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Event Notification Report for December 6, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/05/2001 - 12/06/2001

                              ** EVENT NUMBERS **

38352  38540  38541  38542  
.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38352       |
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+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 10/05/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 04:30[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/05/2001|
+------------------------------------------------+EVENT TIME:        00:26[EDT]|
| NRC NOTIFIED BY:  J. A. WITTER                 |LAST UPDATE DATE:  12/05/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNIT 2 ENTERED TECH SPEC 3.0.3 DUE TO TWO TRAINS OF SERVICE WATER 
DECLARED  |
| INOPERABLE                                                                   |
|                                                                              |
| "At 0026 hrs on October 5, 2001, Beaver Valley Power Station Unit 2          |
| experienced a trip of the 'A' Train Service Water (SWS) Pump. 2SWS-P21 C was |
| operating on the 'A' SWS header when the pump tripped on Motor Ground Over   |
| Current. Both A and B Train Emergency Service Water Pumps (SWE) auto started |
| as designed and Service Water header pressure returned to normal values. Due |
| to a piping class break, safety/non-safety, between the SWS and SWE systems, |
| the unit entered Technical Specification 3.0.3 due to two trains of Service  |
| Water being Inoperable. The unit entered and completed the Abnormal          |
| Operating Procedure for Loss of Service Water, and the Bravo Train of        |
| Service Water was restored Operable when 2SWE-P21 B was secured and isolated |
| from the 'B' SWS header. 25W5-P21 B continued to operate normally during     |
| this event. Technical Specification 3.0.3 was exited at 0037 hrs. The plant  |
| is currently stable and operating at 100% power. Technical Specification     |
| 3.7.4.1 for Service Water (72-hour action) is applicable, as the only        |
| operating pump on the 'A' SWS header is 2SWE-P21A. The Alpha Service Water   |
| Pump, 2SWS-P21 A is unavailable due to Intake Structure Bay cleaning.        |
| Currently efforts are under way to recover the Intake Bay and restore        |
| 2SWS-P21A Operable. It is expected that both trains of Service Water will be |
| Operable within 12 hours. The Non Safety Related Chiller units tripped due   |
| to the SWS low pressure conditions, and were recovered shortly there after.  |
| No additional failures or equipment challenges occurred as a result of this  |
| event."                                                                      |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTED AT 1907 EST ON 12/5/01 BY J. A. WITTER TO FANGIE JONES * *   |
| *                                                                            |
|                                                                              |
| "At 0430 hours on October 5, 2001 Beaver Valley Power Station Unit 2         |
| reported entry into Technical Specification 3.0.3, due to two trains of the  |
| Service Water System being inoperable (Event Notification #38352). The       |
| declaration of the loss of both trains of the Service Water System was a     |
| conservative action taken by the operating personnel at that time. This      |
| notification is a retraction of the 10 CFR 50.72(b)(3)(v)(B) event on        |
| October 5, 2001 at 0026 hours. Subsequent investigation of the event and     |
| engineering assessment of operability concluded that one train of the        |
| Service Water System remained operable throughout the time period of this    |
| event. Therefore, Technical Specification 3.0.3 was not applicable and       |
| Technical Specification 3.7.4.1 was applicable for the loss of one train of  |
| Service Water, which was subsequently properly exited 6 hours later."        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (John Rogge) has |
| been notified.                                                               |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38540       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 12/05/2001|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 16:25[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/05/2001|
+------------------------------------------------+EVENT TIME:        10:00[CST]|
| NRC NOTIFIED BY:  BOB KIDWELL                  |LAST UPDATE DATE:  12/05/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         R4      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE DATA SYSTEM FOUND INOPERABLE                              |
|                                                                              |
| The licensee was conducting their quarterly functional test of the Emergency |
| Response Data System (ERDS) and found it to be inoperable.  The problem with |
| ERDS is being investigated at this time.                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38541       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 12/05/2001|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 20:26[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        12/05/2001|
+------------------------------------------------+EVENT TIME:        18:00[CST]|
| NRC NOTIFIED BY:  ROB HARRSCH                  |LAST UPDATE DATE:  12/05/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|2     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| APPENDIX R REVIEW REVEALED A POTENTIAL FAILURE OF THE MOTOR DRIVEN
AUXILIARY |
| FEEDWATER PUMPS                                                              |
|                                                                              |
| The licensee was conducting an Appendix R review and made the following      |
| discovery.                                                                   |
|                                                                              |
| "Review of the Motor Driven Aux. Feed Pump (MDAFP) response to an Appendix R |
| fire with a coincident loss of off-site power and instrument air indicates   |
| an Appendix R concern in Fire Areas A01-B, A02, A23N and A23S, which are the |
| Central Area of the 26' PAB, SI/CS Pump Room, North Aux. Feed Pump Room and  |
| South Aux. Feed Pump Room, respectively. In each of these areas, a MDAFP is  |
| relied upon as the means of getting Aux Feedwater to at least one Steam      |
| Generator for at least one of the Units and both Units for Fire Area A01-B,  |
| to support heat removal from the RCS. The review performed, revealed that an |
| Appendix R fire in these fire areas could potentially result in an           |
| auto-start of the credited MDAFP, due to fire damage initiating the start    |
| signal or trip of the Main Feedwater Pumps. This auto-start signal also      |
| opens the mini-recirc. valve for the MDAFP and motor driven discharge        |
| valve(s) for the steam generator to be supplied Aux. Feedwater. Due to fire  |
| damage, the motor driven discharge valve may fail to open and the            |
| mini-recirc valve may fail closed due to a loss of instrument air supply.    |
| This could potentially result in dead heading the pump and subsequent damage |
| to the pump.                                                                 |
|                                                                              |
| "In response to the discovery of this issue, hourly fire rounds have been    |
| initiated in the fire areas affected. With the establishment of this         |
| compensatory measure in conjunction with existing guidance contained in      |
| operations procedures, the MDAFPs are considered operable."                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38542       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 12/06/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 04:55[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        12/06/2001|
+------------------------------------------------+EVENT TIME:        03:50[EST]|
| NRC NOTIFIED BY:  JEFF GROFF                   |LAST UPDATE DATE:  12/06/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DUE TO A LOSS OF STATOR WATER COOLING                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0350 on 12/6/01 with the reactor at 100%, a manual reactor scram was     |
| inserted due to the loss of stator water cooling.  All control rods fully    |
| inserted into the core.  While taking a stator water sample, the heat        |
| exchanger vent line broke off the heat exchanger losing stator water from    |
| the system.  A reactor scram was inserted prior to an eminent turbine        |
| generator trip."                                                             |
|                                                                              |
| "Following the reactor scram, water level dropped to approximately 120".     |
| Reactor water level is being maintained in the normal level band (197") with |
| feedwater/condensate.  The following 'Level 3' isolations occurred as        |
| expected:"                                                                   |
|                                                                              |
| "Group 4 - RHR Shutdown Cooling and Head Spray"                              |
| "Group 13 - Drywell Sumps"                                                   |
| "Group 15 - Traversing Incore Probe Systems"                                 |
|                                                                              |
| "All valves in [Groups] 4 and 15 were closed prior to the event.  Group 13   |
| valves closed as designed.  No ECCS systems initiated, and no SRVs lifted.   |
| All Emergency Diesel Generators are operable."                               |
|                                                                              |
| The licensee stated that the main steam isolation valves remained open and   |
| that the main condenser is being used as the heat sink.  Containment         |
| parameters are normal, and the grid is stable.                               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+
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