ML070230029

Closeout of Generic Letter 2003-01, Control Room Habitability

ML070230029
Person / Time
Site:	Waterford
Issue date:	01/29/2007
From:	Fields M NRC/NRR/ADRO/DORL/LPLIV
To:	Walsh K Entergy Operations
Fields, M B, NRR/DORL/LPL4, 415-3062
References
GL-03-001, TAC MB9871
Download: ML070230029 (5)

Text

January 29, 2007 Mr. Kevin T. Walsh Vice President of Operations Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CLOSEOUT OF GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NO. MB9871)

Dear Mr. Walsh:

By letters dated August 7, 2003, September 30, and October 8, 2004 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML032260027, ML042780375, and ML042880299, respectively), Entergy Operations, Inc. (the licensee), responded to Generic Letter (GL) 2003-01, Control Room Habitability, for the Waterford Steam Electric Station, Unit 3 (Waterford 3).

The GL requested that you confirm that your control room meets its design bases (e.g.,

General Design Criteria [GDC] 1, 3, 4, 5, & 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 (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, and plans to retire them (GL 2003-01, Item 2).

The Waterford 3 control room is pressurized for accident mitigation and is designed in accordance with the design criteria contained in the GDCs regarding control room habitability, as documented in your Updated Final Safety Analysis Report.

You reported the results of tracer gas tests for the control room conducted using the guidance of American Society for Testing Materials E741, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution.

You determined that the tested value for inleakage into the control room envelope (CRE) in the isolation mode was 59 cubic feet per minute (cfm), which is less than the value of 220 cfm assumed in the design-basis toxic gas hazard analysis for control room habitability (CRH).

You determined that the tested value for inleakage into the CRE in the pressurization mode was 36 cfm, which is more than the value of 13 cfm assumed in the original design-basis radiological dose analyses for CRH. On July 15, 2004 (ADAMS Accession No. ML042020294),

you submitted a license amendment request to utilize alternative source term methodology

K. T. Walsh which would change the assumed value in the design-basis radiological analysis to a minimum 65 cfm and maximum of 200 cfm (depending on the event). On March 29, 2005 (ADAMS Accession No. ML050890248), the Nuclear Regulatory Commission (NRC) staff approved this license amendment request.

You also provided information that control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke. The information you provided also supported the fact that there are no compensatory measures needed to be in place to demonstrate control room habitability.

The GL 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 in light of the demonstrated inadequacy of a delta pressure measurement to alone provide such verification (GL 2003-01, Item 1c). In your October 8, 2004, response you committed to submit a TS amendment request to modify the requirements related to CRE habitability in accordance with Technical Specification Task Force Traveler 448 (TSTF-448) within 6 months after the final approved Consolidated Line Item Improvement Process for TSTF-448 is published in the Federal Register.

Based on the licensees letters responding to the GL and its commitment to submit a TS amendment request adopting TSTF-448, the NRC staff concludes that GL 2003-01 is considered closed for Waterford 3. If you have any questions, please contact me at (301) 415-3062.

Sincerely,

/RA/

Mel B. Fields, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-382 cc: See next page

K. T. Walsh which would change the assumed value in the design-basis radiological analysis to a minimum 65 cfm and maximum of 200 cfm (depending on the event). On March 29, 2005 (ADAMS Accession No. ML050890248), the Nuclear Regulatory Commission (NRC) staff approved this license amendment request.

You also provided information that control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke. The information you provided also supported the fact that there are no compensatory measures needed to be in place to demonstrate control room habitability.

The GL 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 in light of the demonstrated inadequacy of a delta pressure measurement to alone provide such verification (GL 2003-01, Item 1c). In your October 8, 2004, response you committed to submit a TS amendment request to modify the requirements related to CRE habitability in accordance with Technical Specification Task Force Traveler 448 (TSTF-448) within 6 months after the final approved Consolidated Line Item Improvement Process for TSTF-448 is published in the Federal Register.

Based on the licensees letters responding to the GL and its commitment to submit a TS amendment request adopting TSTF-448, the NRC staff concludes that GL 2003-01 is considered closed for Waterford 3. If you have any questions, please contact me at (301) 415-3062.

Sincerely,

/RA/

Mel B. Fields, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-382 cc: See next page DISTRIBUTION:

PUBLIC RidsNrrDorlLpl4 (DTerao) RidsRgn4MailCenter LPLIV r/f RidsNrrDssScvb (RDennig) RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrPMMFields JRobinson, NRR RidsNrrDprPgcb (CJackson) RidsNrrDorl (CHaney/JLubinski) RidsNrrLAJBurkhardt ADAMS Accession No.: ML070230029 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/SCVB/BC NRR/PGCB/BC NRR/LPL4/BC NAME MFields LFeizollahi RDennig CJackson DTerao DATE 1/23/07 1/23/07 1/23/07 1/25/07 1/29/07 OFFICIAL AGENCY RECORD

Waterford Steam Electric Station, Unit 3 cc:

Vice President, Operations Support Director, Nuclear Safety & Licensing Entergy Operations, Inc. Entergy Operations, Inc.

P.O. Box 31995 1340 Echelon Parkway Jackson, MS 39286-1995 Jackson, MS 39213-8298 Director Louisiana Department of Environmental Nuclear Safety Assurance Quality Radiological Emergency Planning Entergy Operations, Inc. and Response Division 17265 River Road P.O. Box 4312 Killona, LA 70057-3093 Baton Rouge, LA 70821-4312 General Manager Plant Operations Louisiana Department of Environmental Waterford 3 SES Quality Entergy Operations, Inc. Office of Environmental Compliance 17265 River Road P.O. Box 4312 Killona, LA 70057-3093 Baton Rouge, LA 70821-4312 Manager, Licensing Chairman Entergy Operations, Inc. Louisiana Public Services Commission 17265 River Road P.O. Box 91154 Killona, LA 70057-3093 Baton Rouge, LA 70825-1697 Resident Inspector/Waterford NPS Richard Penrod, Senior Environmental P.O. Box 822 Scientist/State Liaison Officer Killona, LA 70066-0751 Office of Environmental Services Northwestern State University Regional Administrator, Region IV Russell Hall, Room 201 U.S. Nuclear Regulatory Commission Natchitoches, LA 71497 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Parish President Council St. Charles Parish P.O. Box 302 Hahnville, LA 70057 Executive Vice President &

Chief Operating Officer Entergy Operations, Inc.

P.O. Box 31995 Jackson, MS 39286-1995 November 2006