ML063110363
| ML063110363 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/06/2006 |
| From: | Siva Lingam NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Lingam, Siva NRR/DORL 415-1564 | |
| References | |
| GL-03-001, TAC MB9861, TAC MB9862 | |
| Download: ML063110363 (4) | |
Text
November 6, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2, RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9861 AND MB9862)
Dear Mr. Christian:
The 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 April 22, 2004, (ADAMS Accession No. ML041130386). 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 Surry Power Station, Unit Nos. 1 and 2 (Surry 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 (CRH), and plans to retire these compensatory measures (GL 2).
By letter dated April 22, 2004, you reported the results of the American Society for Testing and Materials E741 tracer gas tests for the common Surry 1 and 2 control room, conducted in a non-pressurized alignment. Your design/licensing basis is a pressurized Control Room Envelope (CRE), however, you stated that a test in a non-pressurized condition with adjacent area ventilation in the post-accident alignment (secured) would be bounding for unfiltered inleakage. The analysis showed that the maximum tested value for unfiltered inleakage into the CRE, was 147 (+/- 6 cfm), which is less than the value of 500 cfm assumed in the design-basis radiological dose analyses for CRH.
You indicated the hazardous chemical events were evaluated on the basis of no action being taken by the control room operator; i.e, the unfiltered inleakage assumed in your toxic gas event is twice that of the radiological events; therefore, the most-limiting inleakage value of 147 (+/- 6) cfm is incorporated in your design-basis hazardous assessment. You also indicated that reactor control capability is maintained from either the control room or the alternate
D. Christian 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, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL 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 the April 22, 2004, submittal, you committed to submitting a proposed TS change that will incorporate the intent of Technical Specification Task Force (TSTF) Traveler 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 your 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 Surry 1 and 2.
Sincerely,
/RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281 cc: See next page
ML063110363 OFFICE NRR/LPL2-1/PM NRR/LPD2-1/LA NRR/SCVB/BC NRR/LPL2-1/BC NAME SLingam MOBrien RDennig EMarinos DATE 11/2/06 11/2/06 11/5/06 11/6 /06
D. Christian Surry Power Station, Units 1 & 2 cc:
Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385 Mr. Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711