ML063340179
| ML063340179 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/11/2006 |
| From: | Richard Ennis NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | VanMiddlesworth G D Duane Arnold |
| K. Feintuch, LPL3-1 | |
| References | |
| GL-03-001, TAC MB9801 | |
| Download: ML063340179 (4) | |
Text
December 11, 2006Mr. Gary Van MiddlesworthSite Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
SUBJECT:
NRC RECEIPT OF DUANE ARNOLD ENERGY CENTER RESPONSE TOGENERIC LETTER 2003-01 "CONTROL ROOM HABITABILITY" (TAC NO. MB9801)
Dear Mr. Van Middlesworth:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of the responses toGeneric Letter (GL) 2003-01 "Control Room Habitability" for the Duane Arnold Energy Center (DAEC) from Nuclear Management Company, LLC (NMC) dated August 11, 2003, November 25, 2003, and January 28, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML032310414, ML033300162, ML050390308, respectively).
Amendment No. 260, issued on January 27, 2006, transferred the DAEC license from NMC to FPL Energy Duane Arnold, LLC (FPL Energy). As noted in your letter dated February 6, 2006, FPL Energy adopted and endorsed all docketed requests for NRC review previously submitted by NMC. This letter provides a status of your response for DAEC and describes any actions that may be necessary to consider the response to GL 2003-01 to be complete.The GL requested that licensees confirm that the control room 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: (1) Determination of the most limiting unfiltered and/or filtered inleakage into the control room and comparison to values used in the design bases for meeting control room operator dose limits from accidents (GL 2003-01 Item 1a); (2) Determination that the most limiting unfiltered inleakage is incorporated into the hazardous chemical assessments (GL 2003-01 Item 1b); and, (3) Determination that reactor control capability is maintained in the control room or at the alternate shutdown location in the event of smoke (GL 2003-01 Item 1b).
The GL further requested information on any compensatory measures in use to demonstrate control room habitability (CRH) and plans to retire them (GL 2003-01 Item 2).You reported the results of American Society for Testing and Materials E741 tracer gas tests forthe DAEC control room, which is pressurized for accident mitigation. You determined that the most limiting unfiltered inleakage into the control room envelope (CRE), was 85 standard cubic feet per minute (scfm), which is less than the value of 1000 scfm assumed in the design basis radiological analyses for CRH.You also reported that DAEC's toxic chemical analysis assumes a normal ventilation mode of3150 scfm inflow plus 1000 scfm inleakage, for a total of 4150 scfm, all unfiltered. Tracer gas testing in the 'Normal" mode of operation (recirculation mode) was performed and total flow was 2848 +/- 81 scfm. Therefore, normal ventilation mode total intake and inleakage is within G. Van Middlesworth-2-analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor controlcapability is maintained in the event of smoke from either the control room, or the alternate shutdown panel.The GL further requested that licensees assess the Technical Specifications (TSs) to determineif the TSs verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for CRH, in light of the demonstrated inadequacy of a delta () P measurement to, alone, provide such verification (GL 2003-01 Item 1c). Aspermitted by the GL, you provided a schedule for revising the surveillance requirements in the TSs to reference an acceptable surveillance methodology. In your response dated January 28, 2005, you committed to submit proposed changes to the TSs, based upon the final approved version of Technical Specification Task Force (TSTF) Traveler No. TSTF-448, within 180 days following NRC approval of TSTF-448. The information you provided supports that there are no compensatory measures currently inplace to demonstrate CRH. The information you provided also supports your conclusion that the facility design, as documented in the DAEC Updated Final Safety Analysis Report, is consistent with the GDC regarding CRH.Your commitment to submit a License Amendment Request (LAR) based on TSTF-448,following our formal review and approval, is acceptable for purposes of closing out the response to GL 2003-01 for DAEC. The NRC staff will monitor submission of the LAR and interact with you as necessary during the amendment review process.If you have any questions, please contact Karl Feintuch at 301-415-3079 or myself at 301-415-1420.Sincerely,/RA/Richard B. Ennis, Senior Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331 cc: See next page G. Van Middlesworth-2-analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor controlcapability is maintained in the event of smoke from either the control room, or the alternate shutdown panel.The GL further requested that licensees assess the Technical Specifications (TSs) to determineif the TSs verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for CRH, in light of the demonstrated inadequacy of a delta () P measurement to, alone, provide such verification (GL 2003-01 Item 1c). Aspermitted by the GL, you provided a schedule for revising the surveillance requirements in the TSs to reference an acceptable surveillance methodology. In your response dated January 28, 2005, you committed to submit proposed changes to the TSs, based upon the final approved version of Technical Specification Task Force (TSTF) Traveler No. TSTF-448, within 180 days following NRC approval of TSTF-448. The information you provided supports that there are no compensatory measures currently inplace to demonstrate CRH. The information you provided also supports your conclusion that the facility design, as documented in the DAEC Updated Final Safety Analysis Report, is consistent with the GDC regarding CRH.Your commitment to submit a License Amendment Request (LAR) based on TSTF-448,following our formal review and approval, is acceptable for purposes of closing out the response to GL 2003-01 for DAEC. The NRC staff will monitor submission of the LAR and interact with you as necessary during the amendment review process.If you have any questions, please contact Karl Feintuch at 301-415-3079 or myself at 301-415-1420.Sincerely,/RA/Richard B. Ennis, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331 cc: See next page DISTRIBUTIONPUBLICLPL3-1 R/FRidsNrrPMKFeintuchRidsNrrPMREnnisRidsNrrLATHarrisRidsNrrDorlLpl3-1RidsRgn3MailCenterRidsOgcRp JRobinsonRidsNrrDprPgcbRidsAcrsAcnwMailCenterRidsNrrDssScvb ADAMS ACCESSION NO. ML063340179 OFFICELPL3-1/PMLPL3-1/PMLPL3-1/LASCVB/BCPGCB/BCLPL3-1/BCNAMEKFeintuchREnnisTHarrisRDennigCJacksonLRaghavanDATE 11/30/0612/6/06 11/29/0612/6/0612/6/0612/11/06OFFICIAL RECORD COPY G. Van MiddlesworthDuane Arnold Energy Center cc:
Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. RossManaging Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. R. E. HelfrichSenior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. W. E. WebsterVice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420John BjorsethSite Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324Steven R. CatronManager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324U. S. Nuclear Regulatory CommissionResident Inspector's Office Rural Route #1 Palo, IA 52324Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351Mr. M. WarnerVice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. D. A. CurtlandPlant Manager Duane Arnold Energy Center 3277 DAEC Rd.
Palo, IA 52324-9785Mr. R. S. KundalkarVice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Daniel K. McGheeIowa Department of Public Health Bureau of Radiological Health 321 East 12th Street Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075Chairman, Linn CountyBoard of Supervisors 930 1st Street SW Cedar Rapids, IA 52404October 12, 2006