| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/22/2004 - 11/23/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41206 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: NC ENVIRONMENTAL HEALTH SERVICES
Region: 1
City: RALEIGH State: NC
County:
License #: 092-0456-17
Agreement: Y
Docket:
NRC Notified By: LARRY MICHAELS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/18/2004
Notification Time: 18:15 [ET]
Event Date: 11/18/2004
Event Time: 15:52 [EST]
Last Update Date: 11/18/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
KENNETH JENISON (R1)
DANIEL GILLEN (NMSS)
| Event Text AGREEMENT STATE REPORT - LEAD PAINT ANALYZER MISSING AND THEN RECOVERED
An employee of the North Carolina Department of Environmental Health [NCDEH], Environmental Health Services reported to his supervisor on 11/18/04 that his Niton XRF lead paint analyzer device was missing or stolen from the trunk of his car. After retracing his travels going back to the last time he used the device on 11/09/04, it was discovered that he had inadvertently left the device in the parking lot of the Union County Health Department where he had earlier performed a lead investigation. An Union County Health Department employee had found the locked device on 11/09/04 in the parking lot and secured it in their building.
The device will be retrieved by a NCDEH employee on 11/19/04. The device contains 14 milliCuries of Cadmium-109. The device serial number is U1399. The sealed source serial number is NR4649. |
| Power Reactor | Event Number: 41214 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ANDY HALLIDAY
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/22/2004
Notification Time: 14:38 [ET]
Event Date: 10/07/2004
Event Time: 20:55 [EST]
Last Update Date: 11/22/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
ANTHONY DIMITRIADIS (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text 60-DAY REPORT DUE TO AN INVALID ACTUATION OF ECCS AND EDGs DURING SURVEILLANCE ACTIVITIES
"The purpose of this report is to provide a telephone notification under 10CFR50.73(a)(2)(iv)(A) for an invalid actuation of the Emergency Core Cooling Systems and the Emergency AC Electrical Power Systems. As allowed by 10CFR50.73(a)(1) this notification is being made via an ENS phone call.
"On October 7, 2004, James A. Fitzpatrick (JAF) was in a refueling outage with the reactor cavity flooded and the spent fuel pool gates removed. At approximately 2055, during the performance of an instrument surveillance procedure (ISP-5-7) for 'Remote Shutdown Reactor Vessel Pressure Indicator Calibration' a pressure perturbation was introduced to the sensing lines while returning 02-3PI-60A to service. The pressure perturbation resulted in an invalid actuation of the Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generator (EDG) initiation logic. The initiation logic functioned as designed, 'A' and 'B' Core Spray Pumps and 'A', 'B', 'C', and 'D' RHR pumps started and injected into core, and EDGs 'A', 'B', 'C' and 'D' started but did not close to the emergency buses since there was no loss of off site power.
"Operations personnel verified plant conditions, secured ECCS injection and secured the EDGs. The event was entered in the plant corrective action program via Condition Report CR-JAF-04-04457. Preliminary investigation has identified valve manipulation to restore pressure indicator 02-3PI-60A to service as the cause of a pressure perturbation in a shared sensing line, which caused the level transmitters sharing the same line to detect a low reactor water level condition. All systems that actuated operated per their design.
"As a result of the injection, water overflowed to the skimmer surge tanks and into the reactor building drain system as designed, resulting in contamination of sections of the reactor building. No personnel contaminations or unexpected exposures occurred as a result. A recovery plan was developed and implemented to minimize the impact and to recover the affected plant areas.
"In addition, signals were received for HPCI and RCIC initiation, SBGT initiation, Recirc pump trip and Alternate Rod Insertion (ARI). Due to outage activities, these systems were removed from service and protective tagged, and thus the systems did not respond. Although not required by 10 CFR 50.73 JAF will submit a voluntary LER to address this event in greater detail.
"The NRC Sr. Resident Inspector was notified."
The licensee also informed the State of New York. |
| Power Reactor | Event Number: 41215 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: MIKE RIPLEY | Notification Date: 11/22/2004
Notification Time: 18:27 [ET]
Event Date: 11/22/2004
Event Time: 15:10 [EST]
Last Update Date: 11/22/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
ANTHONY DIMITRIADIS (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 15 | Power Operation | 15 | Power Operation | Event Text PORTION OF PRIMARY INSTRUMENT LINES NOT ALIGNED TO SECONDARY CONTAINMENT
"At 15:10 on 11/22/2004 Operations was notified of a condition that could have prevented the ability of Secondary Containment to control and monitor the release of radioactive material.
"Three primary system instrument lines have approximately a 20-foot run in an area that is not normally aligned to Secondary Containment. This area has been realigned to Secondary Containment until an analysis of this design can be completed. This has been determined to be reportable under 10CFR50.72(b)(3)(v)(C).
"Unit 1 is at 15% power with the main generator off line for unrelated repairs."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41216 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DAN JORDHEIM
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/23/2004
Notification Time: 03:01 [ET]
Event Date: 11/22/2004
Event Time: 17:30 [PST]
Last Update Date: 11/23/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JEFFERY CLARK (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INADVERTENT ISOLATION OF THE REACTOR CORE ISOLATION COOLING SYSTEM
"This ENS notification is made to report that on November 22, 2004 at 17:30 PST the Reactor Core Isolation Cooling (RCIC) system was rendered inoperable when its inboard steam supply containment isolation valve inadvertently closed during the performance of a routine surveillance procedure. The surveillance procedure was stopped and plant operators entered the appropriate Technical Specification Action Statements. The RCIC system was restored to its normal standby lineup and declared operable two hours and three minutes after the isolation.
"NRC guidance in NUREG 1022 (Rev. 2), 'Event Reporting Guidelines,' and NRC Regulatory Issue Summary (RIS) 2001-14, 'Position on Reportability Requirements for Reactor Core Isolation Cooling System Failure,' indicates that RCIC failures are not reportable unless the RCIC system is specifically credited in the plant's Final Safety Analysis Report for mitigating the consequences of a Control Rod Drop Accident (CRDA). Columbia Generating Station has determined that the current licensing basis and docketed correspondence is not clear regarding RCIC credit for CRDA mitigation. Proposed FSAR changes were recently submitted by Energy Northwest to the NRC that would clarify that RCIC is not credited for CRDA mitigation. However, the NRC staff has not yet approved these proposed changes. Therefore, Columbia Generating Station has decided to conservatively report this event under 10 CFR 50.72(b)(3)(v)(D). A follow-up LER will be issued under 10 CFR 50.73(a)(2)(v)(D)."
The licensed has notified the NRC Resident Inspector. | |