| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/30/2004 - 08/02/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40898 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: COLORADO STATE UNIVERSITY
Region: 4
City: FORT COLLINS State: CO
County:
License #: 002-27
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/27/2004
Notification Time: 12:42 [ET]
Event Date: 07/26/2004
Event Time: [MDT]
Last Update Date: 07/27/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RUSSELL BYWATER (R4)
CHARLIE MILLER (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING STUCK IRRADIATOR SOURCE
Yesterday, July 26, 2004, Colorado State University, a Colorado licensee, notified the Department that a source used in one of their panoramic irradiators became stuck in the exposed position during a routine service check. The University's Radiation Safety Officer locked and posted the irradiator room to prevent further entry. The room was designed for irradiator use, so, there is no potential for exposures to staff or members of the public. The maker of the irradiator, JL Shepherd, was notified, and a plan is being developed to manually move the source to the shielded position.
Location: Colorado State University, Fort Collins, Colorado
License: Colorado # 002-27
Irradiator: JL Shepherd Model #354
Source: Amersham, Cs-137, 21.7 Ci |
| General Information or Other | Event Number: 40900 | Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: NORTHWEST INSPECTION
Region: 4
City: SPOKANE State: WA
County:
License #: WN-IR065-1
Agreement: Y
Docket:
NRC Notified By: ARDEN C. SCROGGS
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/27/2004
Notification Time: 14:55 [ET]
Event Date: 06/25/2004
Event Time: [PDT]
Last Update Date: 07/27/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RUSSELL BYWATER (R4)
PATRICIA HOLAHAN (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING A STOLEN/RECOVERED RADIOGRAPHY CAMERA
The following information was provided by the State of Washington to the NRC via email:
"This is notification of an event in Washington State as reported to or investigated by the WA Department of Health, Office of Radiation Protection.
"STATUS: new
"Licensee: Northwest Inspection
"City and State: Richland, Washington
"License Number: WN-IR065-1
"Type of License: Industrial Radiography
"Date of Event: 25 June 2004 (reported July 26)
"Location of Event: Spokane, Washington
"ABSTRACT: (where, when, how, why; cause, contributing factors, corrective actions, consequences, Dept. of Health (DOH) on-site investigation; media attention):
"The licensee's radiation safety officer reported that they had had a radiography vehicle stolen, with a radiography exposure device secured inside (device and source information not yet known). The Radiographer, at the end of the day, had left the radiography vehicle unattended while that Radiographer entered a work-site office to complete paperwork. The Assistant Radiographer had left the work-site earlier when actual radiography had concluded.
"During the brief time the vehicle was unattended, reported to be about 2 minutes, the vehicle was taken. The Radiographer called the police and the radiation safety officer when the vehicle was noticed missing.
"A short time later, reported to be about 30 minutes, a Spokane area resident noticed the truck, stuck by the side of the road. The resident used licensee identification, from the outside of the vehicle, to contact the licensee. The licensee had the resident call local police. The police secured the vehicle. Later, the licensee recovered the vehicle. The locked camera storage/transportation container had not been disturbed.
"No Media attention noted.
"Notification Reporting Criteria: 10 CFR, Part 20.2201(a)(1)(ii)
"Isotope and Activity involved: Not yet known
"Overexposures? (number of workers/members of the public; dose estimate; body part receiving dose; consequence): None, N/A
"Lost, Stolen or Damaged? (mfg., model, serial number): Stolen (briefly), camera and source information is not yet known.
"Disposition/recovery: Recovered without additional incident.
"Leak test? Not yet known
"Vehicle: (description; placards; Shipper; package type; Pkg. ID number)
"The vehicle is a combination of pick-up truck with industrial trailer. The trailer serves as the darkroom and camera storage. No placards since package was a Yellow II. Type B package inside a convenience over-pack.
"Release of activity? None, N/A
"Event Report # WA-04-043" |
| Power Reactor | Event Number: 40909 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN WEBERS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 07/30/2004
Notification Time: 12:51 [ET]
Event Date: 07/30/2004
Event Time: 09:45 [EDT]
Last Update Date: 07/30/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| 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 REACTOR CORE ISOLATION COOLING (RCIC) TURBINE FAILED TO ACHIEVE DESIGN PRESSURE AND FLOW DURING SURVEILLANCE TESTING
The following information was obtained from the licensee via facsimile:
"During a surveillance of the Reactor Core Isolation Cooling system (RCIC), the RCIC turbine failed to achieve design pressure and flow. Other safety systems, including the High Pressure Coolant Injection (HPCI) system, are available.
"This failure is believed to be due to a RCIC flow controller problem. Investigation is continuing."
