ML070050060

NRC Receipt of Oconee Nuclear Station, Units 1, 2, and 3, Response to Generic Letter 2003-01

ML070050060
Person / Time
Site:	Oconee
Issue date:	01/09/2007
From:	Olshan L NRC/NRR/ADRO/DORL/LPLII-1
To:	Brandi Hamilton Duke Power Co
Olshan L N, NRR/DORL, 415-1419
References
GL-03-001, TAC MB9829, TAC MB9830, TAC MB9831
Download: ML070050060 (5)

Text

January 9, 2007 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

NRC RECEIPT OF OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (OCONEE), RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9829, MB9830, AND MB9831)

Dear Mr. Hamilton:

The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response to Generic Letter 2003-01, Control Room Habitability, dated December 9, 2003 (Agencywide Documents Access and Management System [ADAMS] Accession No. ML033510109). This letter provides a status of your response and describes any actions that may be necessary to consider your response to GL 2003-01 complete.

The GL requested that you confirm that your control rooms 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, and plans to retire them (GL 2003-01, Item 2).

You reported the results of ASTM E741(American Society for Testing Materials, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution) tracer gas tests for the Oconee control rooms. The control room for Units 1 and 2 are common while the control room for Unit 3 is separate. All control rooms are pressurized for accident mitigation.

B. Hamilton For Units 1 and 2 you determined that the maximum tested value for unfiltered inleakage into the control room envelope (CRE) was 869 (+/- 31) actual cubic feet per minute (acfm) for normal alignment (pre-booster pump actuation) and 0 (+/- 30) standard cubic feet per minute (scfm) for emergency alignment (post-booster fan actuation). These values are less than the unfiltered inleakage values of 1150 cfm (pre-booster pump actuation) and 40 cfm (post-booster pump actuation) assumed in your design basis radiological dose analyses for control room habitability (CRH).

For Unit 3 you determined that the maximum tested value for unfiltered inleakage into the CRE was 467 (+/- 16) acfm for normal alignment (pre-booster pump actuation) and 0 (+/- 42) scfm for emergency alignment (post-booster pump actuation). These values are less than the unfiltered inleakage values of 1150 cfm (pre-booster pump actuation) and 40 cfm (post-booster pump actuation) assumed in your design basis radiological dose analyses for CRH.

You indicated that your hazardous chemical assessment accounts for the most-limiting unfiltered inleakage into the Oconee CRE, which occurs during normal operation with the booster fans OFF. This value is 1065 cfm for the Units 1 and 2 control rooms and 534 cfm for the Unit 3 control room from the 1998 tracer gas test. Since your 2001 tracer gas test results are lower (869 +/- 31 and 467 +/- 16, respectively) the information you provided adequately supported the conclusion that the most-limiting unfiltered in leakage into the CRE is incorporated into the hazardous chemical assessments. You also indicated that reactor control capability is maintained from either the control room or the the 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 () P measurement to alone provide such verification (GL 2003-01, Item 1.c). 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 December 9, 2003, response, you stated your plans to implement Technical Specification Task Force (TSTF)-448 once it is made available for use.

The information you provided also supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH.

B. Hamilton The information you provided also supported the conclusion that you are committed to meet the intent of the draft GDC regarding CRH which is documented in your Updated Final Safety Evaluation Report (UFSAR).

Based on the information provided and your plans to implement TSTF-448, the NRC staff finds your responses to GL 2003-01 complete.

If you have any questions regarding this correspondence, please contact me.

Sincerely,

/RA/

Leonard N. Olshan, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287 cc: See next page

B. Hamilton January 9, 2007 The information you provided also supported the conclusion that you are committed to meet the intent of the draft GDC regarding CRH which is documented in your Updated Final Safety Evaluation Report (UFSAR).

Based on the information provided and your plans to implement TSTF-448, the NRC staff finds your responses to GL 2003-01 complete.

If you have any questions regarding this correspondence, please contact me.

Sincerely,

/RA/

Leonard N. Olshan, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270 and 50-287 cc: See next page Distribution:

PUBLIC RidsNrrLAMOBrien RidsAcrsAcwnMailCenter LPL2-1 R/F RidsNrrPMLOlshan RidsRgn2MailCenter (MErnstes)

RidsNrrDorlLpl2-1(EMarinos) RidsOgcRp RidsNrrDorlDpr Accession Number: ML070050060 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC NAME LOlshan:nc MOBrien EMarinos DATE 1/8/2007 1/8/2007 1/9/2007 OFFICIAL RECORD COPY

Oconee Nuclear Station, Units 1, 2, and 3 cc:

Mr. Bruce H. Hamilton Mr. Leonard G. Green Vice President, Oconee Site Assistant Attorney General Duke Power Company LLC NC Department of Justice 7800 Rochester Highway P.O. Box 629 Seneca, SC 29672 Raleigh, NC 27602 Ms. Lisa F. Vaughn Mr. R. L. Gill, Jr.

Associate General Counsel and Managing Manager - Nuclear Regulatory Attorney Issues and Industry Affairs Duke Energy Carolinas, LLC Duke Power Company LLC 526 South Church Street - EC07H 526 S. Church St.

Charlotte, North Carolina 28202 Mail Stop EC05P Charlotte, NC 28202 Manager, LIS NUS Corporation Division of Radiation Protection 2650 McCormick Dr., 3rd Floor NC Dept of Environment, Health, & Natural Clearwater, FL 34619-1035 Resources 3825 Barrett Dr.

Senior Resident Inspector Raleigh, NC 27609-7721 U.S. Nuclear Regulatory Commission 7812B Rochester Highway Mr. Peter R. Harden, IV Seneca, SC 29672 VP-Customer Relations and Sales Westinghouse Electric Company Mr. Henry Porter, Director 6000 Fairview Road Division of Radioactive Waste Management 12th Floor Bureau of Land and Waste Management Charlotte, NC 28210 Dept. of Health and Env. Control 2600 Bull St. Mr. Henry Barron Columbia, SC 29201-1708 Group Vice President, Nuclear Generation and Chief Nuclear Officer Mr. Michael A. Schoppman P.O. Box 1006-EC07H Framatome ANP Charlotte, NC 28201-1006 1911 North Ft. Myer Dr.

Suite 705 Mr. Charles Brinkman Rosslyn, VA 22209 Director, Washington Operations Westinghouse Electric Company Mr. B. G. Davenport 12300 Twinbrook Parkway, Suite 330 Regulatory Compliance Manager Rockville, MD 20852 Oconee Nuclear Site Duke Energy Corporation Ms. Kathryn B. Nolan ON03RC Senior Counsel 7800 Rochester Highway Duke Energy Carolinas, LLC Seneca, SC 29672 526 South Church Street - EC07H Charlotte, NC 28202