| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/28/2004 - 07/29/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40896 | Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: KEYMASTER TECHNOLOGIES, INC.
Region: 4
City: KENNEWICK State: WA
County:
License #: WN-I0282-1
Agreement: Y
Docket:
NRC Notified By: ARDEN C. SCROGGS
HQ OPS Officer: ARLON COSTA | Notification Date: 07/23/2004
Notification Time: 17:46 [ET]
Event Date: 07/23/2004
Event Time: 11:00 [PDT]
Last Update Date: 07/23/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TOM FARNHOLTZ (R4)
LAWRENCE KOKAJKO (NMSS)
| Event Text WASHINGTON - AGREEMENT STATE NOTIFICATION OF LEAKING SOURCE
"The Licensee's Radiation Safety Officer reported at about 11 AM on July 23, 2004, that they had discovered a leaking Cobalt 57 source. The source was new. It had been taken from storage and placed into the work area for leak test prior to being placed into an XRF device. The leak test initially read 11,000 counts per minute (cpm). The source was cleaned to 416 cpm and replaced into a second shielded storage container and then sealed. The original container was wiped and found to be clean. The source work area had minor amounts of contamination and was decontaminated by the licensee. The source storage locker had not been contaminated.
"This source was part of a 13 source lot received May 18, 2004, from Isotope Products Laboratories. Upon arrival, all 13 sources passed a leak test. This source was the last of the 13 to be readied for use. The previous 12 sources also passed a leak test prior to being placed into their respective XRF devices. The licensee contacted the manufacturer to report the event. The licensee is waiting the manufacturer suggested course of action regarding disposal. Presently, there has been no media attention.
"Isotope and Activity involved: Cobalt 57, 12.52 millicuries (as of May 2004).
"XRF source, Model PHI-0106, S/N B7-461.
"WA Event Report # WA-04-042." |
| Power Reactor | Event Number: 40902 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: MIKE RIPLEY | Notification Date: 07/28/2004
Notification Time: 09:52 [ET]
Event Date: 07/28/2004
Event Time: 08:00 [EDT]
Last Update Date: 07/28/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
STEPHEN CAHILL (R2)
TERRY REIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 92 | Power Operation | | 2 | N | Y | 100 | Power Operation | 95 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS
"Event: At 08:00 hours Oconee Unit 1 initiated a unit shutdown per Technical Specification (TS) 3.0.3. Unit 2 initiated shutdown at 0900 [ET]. It is expected that Unit 3 will initiate shutdown at 1000 hours. Target for entry into Mode 3 is 1300 hours on all units. At 0129 hours all three Oconee units received a number of alarms related to power to the 230 KV switchyard (SWYD) battery chargers. At 0200 hours Operations determined that both AC power sources to the SWYD battery chargers required by TS 3.8.3 had tripped and declared entry into TS 3.0.3 because no specific condition of TS 3.8.3 applied. Evaluation for potential applicability of other reporting criteria is still in progress.
"Initial Safety Significance: The SWYD batteries currently have normal voltage (being monitored hourly) but are NOT considered operable per TS 3.8.5 at this time, which would also require TS 3.0.3 entry. However, if voltage drops too low the ability to remotely operate SWYD power circuit breakers would be affected, which would impact SWYD isolation capability. Local manual operation would still be possible, and operations personnel are stationed in the SWYD as a contingency.
"Corrective Action: 1. Maintenance has identified a fault in a power transfer switch. Actions have been completed to isolate the fault and restore power to the battery chargers. 2. Measurements of battery voltages are being taken hourly. A surveillance will be performed to verify TS 3.8.5 compliance after the charger power supply is restored. 3. Shutdown of Oconee units will follow schedule above unless power and battery voltages are restored sooner (as expected)."
The electrical grid is stable and standby emergency power remains operable. The NRC Resident Inspector has been informed. The licensee does not intend to make any State, local or other Federal notifications or issue any press release at this time.
