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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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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).                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37249       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - 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.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37250       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| - 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.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37251       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| - 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37252       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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                                   
+------------------------------------------------------------------------------+
| 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.       |
+------------------------------------------------------------------------------+