United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for April 4, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/03/2012 - 04/04/2012

** EVENT NUMBERS **


47716 47792 47800 47801 47802 47803

To top of page
Part 21 Event Number: 47716
Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DUYEN PHAM
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/02/2012
Notification Time: 16:51 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 04/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
MARK FRANKE (R2DO)
MARK RING (R3DO)
JACK WHITTEN (R4DO)
PART 21 GROUP-EMAIL ()

Event Text

PART 21 REPORT - ROSEMONT PRESSURE TRANSMITTERS OUT OF TOLERANCE CONDITION

The following information was received by facsimile:

"During the course of qualification testing to replace certain diodes identified for obsolescence, an out of tolerance condition during steam pressure/temperature testing was observed on a test pressure transmitter in the qualification program. Through investigation into the out of tolerance condition, it was determined that the condition was not related to the replacement diode, but rather the result of the magnitude of a resistance change made to the transmitter temperature compensation circuitry during a final factory acceptance test. A brief description of the final acceptance test follows.

"During pressure transmitter final processing, a test is conducted on Model 1154 Series H pressure transmitters to assess the effects of ambient temperature changes on the 4mA to 20mA analog output. The temperature test is performed on each transmitter to verify the transmitter accuracy performance over normal operating temperatures from 40 F to 200 F. If the transmitter does not meet the acceptance criteria for the test, changes can be made to the compensating resistor values to optimize performance in the normal operating temperature range. If the resistance adjustment is too large, it has been determined that the accuracy of the pressure transmitter relative to the published steam pressure/temperature profile and accuracy specification may be exceeded during a steam pressure/temperature event.

"The magnitude of output shift during steam pressure/temperature conditions, that is attributable to the resistance changes made in final processing, is predictable based on the specific amount of resistance added or subtracted during the compensation process for each transmitter. Accordingly, RNII [Rosemount Nuclear Instruments, Inc] has reviewed the production records for the potentially affected transmitters and a revised steam pressure/temperature accuracy specification has been established for each shipped pressure transmitter. The revised steam pressure/temperature accuracy specification has been listed by serial number.

"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification. Also note that for certain calibrations with large zero elevation and suppressions as defined in RNII's Part 21 Notification, dated February 23, 2012, an alternate steam pressure/temperature accuracy specification is also provided for pressure transmitters that are affected by both notifications. All other 1154 Series H published specifications remain unchanged.

"On February 23, 2012, it was concluded that a substantial safety hazard may exist. RNII does not have sufficient information to determine the potential safety impact in plant applications. As a result, a notification about the potential substantial safety hazard is being made in accordance with 10 CFR Part 21 to customers who purchased affected 1154 Series H pressure transmitters.

"The manufacturing rework procedure 01153-3000 has been updated to limit the amount of acceptable resistance that may be added or subtracted during final testing. A revised steam pressure/temperature accuracy specification for each pressure transmitter impacted by this notification has been determined.

"RNII recommends that users review the application where 1154 Series H pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature accuracy specification."

The United States nuclear sites associated with this Part 21 are: Farley, D.C. Cook, Palo Verde, ANO-1, Calvert Cliffs, Point Beach, Oconee, Catawba, Waterford 3, Braidwood, La Salle, Davis Besse, Crystal River 3, Vogtle, Millstone, Diablo Canyon, Salem, Hope Creek, San Onofre, South Texas, Watts Bar, Comanche Peak, Wolf Creek, St. Lucie, Dominion Energy - Unspecified, and Northeast Nuclear Energy - Unspecified.


* * * UPDATE FROM DUYEN PHAM TO PETE SNYDER ON 4/3/12 AT 1531 EDT * * *

The following information was received by facsimile:

This revision potentially affects the following commercial nuclear power plant sites in the United States:
1. Calvert Cliffs, 2. Millstone, 3. Hope Creek, 4. Salem, 5. Catawba, 6. Crystal River, 7. Farley, 8. Oconee, 9. St. Lucie, 10. Vogtle, 11. Watts bar, 12. Braidwood, 13. Davis Besse, 14. D.C. Cook, 15. LaSalle, 16. Point Beach, 17. Arkansas Nuclear One, 18. Comanche Peak, 19. Diablo Canyon, 20. Palo Verde, 21. San Onofre, 22. South Texas Project, 23. Waterford 3, and 24. Wolf Creek.

"Note: Notification #1 [EN #47693], dated 23 February 2012 (and revised on 2 April 2012) impacts ALL 1154 Series H pressure transmitters range codes 4 to 8 shipped since 1988. This does NOT impact the 1154SH9 since the 1154SH9 has a wider steam pressure/temperature specification. The revised specification is the same for all affected transmitters.

"Note: Notification #2 [this report - EN #47716], dated 2 March 2012 (and revised as of today [3 April 2012]) impacts only a subset of 1154 Series H pressure transmitters range codes 4 to 9 shipped from March 1994 to February 2012. This is a smaller affected population and does include the range 9 in the scope. The revised specification for this second issue is serial number dependent and only affects the transmitters listed in Appendix A [of the full part 21 report]."

Notified R1DO(Caruso), R2DO(McCoy), R3DO(Bloomer), R4DO(Haire), and Part 21 Group via email.

