| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/03/2004 - 06/04/2004 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40652 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: WILLIAM CARSKY
HQ OPS Officer: BILL GOTT | Notification Date: 04/06/2004
Notification Time: 19:47 [ET]
Event Date: 04/06/2004
Event Time: 14:00 [CDT]
Last Update Date: 06/03/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
BRENT CLAYTON (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 93 | Power Operation | 93 | Power Operation | Event Text AIR VALVE MISALIGNMENT REDUCES STANDBY LIQUID CONTROL CAPABILITY
"On April 6, 2004, at 1400 CDT, Clinton Power Station discovered an air valve open for the Standby Liquid Control tank sparger. The open air sparger valve caused both Standby Liquid Control pumps to be inoperable due to the potential of air binding the pumps. The valve was closed, and the Standby Liquid Control is now operable. A Prompt Investigation is being commenced to determine circumstances of this open air sparger. The condition existed for approximately five weeks."
The system was restored at approximately 1500 on 4/6/04.
The Licensee notified the NRC Resident Inspector.
* * * UPDATE 1840 EDT ON 6/3/04 FROM ED TIEDEMANN TO S. SANDIN * * *
This report is retracted based on the following:
"During further investigation, a calculation was performed to detail the air entrainment into the SLC pumps and the results show that air entrainment from the air sparger would not reduce system flow below that required by Technical Specifications. Therefore, it was determined that the system design is such that whenever the air sparge valve to the Standby Liquid Control (SLC) tank is open, the pumps remain operable and capable of performing their safety function. Thus, this occurrence (EN #40652 dated 4/6/04) was not reportable under 10CFR50.72(B)(3)(V)(A) and 10CFR50.72(B)(3)(V)(D).
"The Licensee notified the NRC Resident Inspector."
Notified R3DO (Lanksbury). |
| General Information or Other | Event Number: 40783 | Rep Org: ROTORK CONTROLS INC
Licensee: ROTORK CONTROLS INC
Region: 1
City: ROCHESTER State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KAREN BLACK
HQ OPS Officer: MIKE RIPLEY | Notification Date: 05/28/2004
Notification Time: 15:51 [ET]
Event Date: 05/28/2004
Event Time: [EDT]
Last Update Date: 06/03/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
RICHARD CONTE (R1)
DAVID AYRES (R2)
SONIA BURGESS (R3)
MIKE RUNYAN (R4)
NRR PART 21 CONTACTS (NRR)
NMSS PART 21 CONTACT (NMSS)
| Event Text PART 21 NOTIFICATION - VALVE ACTUATOR SWITCH MECHANISMS
"Basic Component Affected
Rotork NA1 switch mechanism assemblies manufactured between 1978 (post 78 build) and November 2001 supplied either as a spares item or fitted in an NA1 type Electric Valve Actuator. Customers supplied with potentially affected actuators manufactured between January 1998 and November 2001, were previously notified individually of this condition and may have completed the risk assessment and corrective action detailed below. This report extends the affected time frame, potentially affecting actuators not identified on the original notifications.
"Rotork NA4, NA5, NA1E and NAE5 type Electric Valve Actuators are not affected.
"Nature of the Defect and Associated Safety Hazard
It has recently been identified that the molded (PPS) components within the switch mechanism assembly have a low level of crystallinity and it cannot be confirmed that they are to the same specification as those originally tested and qualified at Wyle in 1978 (refer test report 43979-1 Rev A).
Effect on Functionality
The report provides a detailed explanation of the effect on function depending on the valve position and open/close action.
"NA4 and NAS type Electric Valve Actuators have a maximum ambient temperature rating of 70 deg C (160 deg F) and are not affected. NA1 type Electric Valve Actuators have the same ambient temperature rating but can be subject to a loss of coolant accident (LOCA). The condition reported will only affect Valve Actuators in plant locations where: 1) the LOCA and Operational temperature specifications, as defined in the Design Basis Document for each facility and location, could result in the switch mechanism components exceeding 80 deg C (176 deg F) and 2) The switch mechanism fitted was manufactured between 1978 and November 2001 and 3) The actuator is exposed to the two conditions outlined in section 2.0 of the report."
