| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/01/2003 - 12/02/2003 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40216 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CHUCK OLSON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 10/02/2003
Notification Time: 20:32 [ET]
Event Date: 10/02/2003
Event Time: 17:15 [CDT]
Last Update Date: 12/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
CHUCK CAIN (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text RCS BOUNDARY LEAKAGE DUE TO SMALL CRACK ON DRAIN LINE WELDED CAP
"Safety injection tank (SIT) isolation valve (2CV-5043-2) has a drain pipe under the valve body with a welded cap. The welded cap has a small crack with boric acid residue. The welded cap does not have any threads and is considered RCS boundary leakage. There is a check valve between the reactor coolant system (RCS) and the SIT Outlet valve. The crack will be repair welded prior to coming out of the 2R16 outage."
The Licensee has notified the NRC Resident Inspector.
* * * RETRACTED EVENT AT 1432 EST ON 12/01/03 FROM SCHEIDE TO ROTTON * * *
"This report is being made to retract a notification made at 1715 CDT on 10/02/03 (EN# 40216.)
"The notification documented the identification of a small amount of boric acid residue on a drain line attached to a Safety Injection Tank isolation valve (2CV-5034-2). The report stated that the indication was within the Reactor Coolant System boundary. However, subsequent review of the condition determined that the indication was not within the Reactor Coolant System boundary since it was isolated from the Reactor Coolant System by an operable check valve. Therefore, the condition did not represent a serious degradation of a principal safety barrier.
"Note; The drain line is 3/4 inch diameter stainless steel."
The licensee notified the NRC Resident Inspector. Notified Claude Johnson - R4DO. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40314 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JEFF PEASE
HQ OPS Officer: MIKE RIPLEY | Notification Date: 11/11/2003
Notification Time: 17:11 [ET]
Event Date: 11/10/2003
Event Time: 17:40 [EST]
Last Update Date: 12/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
JOHN PELCHAT (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text FITNESS FOR DUTY PROGRAM CONDITION
"On November 10, 2003, at 1740 hours it was determined that a Fitness-For-Duty program condition existed which required a 24-hour report to the NRC.
"Personnel with unescorted access are placed into different groups within the Fitness-For-Duty program. One of these groups, the Immune group, is for personnel not eligible for random test selection at our site, such as the NRC. The remaining groups become part of the random eligible population.
"During a review of the Fitness-For-Duty program it was discovered that the total number of personnel in the Immune population group was higher than normally expected (133 vs. 24). Some personnel required to be in the random eligible population were discovered to be in the Immune group, which rendered them ineligible for selection. (This primarily affected personnel transferring from an approved program within 30 days.). This resulted in non-compliance with 10 CFR 26.24.
"Security personnel are manually correcting the group listings, identifying the affected individuals, scheduling individuals still on site for testing, and notifying the plants where individuals potentially affected may have gone.
"A root cause investigation is presently being conducted to identify the extent, time frame, and cause of this event. If relevant information is uncovered as a part of the root cause investigation that affects the reportability determination, the NRC will be notified.
"This condition is being reported in accordance with 10CFR26.73."
The licensee has notified the NRC Resident Inspector
* * * RETRACTION AT 1553 ON 12/01/03 FROM SWEET TO GOTT * * *
Based on subsequent research, the licensee determined that the above event is not reportable as a significant event under 10 CFR 26.73.
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Bonser) |
| Power Reactor | Event Number: 40364 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JEFF PEASE
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/01/2003
Notification Time: 14:37 [ET]
Event Date: 10/03/2003
Event Time: [EST]
Last Update Date: 12/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
BRIAN BONSER (R2)
WILLIAM BECKNER (NRR)
RICHARD CONTE (R1)
BRUCE BURGESS (R3)
CLAUDE JOHNSON (R4)
JACK FOSTER (NRR)
|
| 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 NONCOMFORMANCE NOTIFICATION FOR SOLID STATE PROTECTION MASTER RELAY
Failure of Master Relay K507 (MidTex Part Number 15614D200) in the Solid State Protection System (SSPS) was attributed to corrosion caused by off-gassing of chlorine contamination from paper used to wrap the relay coil, or the adhesive used to attach the paper wrap to the coil. Master Relays must change state, upon energization, to actuate various safety related equipment in the plant. The failure of Master Relay K507 is considered to be a manufacturing defect in a basic component that could cause a loss of safety function.
The majority of MidTex relays investigated had cloth wrapped coils and these relays showed no evidence of corrosion.
The number of affected relays and installed locations was not available at the time of the initial notification.
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 40366 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: MIKE JONES
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/01/2003
Notification Time: 22:27 [ET]
Event Date: 12/01/2003
Event Time: 20:00 [EST]
Last Update Date: 12/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
BRIAN BONSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text CONTAMINATED INDIVIDUAL TRANSPORTED TO LOCAL HOSPITAL
Polar crane operator experienced a medical condition that required immediate transport to the local hospital. The individual's Anti-contamination clothing were removed in a contaminated area of the Containment building by medical responders and the individual with the medical condition was identified as being contaminated. No specific contamination level was available at the time of the initial report other than he was frisked and the level was above background. It was also not known what the general level of contamination in the immediate vicinity of the individual was at the time of the initial report. A licensee Radiation Protection Technician escorted the individual to a local hospital in an ambulance. After arrival at the hospital, the individual's modesty garments were removed and the individual was no longer contaminated. Modesty garments were disposed of and the ambulance was surveyed and determined to by uncontaminated. The transported individual is in stable condition.
The licensee notified the NRC Resident Inspector. No media or press release is expected to be made at this time. | |