Design pressure/flow is 1250 psig/400 gpm. Actual pressure/flow was 1220 psig/350 gpm.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40910 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: ARTHUR MOORE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 07/30/2004
Notification Time: 13:58 [ET]
Event Date: 07/30/2004
Event Time: 10:00 [PDT]
Last Update Date: 07/30/2004 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
RUSSELL BYWATER (R4)
TERRY REIS (NRR)
BILL BORCHARDT (NRR)
RICHARD WESSMAN (IRD)
BRUCE MALLET (R4)
ELIOT BRENNER (OPA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text ALERT DECLARED AT COLUMBIA GENERATING STATION
The following information was obtained by the licensee via facsimile:
"Reactor SCRAM received at 0924 [hrs] PDT. Initial indications are the scram signal was caused by RPS [Reactor Protection System] High Pressure. Following the scram, 2 [two] control rods did not immediately indicate [fully inserted]. Control room staff entered [procedure] PPM5.1.2 and took the required actions. All control rods subsequently indicated [fully inserted].
"An ALERT Classification was declared at 1000 [hrs] based on PPM 13.1.1 Criteria 2.2.A.1, 'RPS Setpoint exceeded and automatic actions failed to result in a rod pattern which alone assures reactor shutdown'. Manual actions resulted in all rods [fully inserted] and reactor power [less than or equal to] 5 percent.
"All other plant systems responded as expected with the exception of a wetwell-to-drywell vacuum breaker which indicates open. Investigation into the cause of the scram and actual control rod position is ongoing. Further details will be provided when available."
The licensee also reports that no relief valves lifted during the transient. Decay heat removal is via the main condenser. Reactor level is steady at 36 inches. Reactor temperature and pressure are 507 degrees and 710 psig respectively. Offsite power is available. All emergency systems are available in standby.
The licensee has notified the NRC Resident Inspector of the incidents. The NRC entered Monitoring mode at 1327 hrs EDT with Region IV leading. The NRC exited Monitoring at 1530 hrs. EDT and returned to Normal mode.
Notified HHS (Ayles) as well as others noted in notification block.
* * * UPDATE AT 2130 HRS EDT ON 7/30/04 FROM COLEMAN TO CROUCH * * *
"At 1358 [hrs.] EDT on 7/30/04, NRC was notified of an Alert at Columbia Generating Station (EN #40910).
"This is a follow-up to inform NRC that the event was terminated at 1457 [hrs] (EDT) (1157 PDT). All control rods are inserted. Reactor is shutdown and water level is normal. All required emergency systems are operable. All offsite and onsite power sources are operable. Reactor pressure is normal."
The licensee has notified the NRC Resident Inspector, State of Washington and local authorities of the termination.
The NRC Operations Center notified R4DO(Bywater), DHS, FEMA, DOE(NRC), USDA, EPA and CDC(HHS). |
| General Information or Other | Event Number: 40911 | Rep Org: U.S. DEPARTMENT OF ENERGY
Licensee: RADECO, LLC
Region: 4
City: RICHLAND State: WA
County: BENTON
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN H. SWAILES
HQ OPS Officer: HOWIE CROUCH | Notification Date: 07/30/2004
Notification Time: 12:39 [ET]
Event Date: 07/30/2004
Event Time: [PDT]
Last Update Date: 07/30/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
JAMES TRAPP (R1)
THOMAS DECKER (R2)
JOHN MADERA (R3)
RUSSELL BYWATER (R4)
| Event Text PART 21 SAFETY HAZARD WITH RADECO PORTABLE AIR SAMPLER MODEL H-809VI
The U.S. Department of Energy, Office of River Protection in Richland, WA has identified a potential safety issue with Radeco portable air sampler model H-809VI. This type of portable air sampler is utilized in the commercial nuclear industry.
A Health Physics Technician experience a mild shock while handling a Radeco portable air sampler when the sample holder was touched. Radeco has issued a recommendation or opinion for H-809V series electrical grounding.
