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Event Notification Report for February 20, 2002

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/19/2002 - 02/20/2002

EVENT NUMBERS
3871138712387133871438760

Hospital
Event Number: 38711
Rep Org: MONTGOMERY HOSPITAL
Licensee:
Region: 1
City: MORRISTOWN   State: PA
County:
License #: 3712110-02
Agreement: N
Docket:
NRC Notified By: ROSEMARY NACE
HQ OPS Officer: MIKE NORRIS
Notification Date: 02/20/2002
Notification Time: 13:17 [ET]
Event Date: 02/20/2002
Event Time: 10:00 [EST]
Last Update Date: 02/20/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
MICHAEL MODES (R1)
FRED BROWN (NMSS)
Event Text
SHIPMENT WITH REMOVABLE RADIOACTIVE SURFACE CONTAMINATION EXCEEDING THE LIMITS

A shipment of 170 millicuriesTc-99 diagnostic vials was shipped to Montgomery Hospital, Morristown PA from Mallinckrodt Pharmacy, Philadelphia, PA. An incoming survey on the outside of the shipping package indicated loose smearable levels of 938,000 to 1,000,000 dpm/smear of beta-gamma contamination. Surveys of the shipping vehicle and driver indicated no removable contamination. No personnel at the Hospital were contaminated and the shipping package is stored in the hospital hot cell. The material was shipped non-exclusive use.

Licensee contacted Michelle Beardsley at R1 and the shipper.


Power Reactor
Event Number: 38712
Facility: HOPE CREEK
Region: 1     State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: CHRISTOPHER SEATA
HQ OPS Officer: MIKE NORRIS
Notification Date: 02/20/2002
Notification Time: 13:25 [ET]
Event Date: 02/20/2002
Event Time: 08:00 [EST]
Last Update Date: 02/20/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
MICHAEL MODES (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
FITNESS FOR DUTY REPORT

A non-licensed Supervisory employee was determined to have failed to comply with FFD procedures during random test. The employee's access to the plant has been terminated. Contact the HOO for additional details.

The Resident Inspector has been notified.


Power Reactor
Event Number: 38713
Facility: SEQUOYAH
Region: 2     State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL HOWARD
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/20/2002
Notification Time: 16:34 [ET]
Event Date: 02/20/2002
Event Time: 15:00 [EST]
Last Update Date: 02/21/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
LEONARD WERT (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation
Event Text
SAFE SHUTDOWN CAPABILITY IMPACTED BY NON-CONSERVATIVE SG NR SETPOINT

"Based on the review of [Operating Experience (OE)] 13294 from Diablo Canyon regarding unexpected response of Steam Generator [(SG)] Narrow Range level trip not responding as expected, an assessment was performed of the narrow range (NR) Steam Generator level channels at Sequoyah 1 and 2. This assessment determined that the current 10.7% lo-lo level trip setpoint did not account for the uncertainties associated with the differential pressure (dP) created by the steam flow past the mid-deck plate in the moisture separator section of the steam generator. This dP phenomena will cause the SG NR level channels to read higher than actual water level at high steam flows. Thus, the lo-lo level trip setpoint is non-conservative.

"In the unlikely event of a Loss of Normal Feedwater or a Loss of Offsite Power, the potential exists that a required reactor trip on lo-lo steam generator level may be delayed or may not be received at all. In this scenario, other trip functions such as overtemperature delta-T would be expected to actuate in response to the initiating event. However, these would arrive in a different sequence, and the net effect on the UFSAR Chapter 15 accident analysis results is unknown. Thus, a condition exists in that a safety function could have been prevented.

"As a conservative measure, upon identification of this condition by Westinghouse via NSAL 02-3, the environmental allowance monitor (EAM) was actuated on U-1 and U-2 on Friday, February 15, 2002. This feature changes the S/G Lo-Lo Level Rx Trip setpoint from 10.7% to 15%. Since the known S/G channel uncertainty is 8.3% with a narrow range span uncertainty of 5.3%, it was determined that operating with the EAMs continuously actuated will allow continued operation. After further evaluation of this condition, it has been determined that 10 CFR 50.72(b)(3)(v)(A) applies as a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to shutdown the reactor and maintain it in a safe shutdown condition.

"EAMs actuated on U-1 at time of discovery (vent in progress). EAMs actuated at 1814 on 2/20/02."

The licensee informed the NRC Resident Inspector.

* * * UPDATED AT 0800 EST BY MICHAEL HOWARD TO FANGIE JONES * * *

Correction to statement above ".. EAMs actuated at 1814 on 2/20/02," should have said EAMs actuated at 1814 on 2/15/02 on U-2.

The licensee informed the NRC Resident Inspector. The R2DO (Leonard Wert) has been informed.


General Information or Other
Event Number: 38714
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GEOSOILS, INC.
Region: 4
City: CARLSBAD   State: CA
County:
License #: 6762-37
Agreement: Y
Docket:
NRC Notified By: ROB GREGOR
HQ OPS Officer: FANGIE JONES
Notification Date: 02/21/2002
Notification Time: 00:20 [ET]
Event Date: 02/20/2002
Event Time: 12:40 [PST]
Last Update Date: 02/21/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
LINDA HOWELL (R4)
E. WILLIAM BRACH (NMSS)
Event Text
24 HOUR AGREEMENT STATE REPORT - STOLEN NUCLEAR DENSITY GAUGE

"Area office received notification that a CPN [Campbell Pacific Nuclear] moisture density gauge, MC3-S/N, M38088381 was stolen from a storage container between the evening of 2/19/02 to the morning of 2/20/02 from a job site at Pine and Butterfield Ranch in Chino Hills, CA.

"Local sheriff contacted and report filed. Licensee to run an add in local paper describing device and offering reward for return of gauge."


Hospital
Event Number: 38760
Rep Org: VA NATIONAL HEALTH PHYSICS PROGRAM
Licensee: CENTRAL CALIFORNIA HEALTH CARE SYSTEM, FRESNO, CALIFORNIA
Region: 4
City: FRESNO   State: CA
County:
License #: 04-01935-03
Agreement: Y
Docket:
NRC Notified By: ED LEIDHOLDT
HQ OPS Officer: FANGIE JONES
Notification Date: 03/11/2002
Notification Time: 17:03 [ET]
Event Date: 02/20/2002
Event Time: 00:00 [PST]
Last Update Date: 03/11/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
GAIL GOOD (R4)
JANET SCHLUETER (NMSS)
Event Text
SEALED GADOLINIUM SOURCE LOST

During an inspection on 2/20/2002 by the VA at the Central California Health Care System, Fresno, CA a sealed Gd-153 (980 microcuries) source was determined to be missing as of 5/11/2001. The source is a solid Gadolinium pellet sealed in a titanium capsule and in a lead shield with a spring operated shutter. Present activity is calculated to be 430 microcuries. A search of the facilities, personnel interviews, and an inventory was conducted. It has been determined that in most probability the source inside its lead shield was mistakenly discarded with non-radioactive hospital waste and is presently buried in the municipal landfill. A visit to the landfill determined that recovery was very unlikely. There was little likelihood that this event resulted in measurable radiation doses to hospital workers or any member of the public.

The RSO has been retrained in proper disposal of sources and methods for decay and storage. It is believed that sufficient corrective actions have been taken to date to prevent a reoccurrence of this event, however further actions are being researched and developed.

The VA has contacted NRC Region 4 (Cain).