QUOTE(cutecat @ Aug 28 2008, 12:34 PM)

My knowledge limited so looked it up;
Fort Calhoun Nuclear Generating Station is a nuclear power plant located on 660 acres (2.7 km²) between Fort Calhoun, Nebraska and Blair, Nebraska.
The utility has an easement for another 580 acres (2.3 km²) which is maintained in a natural state.
This plant has one Combustion Engineering pressurized water reactor generating 500 megawatts of electricity.
This is currently the smallest rated capacity among all operating commercial power reactors in North America.
The plant underwent refurbishment in 2006 by having its steam generators, pressurizer, reactor vessel head, low pressure turbines and main transformer replaced.
The plant recently had its operating license renewed for an additional twenty years.
The power plant is owned and operated by the Omaha Public Power District of Omaha, Nebraska.
QUOTE(Terra @ Aug 28 2008, 02:35 PM)

May 9, 2000
EA 00-106
S. K. Gambhir, Division Manager
Nuclear Operations
Omaha Public Power District
Fort Calhoun Station FC-2-4 Adm.
P.O. Box 399
Hwy. 75 - North of Fort Calhoun
Fort Calhoun, Nebraska 68023-0399
SUBJECT: FIRE PROTECTION TRIENNIAL BASELINE INSPECTION REPORT
NO. 50-285/00-01
Dear Mr. Gambhir:
On January 24 to 28, and March 10, 2000, the NRC conducted a pilot fire protection triennial baseline inspection of your Fort Calhoun Station reactor facility.
The enclosed report presents the results of that inspection.
The team leader presented preliminary findings to you and members of your staff in a briefing on January 28, 2000, and in an exit meeting on March 10, 2000, both of which were held at Fort Calhoun Station.
Following review of the preliminary findings by the NRC’s Significance Determination Process Panel, a re-exit was held by telephone on April 28, 2000, to inform you of changes to the preliminary inspection findings.
Based on the results of this inspection, the NRC has determined that a violation of NRC requirements occurred for failure to comply with License Condition E to your license, relative to maintaining in effect all provisions of your NRC-approved fire protection program.Specifically, the installed configuration of power cables in Fire Area 32 (the air compressor room) conflicts with the description of the fire area provided to the NRC in your exemption request of January 9, 1985.
The NRC used this information as a basis for issuing an exemption from 10 CFR Part 50, Appendix R, Section III.G.2 for power cables in Fire Area 32. The other example concerns the failure of the installed configuration of control cables in Fire Area 32 to meet the requirements of 10 CFR Part 50, Appendix R, Section III.G.2 for ensuring that redundant trains of safe shutdown equipment remain free of fire damage.
This violation is being treated as a noncited violation.
It is the NRC’s understanding that you do not consider the configuration of either the power or control cables to be outside your design basis.
Therefore, it is your position that these violations of your License Condition E did not occur.However, as committed in the exit meeting of March 10, and again in the exit meeting of April 28, 2000, your posted compensatory measures for Fire Area 32 will remain in place until you have contacted Region IV management otherwise.
In addition, this issue was entered into your corrective action program.
The team also identified a condition where a fire in either Fire Areas 34B (the upper electrical penetration room) or 36B (the west switchgear room) could potentially cause fire-induced circuit failures and result in the reactor coolant gas vent system valves spuriously opening and
Omaha Public Power District establishing a vent path beyond your analyzed makeup capacity. The NRC staff and industry are currently working to resolve questions raised by the industry about the adequacy of the existing staff guidance concerning fire-induced circuit failures.
In order to allow the industry to develop an acceptable approach to resolving this issue, the NRC will defer any enforcement action relative to these matters while the staff evaluates the Nuclear Energy Institute’s proposed resolution methodology and you have time to implement the resolution methodology, once approved.
Therefore, an apparent violation of 10 CFR Part 50, Appendix R, Section III.G.1.a, was identified for failure to ensure that one train of redundant systems necessary for achieving and maintaining hot shutdown, located within the same fire area, would remain free of fire
damage. The NRC’s Inspection Manual Chapter 0610* defines an apparent violation as “a potential noncompliance with a regulatory requirement that has not yet been formally cited as a violation in a notice of violation or order.”
It is the NRC’s understanding that you do not consider these circuit vulnerabilities to be a violation of NRC requirements; however, as a conservative response to these findings, you posted compensatory measures for Fire Areas 34B and 36B, which will remain in place until this issue is resolved. During the exit meeting on April 28, 2000, you stated that you had recently completed an analysis, which demonstrated that given a fire in either Fire Areas 34B or 36B, your operators could cope with spurious opening of the reactor coolant gas vent system valves.
These violations are described in the subject inspection report and have been entered into your corrective action program.
If you contest the nature or severity level of any of these violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555-0001, with copies to the Regional Administrator, Region IV, and the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, D.C. 20555-0001.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure will be placed in the NRC Public Document Room.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
/RA/
Dr. Dale A. Powers, Acting Chief
Engineering and Maintenance Branch
Division of Reactor Safety
Docket No.: 50-285
License No: DPR-40
Omaha Public Power District -3-
Enclosure:
NRC Inspection Report No. 50-285/00-01
cc w/enclosure:
Mark T. Frans, Manager
Nuclear Licensing
Omaha Public Power District
Fort Calhoun Station FC-2-4 Adm.
P.O. Box 399
Hwy. 75 - North of Fort Calhoun
Fort Calhoun, Nebraska 68023-0399
James W. Chase, Division Manager
Nuclear Assessments
Fort Calhoun Station
P.O. Box 399
Fort Calhoun, Nebraska 68023
Richard P. Clemens, Manager - Fort Calhoun Station
Omaha Public Power District
Fort Calhoun Station FC-1-1 Plant
P.O. Box 399
Hwy. 75 - North of Fort Calhoun
Fort Calhoun, Nebraska 68023
Perry D. Robinson, Esq.
Winston & Strawn
1400 L. Street, N.W.
Washington, D.C. 20005-3502
Chairman
Washington County Board of Supervisors
Washington County Courthouse
P.O. Box 466
Blair, Nebraska 68008
Cheryl K. Rogers, Program Manager
Nebraska Health and Human Services System
Division of Public Health Assurance
Consumer Services Section
301 Centennial Mall, South
P.O. Box 95007
Lincoln, Nebraska 68509-5007
http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/RE...fcs_2000001.pdf