ML063100218
| ML063100218 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/06/2007 |
| From: | Stang J NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | Gordon Peterson Duke Power Co |
| john stang, NRR/DLPM, 301-415-1345 | |
| References | |
| TAC MB9820, TAC MB9821 | |
| Download: ML063100218 (4) | |
Text
February 6, 2007 Mr. G. R. Peterson Vice President McGuire Nuclear Station Duke Power Company LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
NRC RECEIPT OF MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (MCGUIRE 1 AND 2), RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9820 AND MB9821)
Dear Mr. Peterson:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to Generic Letter (GL) 2003-01, Control Room Habitability, dated August 7, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML032310443), and February 19, 2004 (ADAMS Accession No. ML040630874). This letter provides a status of your responses and describes any additional actions that may be necessary to consider your response to GL 2003-01 complete.
The GL requested that you confirm that your control room meet their 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 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 (CRH), and plans to retire them (GL 2003-01, Item 2).
In your February 19, 2004, letter, you provided the results of the testing performed on the control room using American Society for Testing and Materials(ASTM) Standard, ASTM E741, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution. The test results indicated that the maximum tested value for inleakage into the Control Room Envelope (CRE) was 177 standard cubic feet per minute (scfm) which is less than the value of 610 scfm (with compensatory measure of potassium iodide (KI) assumed in the design basis radiological analyses for CRH. In your February 19, 2004, response, you stated that to retire the compensatory measure, you plan to submit a License Amendment Request (LAR), to incorporate alternative source term methodology into the post-loss-of-coolant accident dose consequence calculation. On December 20, 2005, you submitted the subject LAR.
G. Peterson In your responses to the GL you indicated that your hazardous chemical evaluation accounts for the most-limiting unfiltered in leakage into the CRE is incorpated into the hazardous chemical assessments. You also indicated that reactor control capability is maintained from either the control room or the alternate standby shutdown facility in the event of smoke.
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 CRH, and in light of the demonstrated inadequacy of a delta ()
pressure measurement to alone provide such verification (GL 2003-01, Item 1.c) In your February 19, 2004, response, you indicated that you would review and implement TSTF-448 on a reasonable schedule once it is approved and made available for use. The staff considers 90 days following the NRC approval of TSTF-448 to be a reasonable schedule to submit the license amendment.
The information you provided supported the conclusion that you are required to meet the GDC regarding CRH. Based on your responses, the NRC staff finds that, no additional actions are required and consider actions associated with GL 2003-01 to be complete.
Sincerely,
/RA/
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: See next page
G. Peterson February 6, 2007 In your responses to the GL you indicated that your hazardous chemical evaluation accounts for the most-limiting unfiltered in leakage into the CRE is incorpated into the hazardous chemical assessments. You also indicated that reactor control capability is maintained from either the control room or the alternate standby shutdown facility in the event of smoke.
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 CRH, and in light of the demonstrated inadequacy of a delta ()
pressure measurement to alone provide such verification (GL 2003-01, Item 1.c) In your February 19, 2004, response, you indicated that you would review and implement TSTF-448 on a reasonable schedule once it is approved and made available for use. The staff considers 90 days following the NRC approval of TSTF-448 to be a reasonable schedule to submit the license amendment.
The information you provided supported the conclusion that you are required to meet the GDC regarding CRH. Based on your responses, the NRC staff finds that, no additional actions are required and consider actions associated with GL 2003-01 to be complete.
Sincerely,
/RA/
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: See next page DISTRIBUTION:
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Accession No.: ML063100218 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA SCVB/BC PGCB/BC NRR/LPL2-1/BC NAME JStang /ma MOBrien RDennig CJackson EMarinos DATE 12/28/06 12/27/06 1/3/07 1/3/07 2/6/07 OFFICIAL RECORD COPY
McGuire Nuclear Station, Units 1 & 2 cc:
Mr. G. R. Peterson Vice President McGuire Nuclear Station Duke Power Company LLC 12700 Hagers Ferry Road Hunterville, NC 28078 Ms. Lisa F. Vaughn Associate General Counsel and Managing Attorney Duke Energy Carolinas, LLC 526 South Church Street - EC07H Charlotte, North Carolina 28202 County Manager of Mecklenburg County 720 E. Fourth St.
Charlotte, NC 28202 Mr. C. Jeffrey Thomas Regulatory Compliance Manager Duke Energy Corporation McGuire Nuclear Site 12700 Hagers Ferry Road Huntersville, NC 28078 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission 12700 Hagers Ferry Road Huntersville, NC 28078 Dr. John M. Barry Mecklenburg County Department of Environmental Protection 700 N. Tryon St Charlotte, NC 28202 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road, 12th Floor Charlotte, NC 28210 NCEM REP Program Manager 4713 Mail Service Center Raleigh, NC 27699-4713 Mr. Leonard G. Green Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R.L. Gill, Jr., Manager Nuclear Regulatory Issues &
Industry Affairs Duke Energy Corporation 526 S. Church St.
Mail Stop EC05P Charlotte, NC 28202 Division of Radiation Protection NC Dept of Environment, Health & Natural Resources 3825 Barrett Dr.
Raleigh, NC 27609-7721 Mr. T. Richard Puryear Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, SC 29745 Mr. Henry Barron Group Vice President, Nuclear Generation
& Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006 Ms. Kathryn B. Nolan Senior Counsel Duke Energy Carolinas, LLC 526 South Church Street - EC07H Charlotte, NC 28202