Event Notification Report for February 11, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/10/2000 - 02/11/2000
** EVENT NUMBERS **
36676 36678 36679
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|Power Reactor |Event Number: 36676 |
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| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 16:50[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/08/2000|
+------------------------------------------------+EVENT TIME: 12:09[EST]|
| NRC NOTIFIED BY: CHRISTOPHER HYNES |LAST UPDATE DATE: 02/10/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 93 Power Operation |93 Power Operation |
| | |
| | |
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EVENT TEXT
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| INFORMATION CALL REGARDING RIVER WATER PUMP PROBLEMS |
| |
| "This report is being made to provide preliminary notification of an event |
| that is currently under investigation at Beaver Valley Power Station Unit |
| No. 1 (BVPS-1). |
| |
| "River Water Pump WR-P-1B at Beaver Valley Power Station Unit 1 tripped on |
| overcurrent shortly after it was attempted to be started at 1209 on |
| 02/08/2000. The Action Statement for Technical Specification 3/4.7.4.1 was |
| entered for less than two River Water subsystems being operable. River Water |
| Pump WR-P-1C (swing pump) was then aligned to the 'B' train header and it |
| also tripped on overcurrent shortly after it was started at 1716 on |
| 02/08/2000. |
| |
| "Preliminary information identified that the 1B and 1C River Water Pumps |
| would not operate due to the loss of gap between the pumps rotating assembly |
| and the pump bowl. Investigation into the cause of the loss of the pumps' |
| gap is ongoing. |
| |
| "BVPS-1 River Water Pump 1A on the 'A' train continues to operate |
| satisfactorily and is operable. The 'A' train is being treated as protected |
| equipment (i.e., no elective work is being done on or near 'A' train |
| components). The BVPS-1 operating crews have reviewed the procedures |
| associated with operating the BVPS-1 Auxiliary River Water System in the |
| Alternate Intake Structure and the use of the cross tie connection with the |
| diesel driven fire pump." |
| |
| The licensee stated that the unit entered a 72 hour Technical Specification |
| Limiting Condition for Operation (LCO) at 1209 on 2/8/2000. The NRC resident |
| inspector has been informed of this notification by the licensee. |
| |
| * * * UPDATE AT 1827 ON 02/10/00 BY DAN MURRAY TO JOLLIFFE * * * |
| |
| The licensee has identified that the #1B and #1C River Water Pumps would not |
| operate due to the loss of gap between the pump's rotating assembly and the |
| pump bowl. This event is believed to have been initiated by a temporary |
| operating procedure that started on 02/05/00 for maintenance on the |
| non-safety related filtered water system. This procedure altered the |
| filtered water system configuration which was the normal supply to the River |
| Water Pumps' seal water system. One effect of this change was an increase |
| in the seal water temperature at times as much as 30 degrees above its |
| previous temperature which had been near the current river water |
| temperature. This temperature increase adversely affects a pump in the |
| standby configuration whereby thermal expansion of the pump's rotating |
| assembly causes a loss of clearance. River Water Pump #WR-P-1A has remained |
| operating satisfactorily throughout this event. The identified increased |
| seal water temperature condition would not adversely affect an operating |
| pump. Administrative controls have been implemented to require only the use |
| of seal water supply sources with temperatures at or near the current river |
| water temperature for the River Water Pumps. |
| |
| This condition is being reported to the NRC pursuant to |
| 10CFR50.72(b)(1)(ii)(B) as a condition that is outside the design basis of |
| the plant because of the potential for one train of the two-train safety |
| related River Water System (required to be operable per Technical |
| Specification 3/4.7.4.1) to have been incapable of performing its design |
| safety function for an extended period of time during operation. |
| |
| The licensee plans to revise the test procedure, perform the tech spec |
| surveillance test using the safety related seal water supply source, and |
| exit the tech spec action statement. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R1DO Harold Gray. |
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|Power Reactor |Event Number: 36678 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 02/10/2000|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 16:11[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/10/2000|
+------------------------------------------------+EVENT TIME: 14:14[CST]|
| NRC NOTIFIED BY: TERRY DAMASHEK |LAST UPDATE DATE: 02/10/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| DISCOVERY OF A 120-GALLON CONTAINMENT SPRAY ADDITIVE TANK LEVEL DEVIATION |
| |
| During review of calculations and calibration methods for the containment |
| spray additive tank level indicator, it was determined that actual spray |
| additive tank level was approximately 120 gallons below the technical |
| specification required volume. Technical Specification Limiting Condition |
| for Operation (LCO) 3.6.7 had been entered earlier in the day due to planned |
| maintenance, and efforts to restore spray additive tank level minimum volume |
| are underway. The impact of the 120-gallon level deviation is being further |
| evaluated at this time to determine the impact on the plant design basis. |
| The licensee expects to be able to resolve this issue prior to expiration of |
| the 72-hour LCO. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 36679 |
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| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/11/2000|
| UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 00:59[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/2000|
+------------------------------------------------+EVENT TIME: 18:50[EST]|
| NRC NOTIFIED BY: BROWN |LAST UPDATE DATE: 02/11/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| THE LICENSEE SUBMITTED A 24 HOUR OPERATING LICENSE DEVIATION REPORT. |
| |
| While performing the Penetration Seal Firestop Configuration verification |
| project, engineering determined that 37 firestop penetrations are not |
| configured in accordance with existing approved details. Therefore, these |
| 37 penetrations are not operable, putting the plant in a LCO action |
| statement. Remedial action has been taken per Selected License Commitment |
| 16.9-5 Fire Barrier Penetrations, this action establishes hourly fire |
| watches on each affected penetrations. |
| |
| The NRC Resident Inspector was notified. |
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