ML063210252
| ML063210252 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/05/2006 |
| From: | Bhalchandra Vaidya NRC/NRR/ADRO/DORL/LPLIV |
| To: | Edington R Nebraska Public Power District (NPPD) |
| Vaidya B, NRR/DORL/LP4, 415-3308 | |
| References | |
| GL-03-001, TAC MB9792 | |
| Download: ML063210252 (6) | |
Text
December 5, 2006 Mr. Randall K. Edington Vice President - Nuclear and CNO Nebraska Public Power District P.O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - RE: NRC RECEIPT OF COOPER NUCLEAR STATION RESPONSES TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NO. MB9792)
Dear Mr. Edington:
The U.S. Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses dated November 10, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML033210207), September 30, 2004 (ADAMS Accession No. ML042800269), and June 17, 2005 (ADAMS Accession No. ML051720149), to the NRC Generic Letter (GL) 2003-01, Control Room Habitability, dated June 12, 2003 (ADAMS Accession No. ML031620248).
The GL 2003-01 requested that you confirm that your control room (CR) meets its design bases (e.g., General Design Criteria (GDC) 1, 3, 4, 5, and 19, draft GDC, or principal design criteria),
with special attention to the following:
(1) GL 2003-01, Requested Information, Item 1a: Determination of the most limiting unfiltered and/or filtered inleakage into the CR and comparison to values used in your design bases for meeting CR operator dose limits from accidents.
(2) GL 2003-01, Requested Information, Item 1b: Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments.
(3) GL 2003-01, Requested Information, Item 1b: Determination that reactor control capability is maintained in the CR or at the alternate shutdown location in the event of smoke.
(4) GL 2003-01, Requested Information, Item 2: Provide information on any compensatory measures in use to demonstrate control room habitability (CRH),
and plans to retire them.
(5) GL 2003-01, Requested Information, Item 1c: Assessment of the Technical Specifications (TSs) to determine if they require verification of the integrity of the CR Envelope (CRE), including ongoing verification of the inleakage assumed in the design-basis analysis for CRH, in light of the demonstrated unreliability of the
R. Edington P surveillance (a test to ensure positive differential pressure between CR and adjacent areas) alone to provide such verification.
As requested by GL 2003-01, you provided responses by letters referenced above. They are summarized below:
- a. Cooper Nuclear Stations (CNS) CR is a positive-pressure-design structure.
- b. The results of the American Society of Testing Materials (ASTM) E741 tracer gas tests (ASTM, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution) for CNSs CR indicate that the maximum tested value for inleakage into the CRE was 64 actual cubic feet per minute (acfm) with the Control Room Emergency Filter System operating in the pressurization mode and that these test results are bounded by the unfiltered inleakage assumptions in your revised dose assessment methodology contained in License Amendment Nos. 183, 187, 196, with the correction letter dated March 12, 2003, and 206.
The staff reviewed your License Amendment Request (LAR) dated February 28, 2001 related to radiological assessment calculation methodology (ADAMS Accession No. ML010660067 - Non-Publicly Available) and subsequent License Amendment Nos. 187 (ADAMS Accession No. ML012960618), 196 with the correction letter dated March 12, 2003, (ADAMS Accession No. ML030710724),
and 206 (ADAMS Accession No. ML042470174) and confirmed that your test result of 64 acfm is not more than the value assumed in your design-basis radiological analysis for CRH which is 81 standard cubic feet per minute (scfm)
(71 scfm unfiltered inleakage from infiltration plus 10 scfm unfiltered inleakage from control room ingress/egress) as stated in the above referenced documents.
- c. The maximum tested value for inleakage into the CRE in the isolation (toxic gas) mode was 222 (+/-13) acfm and that this value is incorporated into the Control Room Habitability Hazardous Chemical Analysis which was performed using the guidance contained in Regulatory Guide 1.78, Revision 1, Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release.
- d. Reactor control capability is maintained from either the CR or the alternate shutdown panel in the event of smoke.
- e. A schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology has been developed and a license amendment request addressing the monitoring of CR inleakage would be submitted within 12 months following NRC approval of TS Task Force Traveler (TSTF)-448.
- f. Potassium iodide is utilized as a compensatory measure to demonstrate CR habitability during a loss-of-coolant accident with core damage, but License Amendment No. 206 deleted License Condition 2.c.(6) which enables this compensatory measure to be retired.
R. Edington g. CNS meets the draft GDC regarding CR habitability as documented in the CNS Updated Safety Analysis Report.
Based on the information provided, the regulatory commitment made in your response letters referenced above, and the above discussion, the NRC staff finds the CNS responses to GL 2003-01 to be complete.
If you have any questions regarding this correspondence, please contact me at 301-415-3308.
Sincerely,
/RA/
Bhalchandra Vaidya, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298 cc: See next page
ML063210252 OFFICE NRR/LPLIV/PM NRR/LPLIV/LA NRR/SCVB/BC NRR/PGCB/BC NRR/LPL4/BC NAME BVaidya LFeizollahi RDennig CJackson DTerao DATE 11/28/06 11/28/06 11/28/06 12/1/06 12/5/06 Cooper Nuclear Station cc:
Mr. Ronald D. Asche Mr. H. Floyd Gilzow President and Chief Executive Officer Deputy Director for Policy Nebraska Public Power District Missouri Department of Natural Resources 1414 15th Street P.O. Box 176 Columbus, NE 68601 Jefferson City, MO 65102-0176 Mr. Gene Mace Senior Resident Inspector Nuclear Asset Manager U.S. Nuclear Regulatory Commission Nebraska Public Power District P.O. Box 218 P.O. Box 98 Brownville, NE 68321 Brownville, NE 68321 Regional Administrator, Region IV Mr. John C. McClure U.S. Nuclear Regulatory Commission Vice President and General Counsel 611 Ryan Plaza Drive, Suite 400 Nebraska Public Power District Arlington, TX 76011 P.O. Box 499 Columbus, NE 68602-0499 Director, Missouri State Emergency Management Agency Mr. Paul V. Fleming P.O. Box 116 Licensing Manager Jefferson City, MO 65102-0116 Nebraska Public Power District P.O. Box 98 Chief, Radiation and Asbestos Brownville, NE 68321 Control Section Kansas Department of Health Mr. Michael J. Linder, Director and Environment Nebraska Department of Environmental Bureau of Air and Radiation Quality 1000 SW Jackson P.O. Box 98922 Suite 310 Lincoln, NE 68509-8922 Topeka, KS 66612-1366 Chairman Mr. Donald A. Flater Nemaha County Board of Commissioners Radiation Control Program Director Nemaha County Courthouse Bureau of Radiological Health 1824 N Street Iowa Department of Public Health Auburn, NE 68305 Lucas State Office Building, 5th Floor 321 East 12th Street Ms. Julia Schmitt, Manager Des Moines, IA 50319 Radiation Control Program Nebraska Health & Human Services R & L Mr. Daniel K. McGhee Public Health Assurance Bureau of Radiological Health 301 Centennial Mall, South Iowa Department of Public Health P.O. Box 95007 Lucas State Office Building, 5th Floor Lincoln, NE 68509-5007 321 East 12th Street Des Moines, IA 50319 October 2006
Cooper Nuclear Station cc:
Mr. Keith G. Henke, Planner Mr. John F. McCann, Director Division of Community and Public Health Licensing, Entergy Nuclear Northeast Office of Emergency Coordination Entergy Nuclear Operations, Inc.
930 Wildwood P.O. Box 570 440 Hamilton Avenue Jefferson City, MO 65102 White Plains, NY 10601-1813 Jerry C. Roberts, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 October 2006