Event Notification Report for December 27, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/26/2005 - 12/27/2005
Power Reactor
Event Number: 42232
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: WILLIAM J. BLESSIE
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: WILLIAM J. BLESSIE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/27/2005
Notification Time: 14:59 [ET]
Event Date: 12/27/2005
Event Time: 07:30 [CST]
Last Update Date: 12/27/2005
Notification Time: 14:59 [ET]
Event Date: 12/27/2005
Event Time: 07:30 [CST]
Last Update Date: 12/27/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JEFFREY CLARK (R4)
JEFFREY CLARK (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 |
TECHNICAL SUPPORT CENTER VENTILATION INOPERABLE
"During an equipment operator rounds of the onsite Emergency Response Technical Support Center the access cover for the suction plenum of VA-107, Technical Support Center Air Handling Unit, was found removed and resting on the floor under the opening exposing a 2 ft X 2 ft opening. The as-found condition would have made the Technical Support Center ventilation System inoperable with respect to maintaining Technical Support Center personnel dose limits in a design basis accident. The air handling unit is located in a mechanical room outside the Technical Support Center envelope. With the access cover removed, air from the mechanical room would be drawn into the air handling unit and discharged into the Technical Support Center, in a design basis accident, the as-found condition would allow an undesirable amount of unfiltered air into the Technical Support Center envelope. This condition does not adversely affect the charcoal filtering unit, VA-119, from drawing outside air required to maintain the Technical Support Center in a positive pressure envelope. The cause of the access cover being removed could not be determined, the access cover was re-installed at 08:15 CST and a maintenance work document generated to verify proper operation of latches. This report is being made under 10 CFR 50.72(b)(3)(xiii) since the as-found condition impaired the licensee's ability to staff the Technical Support Center during an accident. Contingency actions are in place in the Emergency Plan to deal with the evacuation of the Technical Support Center."
The licensee notified the NRC Resident Inspector.
"During an equipment operator rounds of the onsite Emergency Response Technical Support Center the access cover for the suction plenum of VA-107, Technical Support Center Air Handling Unit, was found removed and resting on the floor under the opening exposing a 2 ft X 2 ft opening. The as-found condition would have made the Technical Support Center ventilation System inoperable with respect to maintaining Technical Support Center personnel dose limits in a design basis accident. The air handling unit is located in a mechanical room outside the Technical Support Center envelope. With the access cover removed, air from the mechanical room would be drawn into the air handling unit and discharged into the Technical Support Center, in a design basis accident, the as-found condition would allow an undesirable amount of unfiltered air into the Technical Support Center envelope. This condition does not adversely affect the charcoal filtering unit, VA-119, from drawing outside air required to maintain the Technical Support Center in a positive pressure envelope. The cause of the access cover being removed could not be determined, the access cover was re-installed at 08:15 CST and a maintenance work document generated to verify proper operation of latches. This report is being made under 10 CFR 50.72(b)(3)(xiii) since the as-found condition impaired the licensee's ability to staff the Technical Support Center during an accident. Contingency actions are in place in the Emergency Plan to deal with the evacuation of the Technical Support Center."
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 42233
Rep Org: ROSEMOUNT NUCLEAR INSTRUMENTS
Licensee: ROSEMOUNT NUCLEAR INSTRUMENTS
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: N
Docket:
NRC Notified By: DAVID ROBERTS
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: ROSEMOUNT NUCLEAR INSTRUMENTS
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: N
Docket:
NRC Notified By: DAVID ROBERTS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/27/2005
Notification Time: 18:14 [ET]
Event Date: 12/27/2005
Event Time: 00:00 [CST]
Last Update Date: 12/28/2005
Notification Time: 18:14 [ET]
Event Date: 12/27/2005
Event Time: 00:00 [CST]
Last Update Date: 12/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MARVIN SYKES (R1)
MARK LESSER (R2)
DAVID HILLS (R3)
JEFFREY CLARK (R4)
CORNELIUS HOLDEN (NRR)
MARVIN SYKES (R1)
MARK LESSER (R2)
DAVID HILLS (R3)
JEFFREY CLARK (R4)
CORNELIUS HOLDEN (NRR)
PART 21 NOTIFICATION FOR ROSEMOUNT TRANSMITTERS
The Supplier provided this notification via facsimile and is summarized below:
A multi-meter used in the calibration of certain pressure instruments went out of calibration between 10/10/2005 and 11/18/2005. These instruments may not conform to the published accuracy specification of +/- 0.25% of calibrated span. Rosemont Nuclear Instruments, Inc (RNII) successfully recalibrated all affected transmitters that had not yet shipped from its facility. The instruments affected by this failure are:
"(a) certain Model 1152 gage and differential pressure transmitters with model codes beginning with 1152GP, 1152DP, or 1152HP, inclusive of pressure measuring range codes 3, 4, 5, and 6 (the range code is the 7th position in the model string); and
"(b) certain Model 1153 Series B and 1153 Series D gage and differential pressure transmitters with model codes beginning with 1153GB, 1153DB, 1153HB, 1153GD, 1153DD, or 1153HD inclusive of pressure measuring range codes 3, 4, 5, and 6 (the range code is the 7th position in the model string); and
"(c) certain Model 1154 and 1154 Series H gage and differential pressure transmitters with model codes beginning with 1154GP, 1154DP, 1154HP, 1154DH, or 1154HH inclusive of pressure measuring range codes 4, 5, and 6 (the range code is the 7th position in the model string).
