ML062920257
| ML062920257 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/19/2006 |
| From: | Robert Kuntz Plant Licensing Branch III-2 |
| To: | Crane C Exelon Generation Co |
| kuntz, Robert , NRR/DORL, 415-3733 | |
| References | |
| GL-03-001, STN-50-456, STN-50-457, TAC MB9774, TAC MB9775 | |
| Download: ML062920257 (5) | |
Text
December 19, 2006 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC Braidwood Station 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NRC RECEIPT OF BRAIDWOOD STATION, UNITS NOS. 1 AND 2, RESPONSES TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9774 AND MB9775)
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 Access and 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); February 7, 2005 (ADAMS Accession No. ML050490183); and July 11, 2005 (ADAMS Accession No. ML051920406), for the Braidwood Station, Unit Nos. 1 and 2 (Braidwood). This letter provides a status of your responses and describes any additional information 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 1a); (2) determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments; 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). 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).
By letter dated February 7, 2005, you reported the results of American Society for Testing and Materials (ASTM) Standard E741, ?Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution, tracer gas tests for the Braidwood control room:
The Braidwood Station limiting design basis accident analysis control room operator dose, based on an assumed CRE [control room envelope] unfiltered inleakage rate of 100 SCFM [standard cubic feet per minute], bounds the dose that would result from the most limiting measured unfiltered inleakage rate of 29.3 SCFM, and remains within the 10 CFR 50, Appendix A, GDC 19 limits of five rem whole body and 30 rem thyroid. Therefore, Braidwood Station has
C. Crane demonstrated that the most limiting unfiltered inleakage into the CRE is bounded by the value assumed in the design basis accident radiological analyses for control room habitability.
You indicated that Braidwood has a chemical control program for on-site chemicals which ensures there is no impact to the sites current control room habitability analysis, and that analyses performed in accordance with Regulatory Guide (RG) 1.78, Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated Hazardous Chemical Release, and RG 1.95, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release, concluded that no offsite toxic chemicals were a concern for control room habitability. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
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 delta pressure (P) measurement to alone provide such verification (GL 2003-01, Item 1.c). You stated that the unit has a TS requirement for P testing. In your July 11, 2005, response you withdrew your previous license amendment request (LAR) for administrative controls and indicated that you would evaluate your submittal with respect to the elements contained in Technical Specification Task Force Traveler No. 448 (TSTF-448)
Control Room Habitability, and resubmit a proposed LAR based on that evaluation. As permitted by GL 2003-01, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. Your schedule for resubmitting the LAR is within 90 days of NRC approval of TSTF-448.
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability.
Your commitment to submit a proposed 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 proposed LAR and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me at (301) 415-3733.
Sincerely,
/RA/
Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN 50-457 cc: See next page
C. Crane demonstrated that the most limiting unfiltered inleakage into the CRE is bounded by the value assumed in the design basis accident radiological analyses for control room habitability.
You indicated that Braidwood has a chemical control program for on-site chemicals which ensures there is no impact to the sites current control room habitability analysis, and that analyses performed in accordance with Regulatory Guide (RG) 1.78, Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated Hazardous Chemical Release, and RG 1.95, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release, concluded that no offsite toxic chemicals were a concern for control room habitability. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
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 delta pressure (P) measurement to alone provide such verification (GL 2003-01, Item 1.c). You stated that the unit has a TS requirement for P testing. In your July 11, 2005, response you withdrew your previous license amendment request (LAR) for administrative controls and indicated that you would evaluate your submittal with respect to the elements contained in Technical Specification Task Force Traveler No. 448 (TSTF-448)
Control Room Habitability, and resubmit a proposed LAR based on that evaluation. As permitted by GL 2003-01, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. Your schedule for resubmitting the LAR is within 90 days of NRC approval of TSTF-448.
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability.
Your commitment to submit a proposed 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 proposed LAR and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me at (301) 415-3733.
Sincerely,
/RA/
Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN 50-457 cc: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNRRPMRKuntz RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr JRobinson, NRR RidsNrrDssScvb RidsNrrDprPgcb ADAMS Accession Number:ML062920257 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA SCVB/BC PGCB/BC LPL3-2/BC NAME RKuntz:mw EWhitt RDennig CJackson MMarshall DATE 12/6/2006 12/6/2006 12/8/2006 12/15/06 12/19/2006 OFFICIAL RECORD COPY
Braidwood Station Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Dwain W. Alexander, Project Manager Westinghouse Electric Corporation Energy Systems Business Unit Post Office Box 355 Pittsburgh, PA 15230 Ms. Bridget Little Rorem Appleseed Coordinator 117 N. Linden Street Essex, IL 60935 Howard A. Learner Environmental Law and Policy Center of the Midwest 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110 U.S. Nuclear Regulatory Commission Braidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Braceville, IL 60407 Ms. Lorraine Creek RR 1, Box 182 Manteno, IL 60950 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 County Executive Will County Office Building 302 N. Chicago Street Joliet, IL 60432 Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Braidwood Station Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Site Vice President - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Senior Vice President - Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Chairman, Ogle County Board Post Office Box 357 Oregon, IL 61061 Manager Regulatory Assurance - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Braidwood Station Units 1 and 2 Senior Vice President - Midwest Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Regulatory and Legal Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood, Byron and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555