Facilities should check sample holders on the Radeco H-809 and H-810 series samplers to assure proper grounding and no voltage on the sample holder. |
| Power Reactor | Event Number: 40912 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: Mike MacLENNAN
HQ OPS Officer: JOHN MacKINNON | Notification Date: 07/31/2004
Notification Time: 01:28 [ET]
Event Date: 07/30/2004
Event Time: 21:25 [CDT]
Last Update Date: 07/31/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JOHN MADERA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 85 | Power Operation | 85 | Power Operation | Event Text LPCI LOOP SELECT LOGIC FOUND DEGRADED DUE TO PRESSURE INSTRUMENTS OUT-OF-TOLERANCE
"On July 30, 2004 at approximately 2125 hours CDT, Instrument Maintenance personnel were performing the Unit One Reactor Low Pressure (RHR/LPCI) Calibration and Functional Test. At this time, the technicians determined that two out of the four "Reactor Steam Dome Pressure - Low" switches in LPCI loop select logic were out of tolerance high. These switches delay completion of the LPCI loop select logic during Single Loop Reactor Recirculation Pump operations (SLO) until the reactor pressure is less than 900 psig. With these switches out of tolerance high, LPCI loop select logic sensitivity was degraded, increasing the potential to select the wrong loop for injection during periods of SLO. At the time of discovery, both Reactor Recirculation pumps were in operation.
"Both switches were recalibrated immediately upon discovery to within Technical Specification tolerances."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 40913 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Dann R. Dailey
HQ OPS Officer: JOHN MacKINNON | Notification Date: 07/31/2004
Notification Time: 03:20 [ET]
Event Date: 07/30/2004
Event Time: 18:45 [MST]
Last Update Date: 07/31/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RUSSELL BYWATER (R4)
SUZANNE BLACK (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text AIR VOID IN POST-LOCA RECIRCULATION PIPING SYSTEM
"On July 30, 2004, at approximately 18:45 Mountain Standard Time (MST), Palo Verde Nuclear Generating Station Units 1, 2, and 3 were operating at approximately 100% power at normal operating temperature and pressure when it was discovered that a void in the post-LOCA (Loss Of Coolant Accident) recirculation piping from the containment sump may have prevented fulfillment of the safety function to remove residual heat and mitigate the consequences of a Loss of Coolant Accident. The volume of the ECCS (Emergency Core Cooling System) piping sections between the closed containment sump isolation butterfly MOVs (SIAUV0673/0674 and SIBUV0675/0676) and the associated train sump recirculation check valves (SIAV205 and SIBV206) are void of water and occupied with air (Approx. 120 cubic feet). The concern is that during a Recirculation Actuation Signal (RAS) the trapped volume of air between the isolation valves and the downstream check valve cold potentially enter the operating SI pumps (HPSI and CS), which could potentially cause cavitations and/or air binding of the pumps or possibly a water hammer event.
"RAS does not occur for approximately 20 minutes, or longer following a LOCA. In accordance with Generic Letter 91-18, substitution of manual action for automatic action to open the inner containment sump isolation valves following a LOCA, but prior to the RAS setpoint will allow the void to clear, with the exception of a small section between the outer containment isolation valve and the check valve. Engineering had provided reasonable assurance that the recirculation check valve void will not result in an unacceptable void fraction forming in the HPSI/Containment Spray pump suction piping and pump.
"The Control Room Operators have been briefed on the need to perform the manual Operator action to open the inboard ECCS Sump isolation valves (SIAUV673 and SIBUV675) upon receipt of a Containment Spray Actuation System (CSAS) actuation. Each Shift Crew will be briefed accordingly until the EOPs are revised to incorporate this action (will take about 24 hours to be incorporated).
"Engineering continues to evaluate this condition.
"There were no RPS/ESF actuations, and none were required.
"There were no structures, systems or components that were inoperable at the start of (the) event that contributed to the event.
"This condition did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. This condition did not adversely affect the safe operation of the plant or health and safety of the public."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 40914 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: RANDY HODGSON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 07/31/2004
Notification Time: 11:49 [ET]
Event Date: 07/30/2004
Event Time: 21:20 [CDT]
Last Update Date: 07/31/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
RUSSELL BYWATER (R4)
|
| 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 SUSPECTED DRUG PARAPHERNALIA FOUND IN THE PROTECTED AREA
The following information was provided by the licensee via facsimile:
"Drug paraphernalia [a baggie and rolling paper] was found by the turbine building operator in a trash container located on the turbine building mezzanine level. The turbine building operator was emptying the container at the time. The paraphernalia was turned over to the security shift supervisor. Security is confident, based on a veteran law enforcement officer's experience, that the empty bag found in the trash once contained an illegal substance. Further confirmation by testing will be determined on Monday. Our procedure SO-R-1 requires FCS [Fort Calhoun Station] to make a 24-hour report to the NRC per 10CFR26.73."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/31/04 AT 1317 HRS EDT FROM HODGSON TO CROUCH * * *
"The Security Shift Supervisor was notified by the Washington County Sheriff Department that the bag with the unknown substance has been tested positive for marijuana."
The licensee has notified the NRC Resident Inspector. NRC Operations Officer notified R4DO (Bywater). | |