Event Notification Report for August 24, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/23/2000 - 08/24/2000
** EVENT NUMBERS **
37248 37249 37250 37251 37252 37253
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|Power Reactor |Event Number: 37248 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 08/23/2000|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 02:30[CDT]|
| NRC NOTIFIED BY: MIKE HAUNER |LAST UPDATE DATE: 08/23/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(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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| BOTH RIVER WATER SUPPLY SYSTEMS WERE DECLARED INOPERABLE. |
| |
| At 0230 the River Water Supply (RWS) instrument air system failed resulting |
| in an invalid low RWS pit level alarm. Operators restored system air |
| pressure at 0243. The loss of instrument air pressure also resulted in the |
| loss of automatic traveling screen control and the screen high differential |
| level alarm function. Because both of the automatic traveling screen wash |
| systems were inoperable, both RWS systems were declared inoperable for the |
| 13 minute duration. Failure of both systems resulted in a loss of safety |
| function (supplies water to the Residual Heat Removal Service Water Pumps |
| and the Emergency Service Water System). The licensee entered the applicable |
| Technical Specifications for the loss of the RWS system. A new air dryer |
| was installed recently and when the operator cycled the power supply to the |
| air dryer it hung up. This caused the Instrument Air blockage. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE 1102 FROM BRIAN VOSS TAKEN BY STRANSKY * * * |
| |
| The licensee made the following corrections to the event report: (1) the |
| operator cycled the power supply to the compressor after it stopped, not |
| before, as noted above; and (2) there was no instrument air blockage, as |
| stated above. Notified R3DO (Hiland). |
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|Power Reactor |Event Number: 37249 |
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| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 08/23/2000|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 16:31[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 15:10[EDT]|
| NRC NOTIFIED BY: TOM O'MEARA |LAST UPDATE DATE: 08/23/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) 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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| - MD Department of Environment to be notified of high coliform levels in |
| visitor's center domestic water system - |
| |
| The licensee plans to notify the Maryland Department of Environment that |
| high coliform levels were discovered in the Calvert Cliffs visitor's center |
| domestic water system. The licensee isolated the system and provided |
| portable water to the visitor's center. The licensee plans to re chlorinate |
| the water system and resample the system prior to restoring it to service. |
| |
| |
| The licensee plans to notify the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37250 |
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| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 08/23/2000|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 16:57[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 16:04[EDT]|
| NRC NOTIFIED BY: CALVIN WARD |LAST UPDATE DATE: 08/23/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - PUBLIC NOTIFICATION SIRENS INOP FOR 20 MINUTES DUE TO TRIPPED POWER SUPPLY |
| BREAKER - |
| |
| At 1604 on 08/23/00, the licensee was notified that the Saint Lucie public |
| notification sirens were inoperable from 1445 to 1505 due to a tripped power |
| supply circuit breaker. The sirens are now fully operable. All other |
| emergency notification system, emergency assessment, and state notification |
| equipment remained operable during this event. The licensee is investigating |
| the cause of the tripped breaker. |
| |
| The licensee notified local officials and the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37251 |
+------------------------------------------------------------------------------+
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/23/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 18:22[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: BOB KIDDER |LAST UPDATE DATE: 08/23/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - ECC SYSTEM MOV MAY NOT CLOSE DURING A LOCA AND A LOOP AS REQUIRED - |
| |
| While reviewing motor operated valve (MOV) data from December, 1999, plant |
| staff personnel identified an error in the analyzed data for the closing |
| torque for an MOV in the Emergency Closed Cooling (ECC) System that is |
| required to close during a Loss of Coolant Accident (LOCA) and a Loss of |
| Offsite Power (LOOP). |
| |
| The valve, #OP42-F0295B, isolates the ECC System from the Nuclear Closed |
| Cooling (NCC) Water System. A second isolation valve, #OP42-F0290, was |
| subsequently found to have insufficient data to ensure that it alone would |
| have provided the required isolation. Failure of both valves to potentially |
| not close completely could cause the ECC System to transfer the system's |
| cooling water inventory via the NCC Water System to the Intermediate |
| Building resulting in the loss of cooling capability of the ECC System. This |
| would result in the loss of cooling capability for the systems required to |
| support the Residual Heat Removal (RHR) 'B' and 'C' Subsystems. The #F0290 |
| valve has been successfully tested to ensure that it has adequate torque to |
| close under accident conditions; however, there is insufficient leakage test |
| data available on this valve at this time. Therefore, assuming that valve |
| #F0290 leaks and valve #F0295B does not fully close, a total loss of |
| inventory would potentially occur for Division 2. |
| |
| Therefore, this condition is being conservatively reported to the NRC as a |
| loss of safety function during a past outage which removed RHR 'A' from |
| service, until further evaluation is completed. |
| |
| Valve #OP42-F0295B has been electrically closed under static flow conditions |
| to ensure continued operability of the ECC System. |
| |
| Licensee planned actions include further evaluation of past test data or |
| performance of a specific leak test on valve #OP42-F0290 and further |
| evaluation of data on valve #OP42-F0295B. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37252 |
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 08/24/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 02:28[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 14:15[EDT]|
| NRC NOTIFIED BY: B HORNING |LAST UPDATE DATE: 08/24/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| BOTH DIVISIONS OF CORE SPRAY AND HPCI RENDERED INOPERABLE. |
| |
| During a walkdown of equipment required to be environmentally qualified, |
| plant staff identified electrical circuits which do not conform to the |
| requirements of 10 CFR 50.49. These circuits control the minimum flow motor |
| operated valves for both divisions of Core Spray and HPCI (High Pressure |
| Coolant Injection). This condition rendered both divisions of Core Spray |
| and HPCI inoperable. Technical Specification Limiting Condition of Operation |
| for Core Spray and HPCI were entered. This condition therefore constitutes |
| a condition that alone could have prevented Core Spray and HPCI from |
| removing decay heat. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 37253 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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: 08/24/2000|
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
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