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	=Text=		=Text=
	{{#Wiki_filter:December 11, ~~2006Mr~~. Gary Van ~~MiddlesworthSite~~ Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785		{{#Wiki_filter:December 11, 2006 Mr. Gary Van Middlesworth Site Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785

	==SUBJECT:==		==SUBJECT:==
	NRC RECEIPT OF DUANE ARNOLD ENERGY CENTER RESPONSE ~~TOGENERIC~~ LETTER 2003-01 "CONTROL ROOM HABITABILITY" (TAC NO. MB9801)		NRC RECEIPT OF DUANE ARNOLD ENERGY CENTER RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NO. MB9801)

	==Dear Mr. Van Middlesworth:==		==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).		The Nuclear Regulatory Commission (NRC) acknowledges the receipt of the responses to Generic 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).		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 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:		The GL requested that licensees confirm that the control room meets its design bases (e.g.,
	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.		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).
	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}}		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 for the 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 DAECs toxic chemical analysis assumes a normal ventilation mode of 3150 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 analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor control capability 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 determine if 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). As permitted 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 in place 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 Regulation Docket No. 50-331 cc: See next page

			G. Van Middlesworth analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor control capability 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 determine if 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). As permitted 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 in place 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 Regulation Docket No. 50-331 cc: See next page DISTRIBUTION PUBLIC LPL3-1 R/F RidsNrrPMKFeintuch RidsNrrPMREnnis RidsNrrLATHarris RidsNrrDorlLpl3-1 RidsRgn3MailCenter RidsOgcRp JRobinson RidsNrrDprPgcb RidsAcrsAcnwMailCenter RidsNrrDssScvb ADAMS ACCESSION NO. ML063340179 OFFICE LPL3-1/PM LPL3-1/PM LPL3-1/LA SCVB/BC PGCB/BC LPL3-1/BC NAME KFeintuch REnnis THarris RDennig CJackson LRaghavan DATE 11/30/06 12/6/06 11/29/06 12/6/06 12/6/06 12/11/06 OFFICIAL RECORD COPY

			G. Van Middlesworth Duane Arnold Energy Center cc:
			Mr. J. A. Stall Regional Administrator, Region III Senior Vice President, Nuclear and Chief U.S. Nuclear Regulatory Commission Nuclear Officer Suite 210 Florida Power & Light Company 2443 Warrenville Road P. O. Box 14000 Lisle, IL 60532-4351 Juno Beach, FL 33408-0420 Mr. M. Warner Mr. M. S. Ross Vice President, Nuclear Operations Managing Attorney Support Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. R. E. Helfrich Mr. D. A. Curtland Senior Attorney Plant Manager Florida Power & Light Company Duane Arnold Energy Center P. O. Box 14000 3277 DAEC Rd.
			Juno Beach, FL 33408-0420 Palo, IA 52324-9785 Mr. W. E. Webster Mr. R. S. Kundalkar Vice President, Nuclear Operations Vice President, Nuclear Engineering Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 John Bjorseth Daniel K. McGhee Site Director Iowa Department of Public Health Duane Arnold Energy Center Bureau of Radiological Health 3277 DAEC Road 321 East 12th Street Palo, IA 52324 Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075 Steven R. Catron Manager, Regulatory Affairs Chairman, Linn County Duane Arnold Energy Center Board of Supervisors 3277 DAEC Road 930 1st Street SW Palo, IA 52324 Cedar Rapids, IA 52404 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 October 12, 2006}}

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	\| number = ML063340179		\| number = ML063340179
	\| issue date = 12/11/2006		\| issue date = 12/11/2006
	\| title = ~~Duane Arnold,~~ Generic Letter 2003-01		\| title = Generic Letter 2003-01
	\| author name = Ennis R B		\| author name = Ennis R
	\| author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1		\| author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1
	\| addressee name = ~~VanMiddlesworth~~ G D		\| addressee name = Vanmiddlesworth G
	\| addressee affiliation = FPL Energy Duane Arnold, LLC		\| addressee affiliation = FPL Energy Duane Arnold, LLC
	\| docket = 05000331		\| docket = 05000331

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{{Adams
| number = ML063340179
| issue date = 12/11/2006
| title = Duane Arnold, Generic Letter 2003-01
| author name = Ennis R B
| author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1
| addressee name = VanMiddlesworth G D
| addressee affiliation = FPL Energy Duane Arnold, LLC
| docket = 05000331
| license number = DPR-049
| contact person = K. Feintuch, LPL3-1
| case reference number = GL-03-001, TAC MB9801
| document type = Letter
| page count = 4
| project = TAC:MB9801
| stage = Other
}}

=Text=
{{#Wiki_filter: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}}

← Older revision		Revision as of 05:57, 15 January 2025
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	==Dear Mr. Van Middlesworth:==		==Dear Mr. Van Middlesworth:==

