ML051440846
| ML051440846 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/07/2005 |
| From: | Michelle Honcharik NRC/NRR/DLPM/LPD4 |
| To: | Edington R Nebraska Public Power District (NPPD) |
| Honcharik M, NRR/DLPM, 301-415-1774 | |
| References | |
| TAC MC5031 | |
| Download: ML051440846 (5) | |
Text
June 7, 2005 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE THE REQUIRED CHANNELS PER TRIP SYSTEM FOR PRIMARY AND SECONDARY CONTAINMENT ISOLATION AND CONTROL ROOM EMERGENCY FILTER SYSTEM INSTRUMENTATION (TAC NO. MC5031)
Dear Mr. Edington:
By letter dated October 25, 2004, Nebraska Public Power District (NPPD) requested the Nuclear Regulatory Commission (NRC) staff's approval for an amendment to revise the Cooper Nuclear Station Technical Specifications regarding the required channels per trip system for primary and secondary containment isolation and control room emergency filter system instrumentation.
The NRC staff has reviewed the information provided in the October 25, 2004, submittal and has determined that the additional information identified in the enclosure is required in order for the NRC staff to complete its review. As agreed upon with David Van Der Kamp on May 20, 2005, NPPD will respond to the request for additional information (RAI) within 45 days from the date of this letter. The RAI is enclosed.
Sincerely,
/RA by M. Fields for/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
RAI cc w/encl: See next page
Mr. Randall K. Edington June 7, 2005 Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE THE REQUIRED CHANNELS PER TRIP SYSTEM FOR PRIMARY AND SECONDARY CONTAINMENT ISOLATION AND CONTROL ROOM EMERGENCY FILTER SYSTEM INSTRUMENTATION (TAC NO. MC5031)
Dear Mr. Edington:
By letter dated October 25, 2004, Nebraska Public Power District (NPPD) requested the Nuclear Regulatory Commission (NRC) staff's approval for an amendment to revise the Cooper Nuclear Station Technical Specifications regarding the required channels per trip system for primary and secondary containment isolation and control room emergency filter system instrumentation.
The NRC staff has reviewed the information provided in the October 25, 2004, submittal and has determined that the additional information identified in the enclosure is required in order for the NRC staff to complete its review. As agreed upon with David Van Der Kamp on May 20, 2005, NPPD will respond to the request for additional information (RAI) within 45 days from the date of this letter. The RAI is enclosed.
Sincerely,
/RA by M. Fields for/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC PDIV-1 Reading RidsNrrDlpmLpdiv (HBerkow)
RidsNrrDlpmLpdiv1 (DTerao)
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AHowe BMarcus DDuvigneaud ACCESSION NO: ML051440846 OFFICE PDIV-2/PE PDIV-1/PM PDIV-2/LA EEIB-A/SC PDIV-1/SC NAME DDuvigneaud MFields for MHoncharik LFeizollahi AHowe DTerao DATE 6/2/05 6/2/05 6/2/05 6/3/05 6/7/05 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION ISSUES RELATED TO REVISION OF TECHNICAL SPECIFICATIONS TO REVISE THE REQUIRED CHANNELS PER TRIP SYSTEM FOR PRIMARY AND SECONDARY CONTAINMENT ISOLATION AND CONTROL ROOM EMERGENCY FILTER SYSTEM INSTRUMENTATION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 1.
In the October 25, 2004 submittal, the markup of the technical specification (TS)
Table 3.3.6.1-1 showed Functions 2a, 5d, and 6b, Table 3.3.6.2-1 Function 1, and Table 3.3.7.1-1 Function 1 as Reactor Vessel Water Level - Low (Level 3). However, in Amendment 209 Table 3.3.6.1-1 Function 5d, Table 3.3.6.2-1 Function 1, and Table 3.3.7.1-1 Function 1 are shown to be Reactor Vessel Water Level - Low Low (Level 2).
Please explain this discrepancy between Amendment 209 and the October 25, 2004 submittal.
2.
The October 25, 2004 submittal stated, "As a result of the ITS [improved technical specification] conversion the number of Required Channels Per Trip System was changed from 2 to 4. This change was based on an ITS convention that defined each divisional logic to be one trip system. Since all four instrument channels provided input signals in that divisional/trip system logic, the result was that there be 4 Required Channels Per Trip System. However, the CNS [Cooper Nuclear Station] design basis defines each divisional logic as having two trip systems, thus 2 Required Channels Per Trip System. The discussion of changes submitted with the ITS revisions acknowledged the change in practice that was introduced."
(a)
Please provide more details concerning how this change was introduced during the ITS conversion.
(b)
Please identify the pages of the ITS submittal where the discussion of changes, that acknowledged the change in practice, appeared.
(c)
What was the construction of the TS for these instruments prior to the conversion to the ITS format? How many channels, what were the action statements, etc.
3.
In the October 25, 2004 submittal, the markup of page B 3.3-157, Function 6.b, second paragraph, second sentence, reads, "Eight Four channels (four channels per trip system) of the Reactor Vessel Water Level - Low (Level 3) Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function."
If there are four channels total, is "(four channels per trip system)" correct?
4.
Some of the instruments involved in this request also appear in other TS tables with the Required Number of Channels Per Trip System being different from the number of channels in your request. Reactor Vessel Water Level - Low Low (Level 2) appears in Table 3.3.5.1-1, "Emergency Core Cooling System Instrumentation," Function 3a and Table 3.3.5.2-1, "Reactor Core Isolation Cooling System Instrumentation," Function 1, with 4 as the Required Channels Per Trip System. Drywell Pressure - High appears in Table 3.3.5.1-1 Functions 1b, 2b, and 3b, with 4 as the Required Channels Per Trip System.
Please explain why your request does not agree with the Required Channels Per Trip System in TS Tables 3.3.5.1-1 and 3.3.5.2-1 from the same variables.
April 2005 Cooper Nuclear Station cc:
Mr. William J. Fehrman President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. Michael T. Boyce Nuclear Assett Manager Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. John C. McClure Vice President and General Counsel Nebraska Public Power District P. O. Box 499 Columbus, NE 68602-0499 Mr. Paul V. Fleming Licensing Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P. O. Box 98922 Lincoln, NE 68509-8922 Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305 Ms. Cheryl K. Rogers, Program Manager Nebraska Health & Human Services System Division of Public Health Assurance Consumer Services Section 301 Centennial Mall, South P. O. Box 95007 Lincoln, NE 68509-5007 Mr. Mike Wells, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 218 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 State Emergency Management Agency P. O. Box 116 Jefferson City, MO 65101 Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson Suite 310 Topeka, KS 66612-1366 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street Suite D Des Moines, IA 50309 Mr. Scott Clardy, Director Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570 Jerry C. Roberts, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321