* * * UPDATE AT 1400 EDT ON 7/28/04 FROM PHIL NORTH TO S. SANDIN * * *
At 0945 EDT both SWYD battery chargers were energized to restore battery parameters. At 1205 EDT the affected batteries were declared operable and all three (3) Units exited their respective LCOs. Units 1, 2, and 3 are currently holding at 80%, 84% and 89% power, respectively, and will commence power escalation after review and closeout of their paperwork. Notified R2DO (Decker). |
| Hospital | Event Number: 40903 | Rep Org: MADIGAN ARMY MEDICAL CENTER
Licensee: MADIGAN ARMY MEDICAL CENTER
Region: 4
City: TACOMA State: WA
County:
License #: 46-02645-03
Agreement: Y
Docket:
NRC Notified By: DAVID RYNDERS
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/28/2004
Notification Time: 13:20 [ET]
Event Date: 07/08/2004
Event Time: [PDT]
Last Update Date: 07/28/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3047(a) - EMBRYO/FETUS DOSE > 50 mSv
| Person (Organization):
RUSSELL BYWATER (R4)
ROBERTO TORRES (NMSS)
| Event Text MEDICAL EVENT INVOLVING UNINTENDED DOSE TO EMBRYO/FETUS
A female patient undergoing treatment for Graves disease received 26.6 millicuries I-131. The patient received counseling and a pregnancy test on 7/8/04 (negative results) prior to treatment. Subsequent to treatment the Hospital was informed by her husband that a home pregnancy test showed positive. The Hospital contacted the patient and scheduled a second pregnancy test on 7/23/04. The test results confirmed the pregnancy on 7/24/04. The prescribing physician has been informed. The preliminary assessment performed by the Hospital concluded that this medical event would most likely result in either a spontaneous abortion or have no impact on fetus development, i.e., at this stage in the pregnancy (zygote) the thyroid has not developed. |
| Power Reactor | Event Number: 40904 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRUCE LASHBROOK
HQ OPS Officer: JOHN MacKINNON | Notification Date: 07/29/2004
Notification Time: 02:15 [ET]
Event Date: 07/28/2004
Event Time: 21:00 [EDT]
Last Update Date: 07/29/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
| Person (Organization):
JAMES TRAPP (R1)
|
| 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 UNIDENTIFIED REACTOR COOLANT SYSTEM (RCS) LEAK
"This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. An unidentified reactor coolant system (RCS) leak of 1.0 gpm on Salem Unit 1 occurred on 7/28/04 at 2100 hours. It was discovered (that) a pressure instrument weld from 13 charging pump [PDP] discharge piping failed in the auxiliary building. Tech Specs for RCS unidentified leakage was entered. Station abnormal operating procedures (ABRC-001 RCS Leak) were entered and leakage monitoring program referenced. The leak was isolated closing the root valve of the instrument line (discharge pressure transmitter) by 2135 hours. The RCS leakage was outside of containment and was greater than design of 3840 cc/hr. This leakage would have exceeded the GDC-19 limits for control room habitability during the time of the leak initiation and leak isolation. 13 charging pump remained in service and the leak is locally isolated. The tech spec for RCS unidentified leakage was exited and ASME tech spec for the failed weld was entered. There were no unusual or unexpected responses. All systems functioned as required. There were no personnel injuries."
A maintenance tech in the auxiliary building notified control room of a leak about the same time that control room personnel noticed that the Volume Control Tank level was decreasing approx. 0.3gpm. The area around the Positive Displacement Pump (PDP) was roped off and the leak was isolated. Airborne levels in the roped off area was 8000 cpm (from 2130 to 2200 hours). Nobody was evacuated from auxiliary building. At 0040 hours airborne samples were within normal limits. The area around # 13 PDP is still roped off until the surface contamination is cleaned up. Lower Alloways Creek Township will be notified of this by the licensee.
The NRC Resident Inspector will be notified of this event by the licensee. | |