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The NRC is shutdown due to the lapse in appropriations. Exempted activities to maintain critical health and safety activities and progress on critical activities, including activities outlined in Executive Order 14300, as described in the OMB Approved NRC Lapse Plan will continue.

Event Notification Report for September 29, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/28/2000 - 09/29/2000

                              ** EVENT NUMBERS **

37386  37387  37388  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37386       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 09/28/2000|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 01:23[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/28/2000|
+------------------------------------------------+EVENT TIME:        01:21[EDT]|
| NRC NOTIFIED BY:  STEVE CHERBA                 |LAST UPDATE DATE:  09/28/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|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          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ELECTRICAL BUS OUTAGE WILL AFFECT TSC VENTILATION SYSTEM                     |
|                                                                              |
| "This event notification is for planned maintenance on Cook Unit 1's         |
| electrical buses that remove power from a portion of the TSC ventilation     |
| system. Contingencies are established to restore power to the TSC            |
| ventilation fan (if needed) to support Emergency Plan execution. The fan     |
| that will be unavailable boosts airflow through the TSC ventilation charcoal |
| clean-up filter subsystem. Ventilation flow will still pass through this     |
| filter without the booster fan, but TSC pressure will not be boosted to      |
| limit infiltration. Use of this fan is dependent on radiological conditions, |
| if radiological conditions warrant its use, and it is not available, the TSC |
| will relocate to the Unit 2 Control Room in accordance with plant            |
| procedures. Reporting this event is consistent with NUREG-1022, Rev 1        |
| criteria for reporting loss of ERFs.                                         |
|                                                                              |
| "No adverse consequences are expected from this outage. The TSC ventilation  |
| booster fan is expected to be unavailable for 48 hours, starting at 0121     |
| hours on 9-28-2000. Contingencies have been planned to restore power to the  |
| booster fan in 8 to 10 hours if needed. Follow-up notification will be made  |
| when the TSC is again fully available. The NRC Senior Site Resident          |
| Inspector has been informed of this planned evolution."                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37387       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 09/28/2000|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 18:43[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        09/28/2000|
+------------------------------------------------+EVENT TIME:        18:35[EDT]|
| NRC NOTIFIED BY:  ROBERT SMITH                 |LAST UPDATE DATE:  09/28/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |FRANK COSTELLO       R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS  -  PUMP POWER SUPPLY DOES NOT MEET SAFE SHUTDOWN       |
| REQUIREMENTS                                                                 |
|                                                                              |
| On September 28, 2000 at approximately 1835, it was determined that the      |
| power cable routing for the 'B' charging pump is not in accordance with the  |
| assumptions in the Millstone Unit 3 Fire Safe Shutdown Analysis. This        |
| condition could have resulted in the inability to maintain RCP seal cooling  |
| in the event of a design basis fire.   This condition is historical in       |
| nature.   In accordance with the Millstone Unit 3 Technical Requirements     |
| Manual, a fire watch has been established in the affected area as a          |
| compensatory measure until a corrective action plan can be developed and     |
| implemented.   All other fire protection features in the affected areas are  |
| operable.                                                                    |
|                                                                              |
| The cable is supposed to be run inside of a fire curtain, but instead was    |
| run outside of this curtain.                                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37388       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 09/28/2000|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 19:26[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        09/28/2000|
+------------------------------------------------+EVENT TIME:        17:30[EDT]|
| NRC NOTIFIED BY:  JAMES KOVALCHICK             |LAST UPDATE DATE:  09/28/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |FRANK COSTELLO       R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Refueling        |0        Refueling        |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL LOSS OF RHR AND ACCIDENT MITIGATION CAPABILITY                     |
|                                                                              |
| ON 09/28/00 AT 04:30 HRS. SURVEILLANCE TESTING SHOWED THAT A CHECK VALVE     |
| FAILED TO ISOLATE FLOW BETWEEN THE EMERGENCY SERVICE WATER (ESW) SYSTEM AND  |
| THE NON-SAFETY                                                               |
| RELATED UNIT 2 SERVICE WATER (SW) SYSTEM.  FAILURE TO PREVENT FLOW FROM THE  |
| EMERGENCY SERVICE WATER SYSTEM TO THE SERVICE WATER SYSTEM COULD RENDER BOTH |
| ESW SUBSYSTEMS INOPERABLE.                                                   |
|                                                                              |
| AT 05:58 ON 09/28/00, A MANUALLY OPERATED BLOCK VALVE WAS CLOSED BETWEEN THE |
| SYSTEMS TO MAINTAIN INTEGRITY OF THE ESW SUBSYSTEMS.  THIS ACTION ENSURES    |
| THAT BOTH ESW                                                                |
| SUBSYSTEMS ARE MAINTAINED OPERABLE.                                          |
|                                                                              |
| FURTHER EVALUATION AND TESTING WAS PERFORMED AND AT 17:30 HRS. ON 09/28/00,  |
| THE CONCLUSION WAS REACHED THAT THIS CONDITION COULD ALONE HAVE PREVENTED    |
| THE FULFILLMENT OF THE ESW SYSTEM SAFETY FUNCTION.                           |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+


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Page Last Reviewed/Updated Wednesday, March 24, 2021