Information Notice 2008-21, Impact of Non-Safety Electrical Support System Vulnerabilities on Safety Systems: Difference between revisions
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| issue date = 11/24/2008 | | issue date = 11/24/2008 | ||
| title = Impact of Non-Safety Electrical Support System Vulnerabilities on Safety Systems | | title = Impact of Non-Safety Electrical Support System Vulnerabilities on Safety Systems | ||
| author name = Dorman D | | author name = Dorman D, Shea J | ||
| author affiliation = NRC/NMSS/FCSS, NRC/RGN-II/DFFI | | author affiliation = NRC/NMSS/FCSS, NRC/RGN-II/DFFI | ||
| addressee name = | | addressee name = | ||
Line 13: | Line 13: | ||
| document type = NRC Information Notice | | document type = NRC Information Notice | ||
| page count = 4 | | page count = 4 | ||
}} | }} | ||
{{#Wiki_filter: | {{#Wiki_filter:UNITED STATES | ||
NUCLEAR REGULATORY COMMISSION | |||
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS | |||
WASHINGTON, D.C. 20555 November 24, 2008 NRC INFORMATION NOTICE 2008-21: IMPACT OF NON-SAFETY ELECTRICAL | |||
SUPPORT SYSTEM VULNERABILITIES ON | |||
SAFETY SYSTEMS | |||
ADDRESSES | |||
All holders of operating licenses for nuclear fuel facilities. | |||
==PURPOSE== | ==PURPOSE== | ||
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform addressees about potential impacts of non-safety support system failures or vulnerabilities on safety | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform | ||
Deficient fit-up with cubicles Worn or misadjusted linkages Inadequate or inappropriate maintenance practices Configuration control errors Deficiencies from original design and refurbishment Design changes Foreign material entry | |||
BWX Technologies On November 17, 2007, heavy smoke was emanating from the vicinity of an electrical | addressees about potential impacts of non-safety support system failures or vulnerabilities on | ||
Paducah Gaseous Diffusion Plant On November 23, 2004, the 480 volt Transformer Service Breaker 2PPA1 was being returned to service when a fault occurred resulting in a | |||
* Inadequate maintenance practices have resulted in gaps/clearances in the breaker mechanism becoming out of specification and preventing proper operation of the circuit | safety systems. This IN references operating experience regarding low-, medium-, and | ||
* Inadequate maintenance practices have resulted in not properly clearing and resetting the trip mechanism once the circuit breaker is fully racked into the connect position - preventing the circuit breaker from closing on | |||
* Inadequate maintenance practices have resulted in main stabs with excessive wear leading to misalignment while racking the circuit breaker into the | high-voltage circuit breakers as described in IN 2007-34 and adds similar operating experience | ||
* Inadequate maintenance practices have resulted in misalignment of the circuit breaker within the panel or | |||
* Inadequate maintenance practices have involved crimping of control power lead lugs. Faulty crimps have caused control power | of non-safety related breakers at fuel facilities. Information Notice 2007-34 is attached. | ||
* Inadequate maintenance practices have involved inadequate cleaning (including hardened greases) and greasing of the circuit breaker | |||
* Inadequate maintenance practices have caused inadvertent actuation of relays mounted on circuit breaker cubicle doors during circuit breaker | Licensees rely on non-safety electrical systems to satisfy many items relied on for safety | ||
(IROFS), technical safety requirements (TSR), or plant features (PF). For IROFS/TSRs/PFs to | |||
be considered available and reliable, they must have necessary instrumentation, controls, and | |||
normal or emergency electrical power available. | |||
It is expected that recipients will review the information for applicability to their facilities and | |||
consider appropriate actions to avoid similar problems. Suggestions contained in this IN are not | |||
NRC requirements; therefore, no specific action or written response is required. | |||
==DESCRIPTION OF CIRCUMSTANCES== | |||
The Region II Division of Fuel Facility Inspection reviewed operating experience for the past five | |||
years at both power reactors and fuel facilities related to electrical circuit breakers and found | |||
that breaker problems were often caused by the following: | |||
Deficient fit-up with cubicles | |||
===Worn or misadjusted linkages=== | |||
