United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for March 6, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/05/2012 - 03/06/2012

** EVENT NUMBERS **


47693 47711 47716 47717 47718

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Part 21 Event Number: 47693
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: VINCE KLCO
Notification Date: 02/23/2012
Notification Time: 11:08 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 03/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MEL GRAY (R1DO)
MIKE ERNSTES (R2DO)
PATTY PELKE (R3DO)
RICK DEESE (R4DO)
PART 21 GRP - EMAIL ()

Event Text

PART 21 REPORT - ROSEMOUNT PRESSURE TRANSMITTERS WITH NONZERO BASED CALIBRATIONS

The following information was received by facsimile:

"During the course of qualification testing to replace certain diodes identified for obsolescence, RNII [Rosemount Nuclear Instruments, Inc.] has determined that Model 1154 Series H range code 4-8 pressure transmitters with a significantly elevated or suppressed 4 mA point may not meet the published steam pressure/temperature accuracy specification.

"The out of tolerance condition observed during steam pressure/temperature qualification testing is not related to the replacement diode changes. It is an inherent performance characteristic related to large zero elevation or suppression. The steam pressure/temperature accuracy specification will be revised to account for nonzero based calibrations with a significantly elevated or suppressed 4 mA point.

"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification.

"RNII recommends that users review the application where 1154 Series H range code 4-8 pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature specification."

Rosemount Nuclear has provided instruments to the following list of domestic U.S. customers: Alabama Power; American Electric Power; Arizona Public Service/Pinnacle West; Bechtel Power; Constellation Energy; Dominion Nuclear Connecticut/Dominion Generation; Duke Energy; ECFS MCS; Edison Material Supply; Electro Mechanics; Entergy; Exelon Generation; Florida Power and Light; FPL Energy; Georgia Power; Northern States Power-Minnesota DBA XCEL Energy; Pacific Gas and Electric; Progress Energy Florida; Progress Energy Carolinas; PSEG Nuclear; South Carolina Electric and Gas; Southern California Edison; Southern Nuclear Operating Company; STP Nuclear Operating; Tennessee Valley Authority; TXU/Luminant; Westinghouse Electric.

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Agreement State Event Number: 47711
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: ACCURATE NDE & INSPECTION, L.L.C.
Region: 4
City: BROUSSARD State: LA
County:
License #: LA-10207-L01
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: PETE SNYDER
Notification Date: 03/01/2012
Notification Time: 09:26 [ET]
Event Date: 01/31/2012
Event Time: [CST]
Last Update Date: 03/01/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN LANTZ (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - POSSIBLE EXCEEDANCE OF ANNUAL DOSE LIMIT

The following information was received from the State of Louisiana via facsimile:

"[An individual's] badge received 2709 mRem for December 2011, which gave him a yearly exposure of 5609 mRem for 2011. [The individual had] performed radiography for the first fifteen days of December. [During] the second half of December he worked on paperwork before leaving the company. He had left his personal radiation monitoring equipment in the front compartment of the x-ray rig truck during the second half of December."

The State of Louisiana will investigate.

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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: 03/05/2012
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.

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Power Reactor Event Number: 47717
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JORGE O'FARRIL
HQ OPS Officer: KARL DIEDERICH
Notification Date: 03/05/2012
Notification Time: 14:46 [ET]
Event Date: 03/05/2012
Event Time: 11:36 [EST]
Last Update Date: 03/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)

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

LOSS OF TONE ALERT RADIO SYSTEM

"At 1303 EST on March 5, 2012, with the James A. FitzPatrick (JAF) Nuclear Power Plant operating at 100% reactor power, Oswego County Emergency Management notified JAF that the National Weather Service had notified them that the Tone Alert Radios had been out of service since 1136 EST on March 5, 2012. The Tone Alert Radio System was restored at 1327 EST on March 5, 2012.

"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) Population for the Nine Mile Point and JAF Nuclear Power Plants. This failure meets NRC 8 hour reporting criterion 10 CFR 50.72(b)(3)(xiii). The County Alert Sirens which also function as part of the Public Prompt Notification System remain operable.

"The loss of the Tone Alert Radios constitutes a significant loss of emergency off-site communications ability. Compensatory measures were verified to have been available. This consists of utilizing the hyper reach system which is a reverse 911 feature available from the county 911 center. Local Law Enforcement Personnel were also available for 'Route Alerting' of the affected areas of the EPZ."

The portion of the EPZ population affected is approximately 10%.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47718
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BENJAMIN GEISS
HQ OPS Officer: KARL DIEDERICH
Notification Date: 03/05/2012
Notification Time: 15:39 [ET]
Event Date: 03/05/2012
Event Time: 12:36 [EST]
Last Update Date: 03/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)

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

LOSS OF TONE ALERT RADIO SYSTEM

"On Monday, March 5, 2012, at 1305 EST, Oswego County Warning Point notified Nine Mile Point [NMP] and NYS [New York State] Warning Point, via the RECS Line, of a loss of the Tone Alert System for greater than one hour as of 1236 EST from the National Weather Service. Site Emergency Procedures define a loss of Tone Alert System for greater than one hour as a significant loss of Emergency Communications (EPlP-EPP-30).

"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) Population for the NMP and JAF [James A. FitzPatrick] Nuclear Power Plants. This failure meets NRC 8-hour reporting criteria 10 CFR 50.72(b)(3)(xiii).

"The County Alert Sirens, which also function as part of the Public Prompt Notification System, remained operable.

"The loss of the Tone Alert System constitutes a significant loss of emergency off-site communications capability. Compensatory measures were verified to be available should the Prompt Notification System be needed. This consists of utilizing the hyper-reach system, which is a reverse 911 feature available from the county 911 center. Local law enforcement personnel are also available for 'Route Alerting' of the affected areas of the EPZ.

"As of 1327 EST on March 5, 2012, Nine Mile Point was notified by the Oswego County Warning Point that the Tone Alert System has been returned to service."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012