Event Notification Report for March 13, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/12/2002 - 03/13/2002
** EVENT NUMBERS **
38761 38762
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|Power Reactor |Event Number: 38761 |
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| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 03/12/2002|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 14:50[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/12/2002|
+------------------------------------------------+EVENT TIME: 08:30[EST]|
| NRC NOTIFIED BY: CECIL WILLIAMS |LAST UPDATE DATE: 03/12/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| UNANALYZED CONDITION - SI MINIFLOW LINE VALVE INTERLOCK MIS-WIRED |
| |
| "In the analysis for certain design bases accidents, credit is taken for a |
| recirculation mode of operation that ensures continued cooling to the |
| reactor core following an injection mode. During the current Unit 1 |
| refueling outage, it was found that a safety injection (SI) miniflow line |
| valve (1HV-8813) interlock was mis-wired. The interlock wiring should have |
| allowed a second valve (1HV-8804B) to be opened during switchover from |
| injection mode to recirculation mode once 1HV-8813 has been closed but would |
| not. This wiring error was subsequently corrected. 1HV-8804B is opened to |
| provide a suction source from the discharge of the Train B residual heat |
| removal (RHR) pump to the suction of the SI pumps. 1HV-8804B must open for |
| recirculation to begin if the opposite train is unavailable. A review has |
| found that this mis-wiring has existed since at least 1996. |
| |
| "Based on preliminary evaluation, on 3-12-2002, at 0830 EST, we concluded |
| that this may represent an unanalyzed condition that significantly degrades |
| plant safety and is reportable per 10 CFR 50.72 (b)(3)(ii)(B). Further |
| evaluation is being performed to determine the significance of the |
| mis-wiring." |
| |
| The NRC Resident was notified by the licensee. |
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|Power Reactor |Event Number: 38762 |
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| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/12/2002|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 20:51[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/12/2002|
+------------------------------------------------+EVENT TIME: 14:30[CST]|
| NRC NOTIFIED BY: THOMAS JESSESSKY |LAST UPDATE DATE: 03/12/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS 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 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| UNANALYZED CONDITION, APPENDIX R VALVE UNABLE TO SATISFY DESIGN
FUNCTION |
| |
| "At 1430 on 3/12/02, an Appendix R credited valve was determined to be |
| unable to satisfy its design function of providing a flow path from the |
| Charging System to the Reactor Coolant System (RCS). The credited flow path |
| is necessary to control RCS inventory and maintain the plant in Mode 3 (Hot |
| Standby) during an Appendix R fire. The flow path is also utilized |
| procedurally in controlling RCS inventory while the RCS is cooled down and |
| depressurized from Mode 3 (Hot Standby) to Mode 5 (Cold Shutdown). |
| |
| "This issue places the plant in an unanalyzed condition and thus is |
| reportable under 50.73 (a)(2)(ii). |
| |
| "The specific valve is 1/2CV-1296 Auxiliary Charging Line Isolation valve. |
| The valve's design function is to open on a differential pressure of 200 |
| psid (with or without instrument air) between the discharge of the charging |
| pumps and the RCS. This line is not utilized during normal operations but is |
| an available charging path to the RCS and utilized during plant shutdown in |
| the event of an Appendix R fire. The valve is an air operated valve that is |
| assumed to have failed close due to a loss of instrument air. It has been |
| found that the valve will not open until a much higher differential pressure |
| is reached. If the RCS is at normal operating pressure (2235 psig), and the |
| actual lift pressure of the valve is greater than 500 psid, charging flow |
| will be unavailable to the RCS. A relief on the discharge of the outlet of |
| the charging pump will lift at 2735 and prevent flow to the RCS. The |
| charging pump maximum discharge pressure is 3000 psig. |
| |
| "Compensatory actions have been undertaken that establish plantwide fire |
| rounds. Fire rounds will be continued until the condition is corrected or a |
| suitable evaluation is completed that establishes other actions." |
| |
| The licensee notified the NRC Resident. |
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