Inadequate or inappropriate maintenance practices | |||
===Configuration control errors=== | |||
Deficiencies from original design and refurbishment | |||
===Design changes=== | |||
Foreign material entry | |||
The following are examples of circuit breaker problems at fuel facilities: | |||
===BWX Technologies=== | |||
On November 17, 2007, heavy smoke was emanating from the vicinity of an electrical | |||
transformer. The fire, which emanated from a shorted 480 volt fuse panel, had melted nearby | |||
plastic material and caused nearby wooden material to ignite and smolder. | |||
Immediate event review by the licensee determined that an electrical surge was halted when the | |||
12.4 kilovolt gang-operated switch disconnected the power supply transformer from the utility | |||
sub-station. The licensees root causes for the fire were human performance such that the | |||
preventative maintenance on the failed breakers was not performed due to production | |||
schedules and equipment failure. (Inspection Report No. 70-27/2007008, ADAMS Accession | |||
No. ML0802503450) The licensee stated in their root cause analysis that the fire was the result | |||
of an electrical fault. The branch circuit and the main breaker feeding the transformer failed to | |||
open as designed allowing a sustained fault condition resulting in the fire. | |||
===Paducah Gaseous Diffusion Plant=== | |||
On May 20, 2003, the plant staff identified a fire in a non-safety related 480 volt circuit breaker | |||
located in the Building C-633 Pump House. The circuit breaker provided power to a motor | |||
associated with a recirculating water cooling tower fan. Due to problems within the circuit | |||
breaker, the breaker did not immediately de-energize after the fault occurred. Instead, after | |||
approximately 8 seconds, the breaker was de-energized after the setpoints associated with a | |||
back-up current limiting device were exceeded. As a result of the delayed de-energizing of the | |||
electrical breaker, other nearby breakers were damaged during the resultant fire. No personnel | |||
injuries occurred as a result of the fire and no safety-related equipment was affected. | |||
(Inspection Report No. 70-7001/2003005, ADAMS Accession No. ML032020568) | |||
===Paducah Gaseous Diffusion Plant=== | |||
On November 23, 2004, the 480 volt Transformer Service Breaker 2PPA1 was being returned to | |||
service when a fault occurred resulting in a fire. Non-safety plant equipment that should have | |||
operated to isolate the fault failed to function and, as a result, the fault remained energized for | |||
approximately 11 minutes. After the fault was isolated, the plant fire brigade used water to | |||
extinguish the fire. No release of radioactive material occurred and no plant personnel were | |||
injured; however, a significant plant transient resulted. The certificate holders root cause | |||
analysis determined that foreign material had caused the fault, and that the failure of other | |||
breakers to properly operate caused additional damage to the switchgear. Short term and long | |||
term corrective actions were initiated (Inspection Report No. 70-7001/2005001, ADAMS | |||
Accession No. ML050620142) Other Circuit Breaker Issues | |||
The NRC review of operating experience also revealed the following circuit breaker issues | |||
involving inadequate maintenance practices: | |||
* Inadequate maintenance practices have resulted in gaps/clearances in the breaker | |||
mechanism becoming out of specification and preventing proper operation of the circuit | |||
breaker. | |||
* Inadequate maintenance practices have resulted in not properly clearing and resetting | |||
the trip mechanism once the circuit breaker is fully racked into the connect position - | |||
preventing the circuit breaker from closing on demand. | |||
* Inadequate maintenance practices have resulted in main stabs with excessive wear | |||
leading to misalignment while racking the circuit breaker into the cubicle. This has led to | |||
the failure of the high-resistance stab connection, which caused an electrical fault. | |||
* Inadequate maintenance practices have resulted in misalignment of the circuit breaker | |||
within the panel or cubicle. Misalignment has led to control power contacts not | |||
connecting when the circuit breaker is racked in. Also, instances of inadequate | |||
assessment, cleaning, and testing of contacts (relay, switch, contacts, etc.) have led to | |||
