05000364/LER-2016-001
On 5/11/2016 at 0653 CDT, with Unit 2 (U2) at 29 percent power, the Hi-Hi Steam Generator (SG) setpoint was reached. This caused the main feedwater valves to isolate, the running main feedwater pumps to trip, automatic start of the Motor Driven Auxiliary Feed Pumps, and the main turbine to trip automatically. The reactor was manually tripped per procedure. This event is reportable as required by 10 CFR 50.73(a)(2)(iv)(A) due to a manual actuation of the Reactor Protection System and the automatic actuation of the Auxiliary Feedwater system.
The cause of the manual reactor trip was determined to be inadequate control of the feedwater system, leading to an overfilling of the Steam Generators. Corrective actions included additional training provided to the startup control room team on manipulations that affect the feedwater system. Also, more specific guidance on feedwater system operation and control during Startup from Hot Standby to Power Operations will also be incorporated into operating procedures. NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 0,..0 .5 , ' 1- r. % LICENSEE EVENT REPORT (LER) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. Joseph M. Farley Nuclear Plant, Unit 2 05000- 364 ContentsA. PLANT AND SYSTEM IDENTIFICATIONWestinghouse - Pressurized Water Reactor Energy Industry Identification Codes are identified in the text as [XX]. B. DESCRIPTION OF EVENTOn 5/11/2016 at 0653 CDT, with Unit 2 (U2) at 29 percent power, the Hi-Hi Steam Generator (SG) setpoint was reached. This caused the main feedwater valves to isolate, the running main feedwater pumps to trip, automatic start of the Motor Driven Auxiliary Feed Pumps, and the main turbine to trip automatically. The reactor was manually tripped per procedure. C. UNIT STATUS AT TIME OF EVENTUnit 2, Mode 1, 29 percent power D. CAUSE OF EVENTThe cause of the manual reactor trip was determined to be inadequate control of the feedwater system, leading to an overfilling of the Steam Generators. E. REPORTABILITY ANALYSIS AND SAFETY ASSESSMENTThis event is reportable as required by 10 CFR 50.73(a)(2)(iv)(A) due to a manual actuation of the reactor protection system and automatic actuation of the auxiliary feedwater system. The reactor was shut down at 0653 and mode 3 was entered to complete the necessary procedural actions. The Motor Driven Auxiliary Feed Pumps also started automatically which is reportable by 10 CFR 50.73(a)(2)(iv)(A). There was no loss of safety function and no radioactive release associated with this event. All required safety systems were available and the plant responded as expected. There were no actual consequences detrimental to the health and safety of the public and is considered to be of very low safety significance. F. CORRECTIVE ACTIONCorrective actions included additional training provided to the startup control room team on manipulations that affect the feedwater system. Also, more specific guidance on feedwater system operation and control during Startup from Hot Standby to Power Operations will also be incorporated into operating procedures. G. ADDITIONAL INFORMATIONOther system affected: No systems other than those mentioned in this report were affected by this event. NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (11-2015) /0 ,..
. 1 (' . . LICENSEE EVENT REPORT (LER) CONTINUATION SHEETAPPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. Joseph M. Farley Nuclear Plant, Unit 2 05000- 364 Commitment Information: This report does not create any licensing commitments == Previous Similar Events: == |
| Joseph M. Farley Nuclear Plant | |
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| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 3642016001R00 - NRC Website | |
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