Letter Sequence Other |
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MONTHYEARML0531903342005-11-14014 November 2005
Notice of Meeting with Southern Nuclear Operating Co, Inc., Regarding Control Room In-leakage Testing at Hatch, Units 1 and 2
Project stage: Request
ML0534700922005-11-29029 November 2005
Hatch, Units 1 & 2, Enclosure, Meeting Summary, Generic Letter 2003-01
Project stage: Meeting
ML0534603052005-12-23023 December 2005
Hatch, Units 1 and 2, Meeting Summary, Generic Letter 2003-01 Control Room Habitability
Project stage: Meeting
NL-06-1930, Response to Generic Letter 2003-01, Control Room Habitability2006-09-0101 September 2006
Response to Generic Letter 2003-01, Control Room Habitability
Project stage: Request
ML0625801342006-10-0303 October 2006
Evaluation of Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2, Response to Generic Letter 2003-01 Control Room Habitability (Tac No. MB9810 and MB9811)
Project stage: Other
2005-12-23
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Text
October 3, 2006 Mr. L. M. Stinson Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, AL 35201-1295
SUBJECT:
EVALUATION OF EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9810 AND MB9811)
Dear Mr. Stinson:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses for Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch), to Generic Letter (GL) 2003-01, Control Room Habitability, dated August 4, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML032190245); March 29, 2004 (ADAMS Accession No. ML040910289); October 27, 2004 (ADAMS Accession No. ML043030315);
November 10, 2005 (ADAMS Accession No. ML053180074); and September 1, 2006 (ADAMS Accession No. ML062480132). This letter provides a status of your response and describes any actions that may be required to consider your response to GL 2003-01 complete.
GL 2003-01 requested that you confirm that your control room meets its design bases (e.g.,
General Design Criteria (GDC) 1, 3, 4, 5, & 19, draft GDC, or principal design criteria), paying special attention to the: (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 the plans to retire them (GL 2003-01, Item 2).
In your letter dated September 1, 2006, you reported the results of tracer gas tests of the Hatch control room that were conducted in accordance with American Society for Testing and Materials E741, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution. The control room uses a positive pressure design. You determined that the maximum tested value for inleakage into the control room envelope (CRE) was 5 standard cubic feet per minute (scfm), which is less than the value of 110 scfm assumed in your design-basis radiological dose analysis.
You also reported that the maximum tested unfiltered inleakage for toxic chemical release operation mode is 16 scfm, but did not report what you assumed in your chemical assessment evaluations. However, you indicated that all industrial facilities located within 5 miles of the plant and all hazardous chemicals currently manufactured, stored, or transported in the vicinity
L. Stinson of the plant have been assessed for control room habitability (CRH) and determined to pose no threat to the plant. You also indicated that reactor control capability is maintained from either the control room or the remote safe shutdown panel 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, in light of the demonstrated inadequacy of a differential pressure measurement to alone provide such verification (GL 2003-01, Item 1c). 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 1, 2006, response you stated that you will implement Technical Specification Task Force (TSTF) 448, Control Room Habitability, once it has been approved by the NRC staff.
The information you provided supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH. The information you provided also supported the fact that you meet the intent of the GDCs for CRH. Your commitment to implement TS changes based on TSTF-448, following our formal review and approval of TSTF-448, is acceptable for the purpose of closing out your response to GL 2003-01.
The NRC staff has completed its review of your response to GL 2003-01 and finds it acceptable. The NRC staff looks forward to working with the Southern Nuclear Operating Company, Inc., staff to implement the provisions of TSTF-448.
Please contact me if you have any questions regarding this correspondence.
Sincerely,
/RA/
Christopher Gratton, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 cc: See next page
L. Stinson of the plant have been assessed for control room habitability (CRH) and determined to pose no threat to the plant. You also indicated that reactor control capability is maintained from either the control room or the remote safe shutdown panel 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, in light of the demonstrated inadequacy of a differential pressure measurement to alone provide such verification (GL 2003-01, Item 1c). 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 1, 2006, response you stated that you will implement Technical Specification Task Force (TSTF) 448, Control Room Habitability, once it has been approved by the NRC staff.
The information you provided supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH. The information you provided also supported the fact that you meet the intent of the GDCs for CRH. Your commitment to implement TS changes based on TSTF-448, following our formal review and approval of TSTF-448, is acceptable for the purpose of closing out your response to GL 2003-01.
The NRC staff has completed its review of your response to GL 2003-01 and finds it acceptable. The NRC staff looks forward to working with the Southern Nuclear Operating Company, Inc., staff to implement the provisions of TSTF-448.
Please contact me if you have any questions regarding this correspondence.
Sincerely,
/RA/
Christopher Gratton, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 cc: See next page Distribution:
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RidsNrrDprPgcb (CJackson) RidsNrrDorlDpr SLee, EDO, Rgn1 DOCUMENT NAME: E:\Filenet\ML062580134.wpd ML062580134 NRR-106 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/PGCB/BC NRR/SCVB/BC NRR/LPL2-1/BC NAME CGratton MOBrien CJackson RDennig EMarinos DATE / /06 / /06 / /06 / /06 / /06 OFFICIAL RECORD COPY
Edwin I. Hatch Nuclear Plant, Unit Nos. 1 & 2 cc:
Laurence Bergen Mr. Jeffrey T. Gasser Oglethorpe Power Corporation Executive Vice President 2100 E. Exchange Place Southern Nuclear Operating Company, Inc.
P.O. Box 1349 P.O. Box 1295 Tucker, GA 30085-1349 Birmingham, AL 35201-1295 Mr. R. D. Baker Mr. Dennis R. Madison, General Manager Manager - Licensing Edwin I. Hatch Nuclear Plant Southern Nuclear Operating Company, Inc. Southern Nuclear Operating Company, Inc.
P.O. Box 1295 U.S. Highway 1 North Birmingham, AL 35201-1295 P.O. