Event Notification Report for July 05, 2012

VALVE IMPROPERLY ALIGNED FOR ACCIDENT MITIGATION

"On 7/5/12 at 0307 hrs (EDT), Salem Unit 2 declared 21 Auxiliary Feedwater Pump out of service due to the failure of the 23AF21, Auxiliary Feedwater Flow Control valve to the 23 Steam Generator. 23AF21 had failed to a full open position during performance of the in-service test. Salem Unit 2 entered Technical Specification 3.7.1.2 a, Action Statement a, which requires restoring the pump to operable status within 72 hours, otherwise be in at least Hot Standby within the next 6 hrs and in Hot Shutdown within the following 6 hours.

"At 1000 hrs on 7/5/12, the air supply to the 23AF21 was found isolated. Troubleshooting and repair of the 23AF21 was completed and, following in service testing, the valve was declared operable at 1349 hrs.

"Review of the valve's operability concluded that the failure of the 23AF21 valve to close represented a condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. The Salem UFSAR assumes that during a Category IV Main Steam break accident, a faulted Steam Generator would be identified and Auxiliary Feedwater would be isolated to the affected Steam Generator within 10 minutes. Since the valve was failed open and could not be operated from the control room, the plant would have to manually isolate 23AF21 or trip the 21 Auxiliary Feedwater Pump to ensure feedwater isolation to the affected, faulted Steam Generator. The time to perform manual isolation or tripping of the Auxiliary Feedwater Pump may have required more time than that analyzed by the plant UFSAR.

"This is being reported under 10CFR50.72(b)(3)(v), the nuclear plant being in a condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident.

"There were no other safety related systems affected by this event and there were no injuries associated with this event."

Maintenance was last performed on this system on May 17, 2012.

The licensee will notify the NRC Resident Inspector and Lower Alloways Creek Township.

UNANALYZED CONDITION DUE TO BLOCKING BOTH REACTOR BUILDING RAILROAD BAY DOORS

"At 1258 CDT on 07/05/2012, Operations was notified that both panels of Door 45 (south doors for the reactor building railroad bay airlock) were blocked by a man lift. Blocking both doors represents an unanalyzed condition as a flow path through the door is assumed for pressure relief during postulated HELB events. The man lift was immediately removed correcting the situation and all work related to Door 45 was stopped. Door 45 was blocked for approximately 20 minutes.

"The NRC Resident Inspector has been notified."


* * * RETRACTION FROM BART BLAKESLEY TO DONALD NORWOOD AT 1605 EDT ON 8/31/2012 * * *

"The purpose of this notification is to retract the previous Event Notification Report (#48072) made by the Monticello Nuclear Generating Plant on 7/5/2012. The initial report indicated that blocking both panels of the railroad bay doors by a man lift represented an unanalyzed condition, as a flow path through the door is assumed for pressure relief during postulated HELB events, and was reported in accordance with 10CFR50.72(b)(3)(ii)(B), Unanalyzed Condition. Since the initial report, Engineering has completed an evaluation that demonstrates equipment supporting safe shutdown would have been capable of performing their specified design function during postulated HELB events. Based on this analysis, the condition initially reported in EN #48072 did not result in an unanalyzed condition that significantly degraded plant safety and is therefore retracted.

"The NRC Resident Inspector has been informed of this retraction."

Notified R3DO (Cameron).