ML063480040
| ML063480040 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/05/2007 |
| From: | Lyon C NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Koehl D Nuclear Management Co |
| F. Lyon LPLE X2296 | |
| References | |
| TAC MB9841, TAC MC9842 | |
| Download: ML063480040 (4) | |
Text
January 5, 2007 Mr. Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - CLOSEOUT OF NRC GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9841 AND MB9842)
Dear Mr. Koehl:
On July 12, 2003, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2003-01, Control Room Habitability (Agencywide Documents Access and Management System (ADAMS) Accession No. ML031620248), to all holders of operating licenses for nuclear power reactors except those who have permanently ceased operation and have certified that fuel has been removed from the reactor vessel.
GL 2003-01 requested that each licensee confirm that its facilitys control room meets its 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 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, and corrective actions needed to retire these compensatory measures (GL 2003-01, Item 2).
By letters dated August 11, 2003 (ADAMS Accession No. ML032580984), December 5, 2003 (ADAMS Accession No. ML033500466), September 29, 2004 (ADAMS Accession No. ML042820156), August 22, 2005 (ADAMS Accession No. ML052420480), and December 8, 2006 (ADAMS Accession No. ML063420598), Nuclear Management Company, LLC (NMC),
responded to GL 2003-01 for the Point Beach Nuclear Plant, Units 1 and 2 (PBNP).
In your response, you reported the results of tracer gas tests for the PBNP control room, which is common to Units 1 and 2 and is pressurized for accident mitigation. The testing was based on the methodology of American Society for Testing Materials (ASTM) 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) was 96 standard cubic feet per minute (SCFM), which is more than the value of 10 cfm of unfiltered inleakage assumed in the PBNP design-basis radiological analyses for control room habitability.
You stated that an engineering evaluation demonstrated that the increase in dose due to the
D. Koehl incorporation of the measured unfiltered inleakage, can be offset by changes made to the assumed containment sump volume and containment leakage. You also stated that no additional compensatory measures are required to ensure operability of the control room ventilation system. In your December 8, 2006, response, you made the following commitment:
NMC will submit a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance within the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term [AST]
methodology by July 30, 2007. As part of this submittal, the post accident reliance on KI [potassium iodide] for control room staff will be addressed.
You also provided information that adequately supported a conclusion that the most limiting unfiltered inleakage into the CRE is incorporated into the hazardous chemical assessments, and that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
In light of the demonstrated inadequacy of a pressure change (P) measurement alone to verify the integrity of the CRE, the GL further requested that licensees assess their facilitys Technical Specifications (TSs) to determine if the TSs adequately verified the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability. As permitted by the GL, you provided a schedule for revising the surveillance requirement in the TSs to reference an acceptable surveillance methodology. In your September 29, 2004, letter, you stated that NMC will provide TS changes to reference an acceptable surveillance methodology following NRC approval of Technical Specification Task Force (TSTF) Traveler 448 (TSTF-448), Control Room Habitability.
NMCs commitments to submit license amendment requests to (1) revise the current accident analysis for PBNP using the AST methodology and (2) reference an acceptable surveillance methodology based on TSTF-448, following NRC approval, are acceptable to the NRC staff for the purpose of closing GL 2003-01 for PBNP.
If you have any questions regarding this matter, please contact me at (301) 415-2296.
Sincerely,
/RA/
Carl F. Lyon, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page
D. Koehl incorporation of the measured unfiltered inleakage, can be offset by changes made to the assumed containment sump volume and containment leakage. You also stated that no additional compensatory measures are required to ensure operability of the control room ventilation system. In your December 8, 2006, response, you made the following commitment:
NMC will submit a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance within the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term [AST]
methodology by July 30, 2007. As part of this submittal, the post accident reliance on KI [potassium iodide] for control room staff will be addressed.
You also provided information that adequately supported a conclusion that the most limiting unfiltered inleakage into the CRE is incorporated into the hazardous chemical assessments, and that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
In light of the demonstrated inadequacy of a pressure change (P) measurement alone to verify the integrity of the CRE, the GL further requested that licensees assess their facilitys Technical Specifications (TSs) to determine if the TSs adequately verified the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability. As permitted by the GL, you provided a schedule for revising the surveillance requirement in the TSs to reference an acceptable surveillance methodology. In your September 29, 2004, letter, you stated that NMC will provide TS changes to reference an acceptable surveillance methodology following NRC approval of Technical Specification Task Force (TSTF) Traveler 448 (TSTF-448), Control Room Habitability.
NMCs commitments to submit license amendment requests to (1) revise the current accident analysis for PBNP using the AST methodology and (2) reference an acceptable surveillance methodology based on TSTF-448, following NRC approval, are acceptable to the NRC staff for the purpose of closing GL 2003-01 for PBNP.
If you have any questions regarding this matter, please contact me at (301) 415-2296.
Sincerely,
/RA/
Carl F. Lyon, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page DISTRIBUTION PUBLIC LPL3-1 R/F RidsAcrsAcnwMailCenter RidsNrrDprPgcb RidsNrrDorlLpl3-1 RidsNrrLATHarris RidsRgn3MailCenter RidsNrrPMFLyon RidsOgcRp RidsNrrDorlDpr JRobinson GTesfaye RidsNrrDssScvb ADAMS Accession Number: ML063480040 *Memo OFFICE LPL3-1/PM LPL3-1/LA SCVB/BC PGCB/BC LPL3-1/BC NAME FLyon:ca THarris RDennig CJackson P. Tam for PMilano DATE 12/19/06 12/15/06 12/19/06 12/22/06 1/5/07 OFFICIAL RECORD COPY
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Mr. Jeffery Kitsembel Vice President, Counsel & Secretary Electric Division Nuclear Management Company, LLC Public Service Commission of Wisconsin 700 First Street P.O. Box 7854 Hudson, WI 54016 Madison, WI 53707-7854 Mr. F. D. Kuester Nuclear Asset Manager President & Chief Executive Officer Wisconsin Electric Power Company WE Generation 231 West Michigan Street 231 West Michigan Street Milwaukee, WI 53201 Milwaukee, WI 53201 Michael B. Sellman Regulatory Affairs Manager President and Chief Executive Officer Point Beach Nuclear Plant Nuclear Management Company, LLC Nuclear Management Company, LLC 700 First Street 6610 Nuclear Road Hudson, MI 54016 Two Rivers, WI 54241 Douglas E. Cooper Mr. Ken Duveneck Senior Vice President & Chief Nuclear Town Chairman Officer Town of Two Creeks Nuclear Management Company, LLC 13017 State Highway 42 700 First Street Mishicot, WI 54228 Hudson, WI 54016 Chairman Site Director of Operations Public Service Commission Nuclear Management Company, LLC of Wisconsin 6610 Nuclear Road P.O. Box 7854 Two Rivers, WI 54241 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 November 2005