taken out service. A reflash fire watch is stationed at the |
| "B" RFP. Lagging has been removed from the RFP and the lagging where the |
| smoke and fire issued from is oil soaked. Investigation of fire is in |
| progress. Unnecessary personnel were evacuated from the area of the fire. |
| "B" RFP is located in the Turbine Building lower level (252'). All |
| Emergency Core Cooling Systems are fully operable except for HPCI (see event |
| # 37252). Offsite electrical grid is stable. No offsite site help was |
| needed. Fire lasted from 0435 ET until 0449 ET. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1348 EDT ON 9/6/00 BY BOB STEIGERWALD TO FANGIE JONES * * |
| * |
| |
| "This notification retracts an earlier report made on 08/24/00, at 05:27 |
| (EDT), per 10CFR50.72(b)(1)(vi). A fire was reported at the outboard bearing |
| of the 'B' Reactor Feed Pump. The fire was minor in nature, limited to the |
| 'B' feed pump room, extinguished within 15 minutes of discovery, and did not |
| hamper the ability of personnel to perform safety-related activities |
| affecting plant safety. Reactor power was reduced and the 'B' feed pump was |
| removed from service. Therefore, this event notification is being |
| retracted." |
| |
| The licensee notified the NRC Resident Inspector. The R1DO (Anthony |
| Dimitriadis) was notified. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37289 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/05/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 05:42[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/05/2000|
+------------------------------------------------+EVENT TIME: 02:00[EDT]|
| NRC NOTIFIED BY: R.T. ELLIOT |LAST UPDATE DATE: 09/06/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| "2B" AUXILIARY FEEDWATER (CA) PUMP RAN 2 HOURS AND 55 MINUTES BEFORE BEING |
| DISCOVERED IT WAS OPERATING. STEAM GENERATORS WERE ISOLATED FROM THE AFW |
| SYSTEM. |
| |
| At 0200 ET the "B" Train of the Solid State Protection System (SSPS) was |
| deenergized for part of their refueling outage maintenance. When the SSPS |
| was deenergized the blocks for the Main Feedwater Pump blocks cleared, which |
| resulted in an automatic start signal to the "2B" AFW pump. The on shift |
| reactor operator did not notice the "2B" AFW pump run light was on until |
| 0455 ET due to refueling outage maintenance activities in Control Room. The |
| "2B" AFW pump recirculated water to the Upper Surge Tank since the Steam |
| Generators were isolated. No damage occurred to the AFW pump. The licensee |
| is investigating this event. |
| |
| The NRC Resident Inspector will be notified of this event. |
| |
| * * * RETRACTED AT 1630 EDT ON 9/6/00 BY LARRY TUMBLESON TO FANGIE JONES * * |
| * |
| |
| "Further investigation has determined that, prior to and during the |
| automatic start, the 2B CA Pump had been properly removed from service. This |
| was accomplished when valves that isolate flow from the pump to the Unit 2 |
| Steam Generators were closed as a result of planned Unit 2 shutdown |
| operations using plant procedures. In addition, the automatic start of the |
| 2B CA Pump was not the result of a valid ESF actuation intended to mitigate |
| the consequences of an event. Instead, the ESF actuation signal which |
| started the pump upon reset of the SSPS relay was present because the MFP's |
| were already off as a result of planned refueling outage shutdown |
| operations. |
| |
| "Based upon the above, the September 5, 2000, automatic start of the 2B CA |
| Pump occurred as a result of an invalid ESF actuation signal received while |
| the pump was properly removed from service. Consequently, this is not |
| reportable under the requirements of 10 CFR 50.72(b)(2)(ii) - Actuation of |
| An Engineered Safety Feature (ESF) and NRC Notification 37289 is retracted. |
| |
| "The Resident Inspector has been notified." |
| |
| The R2DO (Mark Lessor) has been notified. |
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|Power Reactor |Event Number: 37293 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/06/2000|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 12:13[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/06/2000|
+------------------------------------------------+EVENT TIME: 08:45[CDT]|
| NRC NOTIFIED BY: W. MOOKHOEK |LAST UPDATE DATE: 09/06/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| VITAL BUS SUPPLY BREAKER FOUND TO HAVE IMPROPER TRIP SETTING AFFECTING |
| OPERABILITY |
| |
| "On August 29, 2000, at 0038 CDT, Unit 2 experienced a loss of power to |
| Class 1 E 480v motor control center (MCC) E2C1. The power loss resulted in a |
| loss of normal letdown in the Chemical Volume Control System and loss of |
| other safety related loads. The MCC was re-energized at 0108 CDT and plant |
| systems were restored to normal. |
| |
| "An investigation found the long time overload settings for the feeder |
| breaker to MCC E2C1 to be one-half of the required values. The condition had |
| existed since October 23, 1999, when the breaker was placed in service. At |