the circuit breaker not operating in accordance with its design. | |||
* Inadequate maintenance practices have involved crimping of control power lead lugs. | |||
Faulty crimps have caused control power losses. There are also instances of loose | |||
connections not being identified and/or corrected. | |||
* Inadequate maintenance practices have involved inadequate cleaning (including | |||
hardened greases) and greasing of the circuit breaker mechanism. This can result in the | |||
circuit breaker mechanism and auxiliary switch not operating in accordance with their | |||
design. | |||
* Inadequate maintenance practices have caused inadvertent actuation of relays mounted | |||
on circuit breaker cubicle doors during circuit breaker maintenance. | |||
==BACKGROUND== | ==BACKGROUND== | ||
Previous Related Generic Communications: | Previous Related Generic Communications: | ||
* IN 1999-13, | * IN 1999-13, Insights from NRC Inspections of Low- and Medium-Voltage Circuit Breaker | ||
* IN 2005-21, | |||
* IN 2005-15, | Maintenance Programs (ADAMS Accession No. ML031040447) | ||
* IN 2006-18, Supplement 1, | * IN 2005-21, Plant Trip and Loss of Preferred AC Power From Inadequate Switchyard | ||
* IN 2006-31, | |||
* IN 2007-14, | Maintenance (ADAMS Accession No. ML051740051) * IN 2005-15, Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear | ||
Generating Station (ADAMS Accession No. ML050490364) | |||
* IN 2006-18, Supplement 1, Significant Loss of Safety-Related Electrical Power at | |||
Forsmark Unit 1 in Sweden (ADAMS Accession No. ML071900368) | |||
* IN 2006-31, Inadequate Fault Interrupting Rating of Breakers (ADAMS Accession | |||
No. ML063000104) | |||
* IN 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating | |||
Station (ADAMS Accession No. ML070610424) | |||
==DISCUSSION== | |||
Licensees rely on non-safety electrical circuit breakers to power many IROFS, TSRs, or PFs | |||
related to electrical power. For IROFS/TSRs/PFs to be considered available and reliable, they | |||
must have all necessary instrumentation, controls, and normal or emergency electrical power | |||
available. Circuit breakers are relied upon to provide electrical power to equipment credited in | |||
the integrated safety analysis or safety analysis report. Licensees should incorporate the | |||
industry experience highlighted in this, and the above information notices, in electrical circuit | |||
breaker maintenance programs. Maintenance programs should identify and emphasize the | |||
importance of electrical systems which support important safety systems. Because licensees | |||
often use breakers of the same type and manufacture in various electrical support systems | |||
throughout the plant, common mode failure possibilities should be evaluated when performing | |||
modifications or other maintenance. When failures do occur, the extent of condition should be | |||
thoroughly evaluated for the potential for poor maintenance practices or design issues to impact | |||
other important site electrical systems. | |||
==CONTACT== | ==CONTACT== | ||
This IN requires no specific action or written | This IN requires no specific action or written response. Please direct any questions about this | ||
matter to the technical contact listed below. | |||
/RA/ /RA/ | |||
Joseph W. Shea, Director Daniel H. Dorman, Director | |||
Division of Fuel Facility Inspection Division of Fuel Cycle Safety and | |||
Region II Safeguards | |||
Office of Nuclear Material Safety and | |||
Safeguards | |||
===Technical Contact:=== | ===Technical Contact:=== | ||
Mary L. Thomas, DFFI/ FFIB3 404.562.4561 E-mail: MaryLynne.Thomas@nrc.gov | Mary L. Thomas, DFFI/ FFIB3 | ||
404.562.4561 E-mail: MaryLynne.Thomas@nrc.gov | |||
Enclosure: IN 2007-34, Operating Experience Regarding Electrical Circuit Breakers * IN 2005-15, Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear Generating Station (ADAMS | |||
Accession No. ML050490364) | |||
* IN 2006-18, Supplement 1, Significant Loss of Safety-Related Electrical Power at Forsmark Unit 1 in | |||
Sweden (ADAMS Accession No. ML071900368) | |||
* IN 2006-31, Inadequate Fault Interrupting Rating of Breakers (ADAMS Accession | |||
No. ML063000104) | |||
* IN 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station (ADAMS | |||
Accession No. ML070610424) | |||
== | ==DISCUSSION== | ||
Licensees rely on non-safety electrical circuit breakers to power many IROFS, TSRs, or PFs related to electrical | |||
