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
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 38540 |
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| 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. |
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|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. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38542 |
+------------------------------------------------------------------------------+
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| 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
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| 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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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021