ML063120190
| ML063120190 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/17/2006 |
| From: | Gratton C Plant Licensing Branch III-2 |
| To: | Crane C Exelon Generation Co |
| Gratton C, NRR/DORL 415-1055 | |
| References | |
| GL-03-001, TAC MB9781, TAC MB9782 | |
| Download: ML063120190 (6) | |
Text
November 17, 2006 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NRC RECEIPT OF BYRON STATION, UNIT NOS. 1 AND 2 - RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS.
MB9781 AND MB9782)
Dear Mr. Crane:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to Generic Letter (GL) 2003-01, Control Room Habitability, dated August 11, 2003 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML032310390);
December 9, 2003 (ADAMS Accession No. ML033560302); March 19, 2004 (ADAMS Accession No. ML040890545); September 30, 2004 (ADAMS Accession No. ML042740704);
November 29, 2004 (ADAMS Accession No. ML043420211); January 31, 2005 (ADAMS Accession No. ML050320327); and, July 11, 2005 (ADAMS Accession No. ML051920406) for the Byron Station, Unit Nos. 1 and 2 (Byron). This letter provides a status of your response and describes any actions that may be required to consider your responses to GL 2003-01 complete.
GL 2003-01 requested that you confirm that your control rooms meet their design bases (e.g.
General Design Criterion (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 your design bases for meeting control room operator dose limits from accidents (GL 2003-01, Item 1(a)); (2) determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments (GL 2003-01, Item 1(b)); 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 1(b)). GL 2003-01 further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (GL 2003-01, Item 2).
You reported the results of tracer gas testing for the Byron control rooms that were conducted in accordance with American Society for Testing Materials (ASTM), Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution. You determined that the maximum tested unfiltered inleakage into the control room envelope (CRE), was 68 standard cubic feet per minute (scfm), which is less than the value of 100 cubic feet per minute (cfm) assumed in the design basis radiological analyses for control room habitability.
You indicated that the the most limiting inleakage assumed in your chemical hazards analyses is 78.75 cfm which is more than the maximum tested value of 68 scfm unfiltered inleakage into the CRE. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
C. Crane GL 2003-01 further requested that you assess your technical specifications (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability, and in light of the demonstrated inadequacy of a differential pressure (P) measurement to alone provide such verification (GL 2003-01, Item 1(c)). You stated that the units have a TS requirement for P testing. As permitted by the GL, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your July 11, 2005, response you indicated that you would evaluate your submittal with respect to the elements contained in Technical Specification Task Force (TSTF) change traveler TSTF-448, Control Room Habitability, and resubmit a proposed license amendment request (LAR) based on the evaluation within 90 days following NRC approval of TSTF-448.
The information you provided supported the fact that there are no compensatory measures needed to be in place to demonstrate control room habitability.
The information you provided also supported the conclusion that the units are required to meet the GDC regarding control room habitability, which is documented in the Updated Final Safety Analysis Report.
Your commitment to submit a LAR based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. 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 regarding this correspondence, please contact me at 301-415-1055.
Sincerely,
/RA/
Christopher Gratton, Sr. Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454 and STN 50-455 cc: See next page
C. Crane GL 2003-01 further requested that you assess your technical specifications (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability, and in light of the demonstrated inadequacy of a differential pressure (P) measurement to alone provide such verification (GL 2003-01, Item 1(c)). You stated that the units have a TS requirement for P testing. As permitted by the GL, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your July 11, 2005, response you indicated that you would evaluate your submittal with respect to the elements contained in Technical Specification Task Force (TSTF) change traveler TSTF-448, Control Room Habitability, and resubmit a proposed license amendment request (LAR) based on the evaluation within 90 days following NRC approval of TSTF-448.
The information you provided supported the fact that there are no compensatory measures needed to be in place to demonstrate control room habitability.
The information you provided also supported the conclusion that the units are required to meet the GDC regarding control room habitability, which is documented in the Updated Final Safety Analysis Report.
Your commitment to submit a LAR based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. 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 regarding this correspondence, please contact me at 301-415-1055.
Sincerely,
/RA/
Christopher Gratton, Sr. Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454 and STN 50-455 cc: See next page DISTRIBUTION PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrLADClarke RidsNrrPMCGratton RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDssScvb RidsNrrDprPgcb RidsNrrDorlDpr Adams Accession No. ML063120190 NRR-106 OFFICE NRR/LPL3-1/PM NRR/LPL3-2/LA NRR/PGCB/BC NRR/SCVB/BC NRR/LPL3-1/BC NAME CGratton:mw DClarke CJackson RDennig DCollins DATE 11/15/06 11/15/06 11/14/06 11/16/06 11/17/06 OFFICIAL RECORD COPY
Byron Station, Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4351 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Dwain W. Alexander, Project Manager Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230 Howard A. Learner Environmental Law and Policy Center of the Midwest 35 East Wacker Drive Suite 1300 Chicago, IL 60601-2110 U.S. Nuclear Regulatory Commission Byron Resident Inspectors Office 4448 North German Church Road Byron, IL 61010-9750 Ms. Lorraine Creek RR 1, Box 182 Manteno, IL 60950 Chairman, Ogle County Board P.O. Box 357 Oregon, IL 61061 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, IL 61107 Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Byron Station Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Site Vice President - Byron Station Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Senior Vice President - Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Chairman Will County Board of Supervisors Will County Board Courthouse Joliet, IL 60434 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Regulatory Assurance - Byron Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
Byron Station, Units 1 and 2 cc:
Vice President - Regulatory & Legal Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood and Byron Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President - Midwest Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Barry Quigley 3512 Louisiana Rockford, IL 61108