United States Nuclear Regulatory Commission - Protecting People and the Environment

Morning Report for August 6, 1999

                       Headquarters Daily Report

                         AUGUST 06, 1999

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                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

HEADQUARTERS                           X
REGION I                               X
REGION II                              X
REGION III                             X
REGION IV           X
PRIORITY ATTENTION REQUIRED  MORNING REPORT - REGION IV  AUGUST  6, 1999

Licensee/Facility:                     Notification:

Wolf Creek Nuclear Oper. Corp.         MR Number: 4-99-0023
Wolf Creek 1                           Date: 08/05/99
Burlington,Kansas                      SRI via Telephone
Dockets: 50-482
PWR/W-4-LP

Subject: UPDATE ON REACTOR TRIP OF AUGUST 5, 1999

Discussion:

Reference Reportable Event Number 35994. At 12:58 p.m., (CDT), on August
5, 1999, the reactor tripped on Lo Lo Steam Generator level indication
following the inadvertent closure of the D Steam Generator Feedwater
Regulating Valve.  The licensee determined the cause of the valve closure
to be a failed controller card located in the feedwater regulating valve
control circuit.  The card was replaced, and the valve circuit was tested
satisfactorily.  During preparations for plant startup, the C Main
Feedwater Isolation Valve failed to open.  The licensee determined the
cause of the failure to be a leaking check valve in the feedwater
isolation valve operating hydraulic system.  The check valve was
subsequently reseated, and the feedwater isolation valve was tested
satisfactorily.  The check valve does not affect the capability of the
feedwater isolation valve to close.  The licensee entered Mode 2 at 4:30
a.m. on August 6, and the reactor was made critical at 5:17 a.m.  Mode 1
was entered at 9:41 a.m., and the licensee was continuing with the plant
startup.

Regional Action:

The senior resident inspector was onsite to monitor the licensee's
response to the reactor trip.  He is continuing to monitor licensee
activities related to the reactor trip and startup.

Contact:  David Graves               (817)860-8141
          Frank Brush                (316)364-8653
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REGION IV  MORNING REPORT     PAGE  2          AUGUST  6, 1999

Licensee/Facility:                     Notification:

Department Of Veterans Affairs         MR Number: 4-99-0024
Va Medical Center                      Date: 08/06/99
Albuquerque,New Mexico
Dockets: 03002583

Subject: Release of Contaminated Lead Bricks

Discussion:

On July 7, 1999, radioactive material contamination was identified on
lead bricks at a nuclear medicine display at the Department of Energy's
(DOE) National Atomic Museum. Analysis of two bricks identified the
contamination as cesium-137. The bricks were removed from the display,
wrapped, and placed in secure storage by DOE. DOE personnel conducted
comprehensive surveys of the museum and did not identify any further
contamination. Initial analysis of the bricks identified a maximum of
1543 disintegrations per minute (dpm) per 100 square centimeters for
removable contamination and 426,800 dpm per 100 square centimeters for
fixed contamination. A contact dose rate of 0.1 mRem/hr was measured.

The lead bricks used in the display were from the Department of Veterans
Affairs Medical Center (VA), Albuquerque. During its review, the VA
identified additional contaminated bricks, at the VA's facility, in the
same research area in which the displayed bricks had previously been
stored. The source of the contamination appeared to be liquid cesium-137
that was used by a researcher at the VA during the late 1970's to early
1980's. The research area at the Medical Center was secured to prevent
access to the contaminated bricks. The VA and the museum are coordinating
the return of the bricks to the VA. The VA is continuing its review.

Regional Action:

RIV/DNMS is monitoring the VA's response to the event and will review the
event during an upcoming inspection.

Contact:  Elmo E. Collins            (817)860-8291
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