"The end user must determine the impact of this potential non-conformance on its plant operations and safety and take action as deemed necessary. If an affected pressure transmitter has been successfully calibrated after receipt from RNII or will be calibrated prior to installation, no further action should be required."
* * * UPDATE FROM ROSEMOUNT NUCLEAR INSTRUMENTS (D. ROBERTS) TO M. RIPLEY AT 0927 ET 12/28/05 * * *
Rosemount provided the following information via facsimile:
"Yesterday, Rosemount Nuclear Instruments, Inc. (RNII) submitted a notification under 10 CFR Part 21. The submission to the NRC did not include Attachment A, which lists all of the affected U.S. licensees. This fax includes the letter and the attachment. RNII has initiated communication with its customers. The notification letter and attachment A have been sent to each of the affected customers."
Attachment A provides Purchase Order Numbers, Model Numbers, Serial Numbers, and Calibration Dates for instruments provided to the following affected licensees: Dominion Generation, First Energy Corporation, Progress Energy Carolinas, Georgia Power Co., and Southern Nuclear Operating Co.
Notified R1 DO (M. Sykes), R2 DO (M. Lesser), R3 DO (D. Hills), R4 DO (J. Clark), NRR (C. Holden and O. Tabatabai)
The Supplier provided this notification via facsimile and is summarized below:
A multi-meter used in the calibration of certain pressure instruments went out of calibration between 10/10/2005 and 11/18/2005. These instruments may not conform to the published accuracy specification of +/- 0.25% of calibrated span. Rosemont Nuclear Instruments, Inc (RNII) successfully recalibrated all affected transmitters that had not yet shipped from its facility. The instruments affected by this failure are:
"(a) certain Model 1152 gage and differential pressure transmitters with model codes beginning with 1152GP, 1152DP, or 1152HP, inclusive of pressure measuring range codes 3, 4, 5, and 6 (the range code is the 7th position in the model string); and
"(b) certain Model 1153 Series B and 1153 Series D gage and differential pressure transmitters with model codes beginning with 1153GB, 1153DB, 1153HB, 1153GD, 1153DD, or 1153HD inclusive of pressure measuring range codes 3, 4, 5, and 6 (the range code is the 7th position in the model string); and
"(c) certain Model 1154 and 1154 Series H gage and differential pressure transmitters with model codes beginning with 1154GP, 1154DP, 1154HP, 1154DH, or 1154HH inclusive of pressure measuring range codes 4, 5, and 6 (the range code is the 7th position in the model string).
"The end user must determine the impact of this potential non-conformance on its plant operations and safety and take action as deemed necessary. If an affected pressure transmitter has been successfully calibrated after receipt from RNII or will be calibrated prior to installation, no further action should be required."
* * * UPDATE FROM ROSEMOUNT NUCLEAR INSTRUMENTS (D. ROBERTS) TO M. RIPLEY AT 0927 ET 12/28/05 * * *
Rosemount provided the following information via facsimile:
"Yesterday, Rosemount Nuclear Instruments, Inc. (RNII) submitted a notification under 10 CFR Part 21. The submission to the NRC did not include Attachment A, which lists all of the affected U.S. licensees. This fax includes the letter and the attachment. RNII has initiated communication with its customers. The notification letter and attachment A have been sent to each of the affected customers."
Attachment A provides Purchase Order Numbers, Model Numbers, Serial Numbers, and Calibration Dates for instruments provided to the following affected licensees: Dominion Generation, First Energy Corporation, Progress Energy Carolinas, Georgia Power Co., and Southern Nuclear Operating Co.
Notified R1 DO (M. Sykes), R2 DO (M. Lesser), R3 DO (D. Hills), R4 DO (J. Clark), NRR (C. Holden and O. Tabatabai)