	The Nuclear Regulatory Commission (NRC) acknowledges the receipt of the responses to Generic 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).		The Nuclear Regulatory Commission (NRC) acknowledges the receipt of the responses to Generic 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.		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\|date=February 6, 2006\|text=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.,		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).		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).
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	You also reported that DAECs toxic chemical analysis assumes a normal ventilation mode of 3150 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		You also reported that DAECs toxic chemical analysis assumes a normal ventilation mode of 3150 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 analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor control capability is maintained in the event of smoke from either the control room, or the alternate shutdown panel.		G. Van Middlesworth analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor control capability 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 determine if 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). As permitted 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 GL further requested that licensees assess the Technical Specifications (TSs) to determine if 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). As permitted 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 in place 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.		The information you provided supports that there are no compensatory measures currently in place 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.
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	If you have any questions, please contact Karl Feintuch at 301-415-3079 or myself at 301-415-1420.		If you have any questions, please contact Karl Feintuch at 301-415-3079 or myself at 301-415-1420.
	Sincerely,		Sincerely,
	/RA/		/RA/
	Richard B. Ennis, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 cc: See next page		Richard B. Ennis, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 cc: See next page

	G. Van Middlesworth analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor control capability is maintained in the event of smoke from either the control room, or the alternate shutdown panel.		G. Van Middlesworth analyzed limits for toxic chemical analysis. Additionally, you indicated that reactor control capability 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 determine if 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). As permitted 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 GL further requested that licensees assess the Technical Specifications (TSs) to determine if 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). As permitted 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 in place 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.		The information you provided supports that there are no compensatory measures currently in place 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.
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	If you have any questions, please contact Karl Feintuch at 301-415-3079 or myself at 301-415-1420.		If you have any questions, please contact Karl Feintuch at 301-415-3079 or myself at 301-415-1420.
	Sincerely,		Sincerely,
	/RA/		/RA/
	Richard B. Ennis, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 cc: See next page DISTRIBUTION PUBLIC LPL3-1 R/F RidsNrrPMKFeintuch RidsNrrPMREnnis RidsNrrLATHarris RidsNrrDorlLpl3-1 RidsRgn3MailCenter RidsOgcRp JRobinson RidsNrrDprPgcb RidsAcrsAcnwMailCenter RidsNrrDssScvb ADAMS ACCESSION NO. ML063340179 OFFICE LPL3-1/PM LPL3-1/PM LPL3-1/LA SCVB/BC PGCB/BC LPL3-1/BC NAME KFeintuch REnnis THarris RDennig CJackson LRaghavan DATE 11/30/06 12/6/06 11/29/06 12/6/06 12/6/06 12/11/06 OFFICIAL RECORD COPY		Richard B. Ennis, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 cc: See next page DISTRIBUTION PUBLIC LPL3-1 R/F RidsNrrPMKFeintuch RidsNrrPMREnnis RidsNrrLATHarris RidsNrrDorlLpl3-1 RidsRgn3MailCenter RidsOgcRp JRobinson RidsNrrDprPgcb RidsAcrsAcnwMailCenter RidsNrrDssScvb ADAMS ACCESSION NO. ML063340179 OFFICE LPL3-1/PM LPL3-1/PM LPL3-1/LA SCVB/BC PGCB/BC LPL3-1/BC NAME KFeintuch REnnis THarris RDennig CJackson LRaghavan DATE 11/30/06 12/6/06 11/29/06 12/6/06 12/6/06 12/11/06 OFFICIAL RECORD COPY

	G. Van Middlesworth Duane Arnold Energy Center cc:		G. Van Middlesworth Duane Arnold Energy Center cc:
	Mr. J. A. Stall ~~Regional Administrator, Region III~~ Senior Vice President, Nuclear and Chief ~~U.S. Nuclear Regulatory Commission~~ Nuclear Officer ~~Suite 210~~ Florida Power & Light Company ~~2443 Warrenville Road~~ P. O. Box 14000 ~~Lisle, IL 60532-4351~~ Juno Beach, FL 33408-0420 ~~Mr. M. Warner~~ Mr. M. S. Ross ~~Vice President, Nuclear Operations~~ Managing Attorney ~~Support Florida Power & Light Company~~ Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. R. E. ~~Helfrich~~ Mr. D. ~~A. Curtland Senior Attorney Plant Manager~~ Florida Power & Light Company ~~Duane Arnold Energy Center~~ P. O. Box 14000 ~~3277 DAEC Rd.~~		Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. Ross Managing Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. R. E. Helfrich Senior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. W. E. Webster Vice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 John Bjorseth Site Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Mr. M. Warner Vice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. D. A. Curtland Plant Manager Duane Arnold Energy Center 3277 DAEC Rd.
	Juno Beach, FL 33408-0420 Palo, IA 52324-9785 ~~Mr. W. E. Webster~~ Mr. R. S. Kundalkar ~~Vice President, Nuclear Operations~~ Vice President, Nuclear Engineering Florida Power & Light Company ~~Florida Power & Light Company P. O. Box 14000~~ P. O. Box 14000 Juno Beach, FL 33408-0420 ~~Juno Beach, FL 33408-0420 John Bjorseth~~ Daniel K. McGhee ~~Site Director~~ Iowa Department of Public Health ~~Duane Arnold Energy Center~~ Bureau of Radiological Health ~~3277 DAEC Road~~ 321 East 12th Street ~~Palo, IA 52324~~ Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075 ~~Steven R. Catron Manager, Regulatory Affairs~~ Chairman, Linn County ~~Duane Arnold Energy Center~~ Board of Supervisors ~~3277 DAEC Road~~ 930 1st Street SW ~~Palo, IA 52324~~ Cedar Rapids, IA 52404 ~~U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324~~ October 12, 2006}}		Palo, IA 52324-9785 Mr. R. S. Kundalkar Vice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Daniel K. McGhee Iowa Department of Public Health Bureau of Radiological Health 321 East 12th Street Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075 Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404 October 12, 2006}}