power. For IROFS/TSRs/PFs to be considered available and reliable, they must have all necessary instrumentation, controls, and normal or emergency electrical power available. Circuit breakers are relied upon to provide electrical | |||
power to equipment credited in the integrated safety analysis or safety analysis report. Licensees should incorporate | |||
the industry experience highlighted in this, and the above information notices, in electrical circuit breaker | |||
maintenance programs. Maintenance programs should identify and emphasize the importance of electrical systems | |||
which support important safety systems. Because licensees often use breakers of the same type and manufacture in | |||
various electrical support systems throughout the plant, common mode failure possibilities should be evaluated when | |||
performing modifications or other maintenance. When failures do occur, the extent of condition should be thoroughly | |||
evaluated for the potential for poor maintenance practices or design issues to impact other important site electrical | |||
systems. | |||
==CONTACT== | ==CONTACT== | ||
This IN requires no specific action or written | This IN requires no specific action or written response. Please direct any questions about this matter to the technical | ||
contact listed below. | |||
Joseph W. Shea, Director Daniel H. Dorman, Director | |||
Division of Fuel Facility Inspection Division of Fuel Cycle Safety and Safeguards | |||
Region II Office of Nuclear Material Safety and Safeguards | |||
===Technical Contact:=== | ===Technical Contact:=== | ||
Mary L. Thomas, DFFI/ FFIB3 404.562.4561 E-mail: MaryLynne.Thomas@nrc.gov | Mary L. Thomas, DFFI/ FFIB3 | ||
404.562.4561 E-mail: MaryLynne.Thomas@nrc.gov | |||
Enclosure: IN 2007-34, Operating Experience Regarding Electrical Circuit Breakers | |||
DISTRIBUTION: | |||
*see previous concurence | |||
ML082730593 OFFICE DFFI/FFIB3 DFFI/FFIB3 RII/FFI NMSS/FCSS | |||
NAME M. Thomas* D. Rich* J. Shea* D. Dorman | |||
DATE 10/1/08 10/1/08 MCL 10/30/08 10/31/08 OFFICIAL USE ONLY}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} |
Latest revision as of 13:30, 14 November 2019
ML082730593 | |
Person / Time | |
---|---|
Issue date: | 11/24/2008 |
From: | Dan Dorman, James Shea NRC/NMSS/FCSS, NRC/RGN-II/DFFI |
To: | |
References | |
IN-08-021 | |
Download: ML082730593 (4) | |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 November 24, 2008 NRC INFORMATION NOTICE 2008-21: IMPACT OF NON-SAFETY ELECTRICAL
SUPPORT SYSTEM VULNERABILITIES ON
SAFETY SYSTEMS
ADDRESSES
All holders of operating licenses for nuclear fuel facilities.
PURPOSE
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform
addressees about potential impacts of non-safety support system failures or vulnerabilities on
safety systems. This IN references operating experience regarding low-, medium-, and
high-voltage circuit breakers as described in IN 2007-34 and adds similar operating experience
of non-safety related breakers at fuel facilities. Information Notice 2007-34 is attached.
Licensees rely on non-safety electrical systems to satisfy many items relied on for safety
(IROFS), technical safety requirements (TSR), or plant features (PF). For IROFS/TSRs/PFs to
be considered available and reliable, they must have necessary instrumentation, controls, and
normal or emergency electrical power available.
It is expected that recipients will review the information for applicability to their facilities and
consider appropriate actions to avoid similar problems. Suggestions contained in this IN are not
NRC requirements; therefore, no specific action or written response is required.
DESCRIPTION OF CIRCUMSTANCES
The Region II Division of Fuel Facility Inspection reviewed operating experience for the past five
years at both power reactors and fuel facilities related to electrical circuit breakers and found
that breaker problems were often caused by the following:
Deficient fit-up with cubicles
Worn or misadjusted linkages
Inadequate or inappropriate maintenance practices
Configuration control errors
Deficiencies from original design and refurbishment
Design changes
Foreign material entry
The following are examples of circuit breaker problems at fuel facilities:
BWX Technologies
On November 17, 2007, heavy smoke was emanating from the vicinity of an electrical
transformer. The fire, which emanated from a shorted 480 volt fuse panel, had melted nearby
plastic material and caused nearby wooden material to ignite and smolder.