| 0845 on September 6, 2000, this condition was determined to be reportable |
| after completion an engineering evaluation. The engineering evaluation |
| determined that the breaker had a high potential for opening under accident |
| conditions because of the improper settings. The condition was corrected on |
| August 29, 2000, at 1806 CDT. The corresponding breakers in the other ESF |
| trains and in Unit 1 were found to have the correct settings. |
| |
| "Some safety related equipment powered from the MCC was determined to have |
| been inoperable since October 23, 1999, because opening of the breaker would |
| have interrupted the equipment's ability to perform its |
| design function. The duration of inoperability exceeded the Technical |
| Specification allowed outage time for some systems, which include: |
| - 1 of 3 trains of Essential Chilled Water (TS 3/4.7.14): inoperable |
| essential chilled water pump 21C |
| - 1 of 3 trains of Control Room Envelope HVAC (TS 3/4.7.7): inoperable |
| makeup fan 21C |
| - 1 of 3 Standby Diesel Generators (TS 3/4.8.1): inoperable emergency supply |
| fan 21C (support system for SDG 23) |
| |
| "This condition is reportable under 10CFR50.73(a)(2)(i)(B) and notification |
| is required within 24 hours by Section 2G of the Unit 2 Operating License |
| (NPF-80)" |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37294 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: PHILIP MORRIS |NOTIFICATION DATE: 09/06/2000|
|LICENSEE: PHILIP MORRIS |NOTIFICATION TIME: 15:42[EDT]|
| CITY: RICHMOND REGION: 2 |EVENT DATE: 06/01/2000|
| COUNTY: STATE: VA |EVENT TIME: [EDT]|
|LICENSE#: 45-00385-06 AGREEMENT: N |LAST UPDATE DATE: 09/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONALD IRWIN | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SHUTTER ON SCANNER DISABLED ON CONVEYOR LINE |
| |
| A small piece of lead fell off the inside of a shield for a sealed beam |
| source which prohibited the full closure of the shutter on the source. |
| There was no exposure to personnel and repairs will be made by Philip |
| Morris. This was discovered on 6/1/00 during a normal inventory of sources. |
| It wasn't known to be reportable until today. The scanner is used to |
| monitor cartons for missing packs of cigarettes. It is manufactured by |
| Industrial Dynamics, model FT14, with two 100 mCi Am-241 sources. |
| |
| The company also notified NRC Region 2 (Orysia Bailey) |
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|Other Nuclear Material |Event Number: 37295 |
+------------------------------------------------------------------------------+
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| REP ORG: R.D. ZANDE & ASSOCIATES |NOTIFICATION DATE: 09/06/2000|
|LICENSEE: R.D. ZANDE & ASSOCIATES |NOTIFICATION TIME: 15:45[EDT]|
| CITY: KYSER REGION: 2 |EVENT DATE: 09/06/2000|
| COUNTY: GRANT STATE: WV |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 09/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |GARY SHEAR R3 |
+------------------------------------------------+E. WILLIAM BRACH NMSS |
| NRC NOTIFIED BY: JOE STOCK | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NDAM DAMAGED GAUGE/DEVICE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| TROXLER GAUGE DAMAGED BY TRUCK RUNNING OVER IT |
| |
| R.D. Zande and Associates (of Columbus, OH) was conducting a back scatter |
| test on asphalt on State Route 220 in Kyser, WV when an asphalt truck backed |
| over it. The gauge is a Troxler Model 3411 with a cesium source. The case |
| was damaged , case cracked, and the extension rods were damaged. The source |
| was extended at the time and not believed to be damaged. The source was |
| recovered into the shielded position. The gauge will be transported to |
| Cline Technical Services in Amanda, Ohio, will be wipe tested there and |
| final disposition of the gauge will be determined. |
| |
| The company has contacted NRC Region 3 (John Madera and Sam Mulea). |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 37296 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 09/06/2000|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 18:38[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/06/2000|
+------------------------------------------------+EVENT TIME: 16:21[CDT]|
| NRC NOTIFIED BY: ERNEST MATHES |LAST UPDATE DATE: 09/06/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DURING SURVEILLANCE AN AUTOMATIC ISOLATION SIGNAL WAS GENERATED DUE TO |
| MISSED SWITCH POSITIONING |
| |
| "Reactor Core Isolation Cooling (RCIC) system isolated during performance of |
| Annual Leak Detection surveillance (06-IC-A-1003-02). Investigation |
| revealed leak detection switches not in bypass during test. System |
| responded as designed. ES1-F064 (Mn Steam isolation) and trip Throttle |
| valve closed. System restored to standby." |
| |
| The licensee determined there was a missed step in the surveillance |
| procedure. |
| |
| The licensee notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021