ML062710532
| ML062710532 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/20/2006 |
| From: | Stephen Monarque NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Monarque, S R, NRR/DORL, 415-1544 | |
| References | |
| GL-03-001, TAC MB9827, TAC MB9828 | |
| Download: ML062710532 (4) | |
Text
September 20, 2006 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9827 AND MB9828)
Dear Mr. Christian:
The U.S. 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. ML032310416), and March 30, 2004, (ADAMS Accession No. ML040970428). 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 for North Anna Power Station, Unit Nos. 1 and 2 (North Anna 1 and 2).
The GL requested confirmation that your control room meets the 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 1(a)); (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 1(b)). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire these compensatory measures (GL 2).
By letter dated March 30, 2004, you reported the results of the American Society for Testing and Materials E741 tracer gas tests for the North Anna 1 and 2 control room, which is a common control room pressurized for accident mitigation. This analysis showed that the maximum tested value for inleakage into the Control Room Envelope (CRE) was 150 cfm in the non-pressurized alignment, which is less than the value of 500 cfm assumed in the design-basis radiological analysis for control room habitability (CRH).
You indicated the toxic chemical assessments were evaluated on the basis of no action being taken by the control room operator (i.e., normal or emergency supply system remains operating). As such, you assumed the nominal flow of an emergency supply fan (1000 cfm) for unfiltered inleakage value in your toxic chemical design basis analysis. Since the maximum tested inleakage value into the CRE is 150 cfm, you concluded that the most-limiting unfiltered in leakage into the CRE is incorporated into the hazardous chemical assessments. You also
D. Christian indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
The GL further requested an assessment of the Technical Specifications (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design-basis analyses for CRH, in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL Item 1(c)). A schedule was provided in the March 30, 2004, submittal for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In the March 30, 2004, submittal you committed to submitting a proposed TS change that will incorporate the intent of Technical Specification Task Force (TSTF)-448, Control Room Habitability, within 6 months following the NRC staffs approval of TSTF-448.
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate CRH, and concluded that you are committed to meet the GDC regarding CRH.
Your commitment to submit a license amendment request based on TSTF-448, following the NRC staffs formal review and approval of this TSTF, is acceptable for purposes of closing out the NRC staffs review of GL 2003-01 for North Anna 1 and 2.
Sincerely,
/RA/
Stephen R. Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 cc: See next page
ML062710532 OFFICE NRR/LPL2-1/PM NRR/LPD2-1/LA NRR/DPR/PGCB/BC NRR/SCVB/BC NRR/LPL2-1/BC NAME SMonarque MOBrien CJackson RDennig EMarinos DATE 9/18/06 9/18/06 09/05/2006 09/05/2006 9/20/06
North Anna Power Station, Units 1 & 2 cc:
Mr. C. Lee Lintecum County Administrator Louisa County Post Office Box 160 Louisa, Virginia 23093 Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Building 475, 5 th floor Rope Ferry Road Waterford, Connecticut 06385 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U. S. Nuclear Regulatory Commission P. O. Box 490 Mineral, Virginia 23117 Mr. Jack M. Davis Site Vice President North Anna Power Station Virginia Electric and Power Company Post Office Box 402 Mineral, Virginia 23117-0402 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218