To top of page
Agreement State Event Number: 47792
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: UNKNOWN
Region: 4
City: TEMPE State: AZ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/30/2012
Notification Time: 16:36 [ET]
Event Date: 03/28/2012
Event Time: 13:35 [MST]
Last Update Date: 03/30/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
CHRISTEPHER MCKENNEY (FSME)

Event Text

AGREEMENT STATE REPORT - A MOISTURE DENSITY GAUGE WAS FOUND IN BUILDING

The following information was received from the State of Arizona via email:

"At approximately 10:00 AM on March 28, 2012, the Agency [Arizona Radiation Regulatory Agency (ARRA)] was informed that radioactive material had been detected by the Tempe, AZ Fire Department in an old flour mill. The Agency [ARRA] dispatched a response team to the site to locate and confirm information. The response team determined that the isotope involved is Cesium-137 and based on the label information approximately 25 millicuries remain in the device. The device is labeled on the accessible surfaces as a Kay Ray Model 7107 gauge and also as a Model 7519B gauge assembly SN 13454. Based on the site history and the labels, it appears that the device was transferred to Bay State Milling in the 4th quarter of 1980 or the 1st quarter of 1981. The Agency [ARRA] did not issue a specific license for this site. We assume that the device was transferred as a GL (Generally Licensed) device and remained in use into 1998. Only about 10% of the site has been surveyed thus far. The site security is being maintained by the Tempe FD (Fire Department).

"The Agency [ARRA] is now searching historical records for information, including any other devices on site.

"The Agency [ARRA] continues its investigation."

Arizona Report #: 12-008

To top of page
Power Reactor Event Number: 47800
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/03/2012
Notification Time: 05:57 [ET]
Event Date: 04/03/2012
Event Time: 05:24 [EDT]
Last Update Date: 04/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

SPDS AND ERDS REMOVED FROM SERVICE FOR PLANNED MAINTENANCE

"On 4/03/12 at 0524 EDT, the Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 80 hours. During this time, the majority of the control room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 5, and will remain in Mode 5, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10 CFR 50.72(b)(3)(xiii).

"Follow up notification will be made when SPDS and ERDS have been restored."

The licensee has notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 47801
Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRAD LEWIS
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/03/2012
Notification Time: 07:36 [ET]
Event Date: 04/03/2012
Event Time: 08:00 [EDT]
Last Update Date: 04/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

UNIT 2 PLANT PROCESS COMPUTER OUT-OF-SERVICE FOR PLANNED MAINTENANCE

"The Unit 2 DC Cook Nuclear Plant (CNP) Plant Process Computer (PPC) will be removed from service on Tuesday, April 3, 2012 at 0800 EDT to support scheduled maintenance. This will cause the entire Unit 2 PPC, including the ERDS [Emergency Response Data System] to be unavailable to the NRC Operations Center. The planned maintenance also affects the Safety Parameter Display System (SPDS), the Real Time Data Repository (RDR), and PPC data to Emergency Response Facilities at CNP.

"The scheduled maintenance, returning of equipment to service, and post maintenance testing is expected to be completed by 0000 EDT on Wednesday, April 4, 2012.

"Compensatory measures exist within the DC Cook Emergency Response procedures to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service.

"The licensee has notified the NRC Senior Resident Inspector.

"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to any event that results in a major loss of emergency assessment capability, offsite response capability, offsite communications capability (e.g. significant portion of control room indication, Emergency Notification System, or offsite notification system)."

* * * UPDATE FROM BRAD LEWIS TO CHARLES TEAL ON 4/3/12 AT 1536 EDT * * *

At time 1500 EDT, the Plant Process Computer and ERDS system has been restored to service.

The licensee has notified the NRC Resident Inspector. Notified R3DO (Dickson).

To top of page
Fuel Cycle Facility Event Number: 47802
Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: LIDIA LIBINSKI
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/03/2012
Notification Time: 11:29 [ET]
Event Date: 04/02/2012
Event Time: 15:20 [CDT]
Last Update Date: 04/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
Person (Organization):
GERALD MCCOY (R2DO)
ERIC BENNER (NMSS)

Event Text

CONTAMINATED INDIVIDUAL TREATED IN THE ON-SITE DISPENSARY FOR INJURED FINGER

"On 4/2/12 approximately at 1520 CDT a person working in the Feed Materials Building injured his finger between a drum lid and drum ring. The employee received first aid treatment in the on-site dispensary. The individual was found to have contamination on his boots. The employee was not transported to an off-site facility. The employee was released to go home at the end of his shift and appropriately exit monitored. There was no detectable contamination on the employee when he left the site."

The contamination was uranium ore concentrates.

The licensee informed NRC Region II.

To top of page
Power Reactor Event Number: 47803
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: BRIAN VANGOR
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/04/2012
Notification Time: 05:15 [ET]
Event Date: 04/04/2012
Event Time: 05:00 [EDT]
Last Update Date: 04/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JOHN CARUSO (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 48 Power Operation 43 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE STATIC INVERTER

"Indian Point 2 commenced a Technical Specification required shutdown in accordance with Limiting Condition of Operation 3.8.7, Condition B at 0500 hours on 04/04/2012 due to the inoperability of '24' Static Inverter - a component in the 118VAC Distribution System. Indian Point 2 is required to be in Mode 3 by 0802 hours. Repair of the '24' Static Inverter is in progress.

"The NRC Resident Inspector has been notified."

The licensee also notified the NY State Public Service Commission.

Page Last Reviewed/Updated Wednesday, April 04, 2012
Wednesday, April 04, 2012