Immediate event review by the licensee determined that an electrical surge was halted when the
12.4 kilovolt gang-operated switch disconnected the power supply transformer from the utility
sub-station. The licensees root causes for the fire were human performance such that the
preventative maintenance on the failed breakers was not performed due to production
schedules and equipment failure. (Inspection Report No. 70-27/2007008, ADAMS Accession
No. ML0802503450) The licensee stated in their root cause analysis that the fire was the result
of an electrical fault. The branch circuit and the main breaker feeding the transformer failed to
open as designed allowing a sustained fault condition resulting in the fire.
Paducah Gaseous Diffusion Plant
On May 20, 2003, the plant staff identified a fire in a non-safety related 480 volt circuit breaker
located in the Building C-633 Pump House. The circuit breaker provided power to a motor
associated with a recirculating water cooling tower fan. Due to problems within the circuit
breaker, the breaker did not immediately de-energize after the fault occurred. Instead, after
approximately 8 seconds, the breaker was de-energized after the setpoints associated with a
back-up current limiting device were exceeded. As a result of the delayed de-energizing of the
electrical breaker, other nearby breakers were damaged during the resultant fire. No personnel
injuries occurred as a result of the fire and no safety-related equipment was affected.
(Inspection Report No. 70-7001/2003005, ADAMS Accession No. ML032020568)
Paducah Gaseous Diffusion Plant
On November 23, 2004, the 480 volt Transformer Service Breaker 2PPA1 was being returned to
service when a fault occurred resulting in a fire. Non-safety plant equipment that should have
operated to isolate the fault failed to function and, as a result, the fault remained energized for
approximately 11 minutes. After the fault was isolated, the plant fire brigade used water to
extinguish the fire. No release of radioactive material occurred and no plant personnel were
injured; however, a significant plant transient resulted. The certificate holders root cause
analysis determined that foreign material had caused the fault, and that the failure of other
breakers to properly operate caused additional damage to the switchgear. Short term and long
term corrective actions were initiated (Inspection Report No. 70-7001/2005001, ADAMS
Accession No. ML050620142) Other Circuit Breaker Issues
The NRC review of operating experience also revealed the following circuit breaker issues
involving inadequate maintenance practices:
- Inadequate maintenance practices have resulted in gaps/clearances in the breaker
mechanism becoming out of specification and preventing proper operation of the circuit
breaker.
- Inadequate maintenance practices have resulted in not properly clearing and resetting
the trip mechanism once the circuit breaker is fully racked into the connect position -
preventing the circuit breaker from closing on demand.
- Inadequate maintenance practices have resulted in main stabs with excessive wear
leading to misalignment while racking the circuit breaker into the cubicle. This has led to
the failure of the high-resistance stab connection, which caused an electrical fault.
- Inadequate maintenance practices have resulted in misalignment of the circuit breaker
within the panel or cubicle. Misalignment has led to control power contacts not
connecting when the circuit breaker is racked in. Also, instances of inadequate
assessment, cleaning, and testing of contacts (relay, switch, contacts, etc.) have led to
the circuit breaker not operating in accordance with its design.
- Inadequate maintenance practices have involved crimping of control power lead lugs.
Faulty crimps have caused control power losses. There are also instances of loose
connections not being identified and/or corrected.
- Inadequate maintenance practices have involved inadequate cleaning (including
hardened greases) and greasing of the circuit breaker mechanism. This can result in the
circuit breaker mechanism and auxiliary switch not operating in accordance with their
design.
- Inadequate maintenance practices have caused inadvertent actuation of relays mounted
on circuit breaker cubicle doors during circuit breaker maintenance.
