ML13246A378

Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Thursday, February 16, 2012

ML13246A378
Person / Time
Site:	Wolf Creek
Issue date:	02/16/2012
From:	Mark King Office of Nuclear Reactor Regulation
To:
References
FOIA/PA-2013-0273
Download: ML13246A378 (5)

Text

Robles, JesseFrom: King, MarkSent: Thursday, February 16, 2012 2:37 PM

Subject:

IOEB Clearinghouse Screening Summary for Thursday, February 16, 2012~N : TH SUMMARY IS O0_ ClAL USE ***M CO AIN SE TIVE/ PRO IETARY 0 RC I ERNAL US ONLY I FORMAT N**DO N T FOR D Y PORTIONS 0 TSIDE NRC WIT OUT FI T OBTAIN[ P MISSIOIssues for Resolution (IFR): One (1)1) IFR -WOLF CREEK LOOP/NOUE AND AUGMENTED INSPECTION TEAM (AIT) REVIEWIFR screened in from EN 47590 Wolf Creek: NOTIFICATION OF UNUSUAL EVENT AND REACTOR TRIPDUE TO LOSS OF OFFSITE POWER. On January 13, 2012, Wolf Creek Generating Station experienced anautomatic reactor trip and a loss of offsite power (LOOP). The site declared a Notification of Unusual Event(NOUE) (See EN 47590, PNO-IV-1 2-002, and PNO-IV-002A) as a result of the loss of offsite power. Severaloperational and equipment issues were identified during the event, including ground alarms on an Emergency Diesel Generator (EDG), leaks on the Essential Service Water (ESW) system, an unexpected trip of theTurbine Driven Auxiliary Feedwater Pump (TDAFWP),

failure of a temporary diesel-driven fire pump (DFP),void formation in the reactor vessel head region during the natural circulation

cooldown, erroneous sourcerange NI indication, and emergency modifications performed to supply temporary power to various equipment.

A Management Directive (MD) 8.3 evaluation was performed, and an Augmented Inspection Team (AIT) wassent to the site to gather additional information on the event (see AIT Charter).

An OpE COMM hasbeen posted on this event.IFR Screened in under LIC-401 criteria:

l.a risk factor-conditional core damage probability (CCDP) = 1E-6 oran increase in core damage probability (delta CDP) = I E-6, or a change in large early release frequency (deltaLERF) = 1 E-7/yr2.a degradation of important safety equipment that could lead to a loss of safety function to shut down thereactor and maintain it in a safe condition, to remove residual heat, or to control the release of radioactive material2.b transients that result in unexpected plant response or cause damage to equipment important to safety2.c transients that involve inappropriate operator actions or equipment performance that affect core reactivity or reactor safety2.e reactor scram with potential complications from equipment

failure, inappropriate operator

actions, orexternal conditions 2.f programmatic breakdown in the areas of design, analysis, or equipment maintenance that will contribute tothe degradation of plant response to transients 2J potential adverse trend-potential existence of a pattern of similar or recurring events/conditions beingobserved; record every screened (in or out) OpE input in a tracking database dedicated to identifying anypattern of similar or recurring OpE occurrences.

IFR and screen-in document assiqjned to Jesse Robles.Outside of Scope 9.a

3 Outside of Scope*(i e., Screened/reviewed against LIC-401 criteria for initiating an "Issue for Resolution" (IFR), which is IOEB'sprocess for conducting further evaluation of an issue to determine what, if any, additional actions should betaken to communicate and organizationally learn from OpE)NOTEE: THIS RIMMRY IS OFFICIAL **M CONTAI SENSITIVEI P RRIETAR OR NRC IN RNAL U ONLY INFO ATI *DO T FORWARD NNS OUTSIDE F NRC HOUT FIRSTIN RMSAttendees at Screening Meeting:Jesse RoblesBob Bernardo4 Dave GarmonMark KingDoug Bollock, NROMehdi Reisifard, RES- by phone5