ML13246A378
| 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, Jesse From:
King, Mark Sent:
Thursday, February 16, 2012 2:37 PM
Subject:
IOEB Clearinghouse Screening Summary for Thursday, February 16, 2012
~N
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SUMMARY
IS O0_
ClAL USE ONLY*
- 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 MISSIO Issues for Resolution (IFR): One (1)
- 1) IFR -WOLF CREEK LOOP/NOUE AND AUGMENTED INSPECTION TEAM (AIT) REVIEW IFR screened in from EN 47590 Wolf Creek: NOTIFICATION OF UNUSUAL EVENT AND REACTOR TRIP DUE TO LOSS OF OFFSITE POWER. On January 13, 2012, Wolf Creek Generating Station experienced an automatic 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. Several operational 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 the Turbine 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 source range 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) was sent to the site to gather additional information on the event (see AIT Charter).
An OpE COMM has been posted on this event.
IFR Screened in under LIC-401 criteria: l.a risk factor-conditional core damage probability (CCDP) = 1E-6 or an increase in core damage probability (delta CDP) = I E-6, or a change in large early release frequency (delta LERF) = 1 E-7/yr 2.a degradation of important safety equipment that could lead to a loss of safety function to shut down the reactor and maintain it in a safe condition, to remove residual heat, or to control the release of radioactive material 2.b transients that result in unexpected plant response or cause damage to equipment important to safety 2.c transients that involve inappropriate operator actions or equipment performance that affect core reactivity or reactor safety 2.e reactor scram with potential complications from equipment failure, inappropriate operator actions, or external conditions 2.f programmatic breakdown in the areas of design, analysis, or equipment maintenance that will contribute to the degradation of plant response to transients 2J potential adverse trend-potential existence of a pattern of similar or recurring events/conditions being observed; record every screened (in or out) OpE input in a tracking database dedicated to identifying any pattern of similar or recurring OpE occurrences.
IFR and screen-in document assiqjned to Jesse Robles.
Outside of Scope
9.
a
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Outside of Scope
- (i e., Screened/reviewed against LIC-401 criteria for initiating an "Issue for Resolution" (IFR), which is IOEB's process for conducting further evaluation of an issue to determine what, if any, additional actions should be taken to communicate and organizationally learn from OpE)
NOTEE: THIS RIMMRY IS OFFICIAL
- LY
Jesse Robles Bob Bernardo 4
Dave Garmon Mark King Doug Bollock, NRO Mehdi Reisifard, RES-by phone 5