* * * UPDATE AT 1200 EDT ON 6/03/04 TO S. SANDIN VIA FAX * * *
A revision to this report changes the Rotork model number from NAE5 to NA5E.
Notified R1DO (Jenison), R2DO (Fredrickson), R3DO (Lanksbury), R4DO (Sanborn), NMSS Part 21 Coordinator (Torres) and NRR Part 21 Coordinator (Hodge) via fax. |
| Power Reactor | Event Number: 40788 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STAN GAMBLE
HQ OPS Officer: ARLON COSTA | Notification Date: 06/03/2004
Notification Time: 12:47 [ET]
Event Date: 06/03/2004
Event Time: 12:45 [EDT]
Last Update Date: 06/03/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
KENNETH JENISON (R1)
TERRY REIS (NRR)
PAUL FREDRICKSON (R2)
ROGER LANKSBURY (R3)
GARY SANBORN (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text PART 21 NOTIFICATION OF FAILURE OF SPRING CHARGING FUNCTION IN CIRCUIT BREAKER
"Limerick has completed the 10CFR Part 21 evaluation of the failure of the spring charging function on an Asea Brown Boveri (ABB) Model HK circuit breaker. The investigation determined that the primary contributor to the failure was the replacement of ABB latch reset torsion spring number 195205A00 with a weaker spring that was supplied with the breaker overhaul kit number 716656T104. Secondary contributors to the failure were normal wear on additional parts in the operating mechanism.
"ABB supplied a six-turn latch reset torsion spring and a five-turn latch reset torsion spring under spring part number 195205A00 and overhaul kit number 716656T104. The spring of concern is a six-turn spring that does not provide as much force as the original six-turn or five-turn spring. When informally tested during the investigation the six-turn spring provided approximately 66 ounces of force and the five-turn spring provided approximately 102 ounces of force. The original six-turn spring provided a force of 88 ounces.
"Limerick's evaluation concluded that installation of the replacement six-turn latch reset torsion spring could create a substantial safety hazard depending on the breaker's application. Therefore, this notification is being submitted pursuant to the requirements of 10CFR21.21(d)(3)(i). The required 10CFR21.21(d)(3)(ii) 30-day written notification will provide more detail when submitted. ABB evaluation of this issue is still in progress."
The licensee notified the NRC Resident Inspector. |
| General Information or Other | Event Number: 40790 | Rep Org: FLEIS AND VANDERBRINK
Licensee: FLEIS AND VANDERBRINK
Region: 3
City: GRAND RAPIDS State: MI
County:
License #: 2126580-01
Agreement: N
Docket:
NRC Notified By: PAUL GALDES
HQ OPS Officer: ARLON COSTA | Notification Date: 06/03/2004
Notification Time: 19:52 [ET]
Event Date: 06/03/2004
Event Time: 18:00 [EDT]
Last Update Date: 06/03/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
ROGER LANKSBURY (R3)
THOMAS ESSIG (NMSS)
| Event Text VEHICLE ACCIDENT WHILE CARRYING A NUCLEAR GAUGE
A pickup truck used by the licensee during inspection services loaded with a Troxler gauge was involved in an accident. The pickup truck hit a tree and its top came loose, along with its contents, landing in an area away from the pickup. A Troxler gauge, inside its storage box, was one of the items tossed out of the pickup truck. The pickup truck caught on fire after the accident. The technician was injured during the accident and was subsequently taken to a local hospital in Springport, MI.
The burnt pickup truck was hauled away to a storage place along with the top with its contents. The Troxler gauge is inside its storage box and does not appear to be damaged. The gauge is a Troxler Model 3430, S/N 75-6542, 8 millicuries Cs-137 and 40 millicuries of Am-241/Be. The licensee's Radiation Safety Officer intends to retrieve the gauge, perform a leak test and return the gauge to the manufacturer. The licensee was requested to call the Operations Center with an update of the leak test results. | |