BACKGROUND
Previous Related Generic Communications:
- IN 1999-13, Insights from NRC Inspections of Low- and Medium-Voltage Circuit Breaker
Maintenance Programs (ADAMS Accession No. ML031040447)
- IN 2005-21, Plant Trip and Loss of Preferred AC Power From Inadequate Switchyard
Maintenance (ADAMS Accession No. ML051740051) * IN 2005-15, Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear
Generating Station (ADAMS Accession No. ML050490364)
- IN 2006-18, Supplement 1, Significant Loss of Safety-Related Electrical Power at
Forsmark Unit 1 in Sweden (ADAMS Accession No. ML071900368)
- IN 2006-31, Inadequate Fault Interrupting Rating of Breakers (ADAMS Accession
No. ML063000104)
- IN 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating
Station (ADAMS Accession No. ML070610424)
DISCUSSION
Licensees rely on non-safety electrical circuit breakers to power many IROFS, TSRs, or PFs
related to electrical power. For IROFS/TSRs/PFs to be considered available and reliable, they
must have all necessary instrumentation, controls, and normal or emergency electrical power
available. Circuit breakers are relied upon to provide electrical power to equipment credited in
the integrated safety analysis or safety analysis report. Licensees should incorporate the
industry experience highlighted in this, and the above information notices, in electrical circuit
breaker maintenance programs. Maintenance programs should identify and emphasize the
importance of electrical systems which support important safety systems. Because licensees
often use breakers of the same type and manufacture in various electrical support systems
throughout the plant, common mode failure possibilities should be evaluated when performing
modifications or other maintenance. When failures do occur, the extent of condition should be
thoroughly evaluated for the potential for poor maintenance practices or design issues to impact
other important site electrical systems.
CONTACT
This IN requires no specific action or written response. Please direct any questions about this
matter to the technical contact listed below.
/RA/ /RA/
Joseph W. Shea, Director Daniel H. Dorman, Director
Division of Fuel Facility Inspection Division of Fuel Cycle Safety and
Region II Safeguards
Office of Nuclear Material Safety and
Safeguards
Technical Contact:
Mary L. Thomas, DFFI/ FFIB3
404.562.4561 E-mail: MaryLynne.Thomas@nrc.gov
Enclosure: IN 2007-34, Operating Experience Regarding Electrical Circuit Breakers * IN 2005-15, Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear Generating Station (ADAMS
Accession No. ML050490364)
- IN 2006-18, Supplement 1, Significant Loss of Safety-Related Electrical Power at Forsmark Unit 1 in
Sweden (ADAMS Accession No. ML071900368)
- IN 2006-31, Inadequate Fault Interrupting Rating of Breakers (ADAMS Accession
No. ML063000104)
- IN 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station (ADAMS
Accession No. ML070610424)
DISCUSSION
Licensees rely on non-safety electrical circuit breakers to power many IROFS, TSRs, or PFs related to electrical
power. For IROFS/TSRs/PFs to be considered available and reliable, they must have all necessary instrumentation, controls, and normal or emergency electrical power available. Circuit breakers are relied upon to provide electrical
power to equipment credited in the integrated safety analysis or safety analysis report. Licensees should incorporate
the industry experience highlighted in this, and the above information notices, in electrical circuit breaker
maintenance programs. Maintenance programs should identify and emphasize the importance of electrical systems
which support important safety systems. Because licensees often use breakers of the same type and manufacture in
various electrical support systems throughout the plant, common mode failure possibilities should be evaluated when
performing modifications or other maintenance. When failures do occur, the extent of condition should be thoroughly
evaluated for the potential for poor maintenance practices or design issues to impact other important site electrical
systems.
CONTACT
This IN requires no specific action or written response. Please direct any questions about this matter to the technical
contact listed below.
Joseph W. Shea, Director Daniel H. Dorman, Director
Division of Fuel Facility Inspection Division of Fuel Cycle Safety and Safeguards
Region II Office of Nuclear Material Safety and Safeguards
Technical Contact:
Mary L. Thomas, DFFI/ FFIB3
404.562.4561 E-mail: MaryLynne.Thomas@nrc.gov
Enclosure: IN 2007-34, Operating Experience Regarding Electrical Circuit Breakers
DISTRIBUTION:
- see previous concurence
ML082730593 OFFICE DFFI/FFIB3 DFFI/FFIB3 RII/FFI NMSS/FCSS
NAME M. Thomas* D. Rich* J. Shea* D. Dorman
DATE 10/1/08 10/1/08 MCL 10/30/08 10/31/08 OFFICIAL USE ONLY