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Event Notification Report for April 19, 2001

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/18/2001 - 04/19/2001

EVENT NUMBERS
37933379303793138061

!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37933
Facility: KEWAUNEE
Region: 3     State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: BRADLY MCMAHON
HQ OPS Officer: DOUG WEAVER
Notification Date: 04/19/2001
Notification Time: 17:24 [ET]
Event Date: 04/19/2001
Event Time: 14:40 [CDT]
Last Update Date: 06/13/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RONALD GARDNER (R3)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 96 Power Operation 96 Power Operation
Event Text
DEGRADED APPENDIX "R" FIRE BARRIER

While conducting a walk down inspection of 10CFR50 Appendix R Barriers, two degraded gypsum walls were identified. The two walls are intended to serve as three hour rated Appendix R barriers. The inspection of the walls revealed that a segment of the walls approximately 6 feet by 6 inches was not constructed as required. The two walls provide separation of safe shutdown equipment in the event of an Appendix R design basis fire. The walls separate the charging pumps, a dedicated shutdown system component, from the safety injection pumps which are alternate shutdown system equipment.

Although the walls are not constructed as designed, they appear to be completed to about 75% of design and are judged capable of providing some protection. Nevertheless, the walls are declared inoperable and compensatory actions according to the Kewaunee Fire Plan have been initiated. The walls are declared inoperable due to not having any documented analysis to support the design basis rating.

The licensee notified the NRC resident inspector.

* * * UPDATE AT 1517 ON 6/13/01 BY HARRINGTON RECEIVED BY WEAVER * * *

The licensee has retracted this event based upon further review. On 4/19/01 Kewaunee Nuclear Power Plant (KNPP) reported to NRC via the Event Notification System (ENS) an unanalyzed condition related to two Appendix R fire barriers. The report was made based on a cursory visual inspection of two barriers that appeared to be missing a portion of a layer of gypsum board. Based on what appeared to be less than the three required layers of gypsum board, a conservative assumption was made that the barriers did not meet design requirements. Since the ENS report was filed, the barriers were partially disassembled to gather data for-performing a fire hazards analysis of the apparently degraded barriers in accordance with Generic Letter 86-10. Disassembling the barriers revealed that what appeared to be a partially missing layer was in fact an additional partial layer of gypsum board.

Based on the additional data gathered from disassembling the barriers, the barriers met design requirements for a three hour rated Appendix R fire barrier. Therefore, the barriers were not degraded and an unanalyzed condition never existed. Consequently, the reporting criteria for an unanalyzed condition was not exceeded and is the basis for retracting the ENS report notification made on 4/19/01.

The licensee notified the NRC resident inspector.


General Information or Other
Event Number: 37930
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: KLEINFELDER, INC.
Region: 4
City: TEMPE   State: AZ
County:
License #: 7-409
Agreement: Y
Docket:
NRC Notified By: FACSIMILE
HQ OPS Officer: DOUG WEAVER
Notification Date: 04/19/2001
Notification Time: 12:45 [ET]
Event Date: 04/19/2001
Event Time: 05:00 [MST]
Last Update Date: 10/15/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
CHARLES MARSCHALL (R4)
DONALD COOL (NMSS)
Event Text
THEFT OF MOISTURE/DENSITY GAUGE

On 19 April 2001, the licensee reported the theft of a Campbell-Pacific moisture/density gauge, model CPN MC3, serial number M370403663, from the Foxtree Apartments, northwest corner of McKellips and Scottsdale Roads, Tempe, Arizona. The gauge was locked in its transport container chained in the back of a 1999 Dodge Ram 1500, 2WD Quad Cab pickup, Arizona license CA 63664. The truck itself was stolen early in the morning of 19 April. The theft has been reported to the Tempe police. A reward is being offered. The gauge contains approximately 8 millicuries of cesium 137 and 40 millicuries of americium-beryllium.

The State will notify the FBI, Mexico, and the states of Colorado, Nevada, Utah, New Mexico and California.

* * * UPDATE 1645EDT ON 10/15/02 FROM AUBREY V. GODWIN TO S. SANDIN VIA FAX * * *

"Date: October 15, 2002 Time: 1:00 PM (MST) Supplemental Notice 01-5S
"First Notice: 01-5

"On April 19, 2001 the licensee report[ed] the theft of a Campbell-Pacific International, Inc., moisture/density gauge, model MC3, SN# M370403663 and a 1999 Dodge Ram 1500 truck. At approximately 7:15 PM, Oct. 12, 2002, the Agency duty officer was informed that the Phoenix PD bomb squad had found a device containing radioactive material. Upon investigation, the Agency determined that the device was the one stolen in 2001 from the Licensee. The device was not locked and wipe indicated the outside was not contaminated. The device is being returned to the licensee.

"The states of CO, CA, UT, NV, NM, and U.S. NRC and FBI as well as Mexico are being notified [of] the status of this incident."

Notified R4DO(Pick) and NMSS(Hodges).


Power Reactor
Event Number: 37931
Facility: MCGUIRE
Region: 2     State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DON CRISP
HQ OPS Officer: DOUG WEAVER
Notification Date: 04/19/2001
Notification Time: 14:09 [ET]
Event Date: 04/19/2001
Event Time: 12:30 [EDT]
Last Update Date: 04/19/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
KERRY LANDIS (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 80 Power Operation 80 Power Operation
2 N Y 100 Power Operation 100 Power Operation
Event Text
A licensed employee was determined to be under the influence of alcohol during a for cause test. The employee's access to the plant has been suspended. NRC employees may contact the operations center for additional details.

The licensee notified the NRC resident inspector.


Power Reactor
Event Number: 38061
Facility: BYRON
Region: 3     State: IL
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARRI MARCHIONOA
HQ OPS Officer: DOUG WEAVER
Notification Date: 06/11/2001
Notification Time: 11:44 [ET]
Event Date: 04/19/2001
Event Time: 23:00 [CDT]
Last Update Date: 06/11/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
ROGER LANKSBURY (R3)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
60 DAY REPORT - INVALID ACTUATION OF THE AUXILIARY FEEDWATER SYSTEM

"On April 19. 2001, at 2300, during restoration of an out of service which required relanding two leads at Solid State Protection System slave relay K620, one wire came off the screw as it was being relanded to slave relay K620 and made intermittent contact with terminal 8. It was subsequently found the Unit 2 'A' Auxiliary Feedwater pump breaker closed but the pump did not start since the breaker was in the test position and steam generator blowdown containment isolation valve 2SD002H was closed. The Unit 2 'A' Auxiliary Feedwater pump and 2SD002H are both actuated by slave relay K633 which is fed from the same master relay that feeds slave relay K620. It could not be determined how slave relay K633 was actuated during this evolution. This is considered a partial train actuation. Other slave relay components were properly removed from service or in a position such that their safety function had already been completed or were not expected to actuate due to the short duration of the signal. Subsequent slave relay testing verified all slave relays and equipment circuits were operating properly. The event was entered into the Corrective Action Process to initiate corrective actions."

The NRC Resident Inspector was notified of this 60 day report by the licensee.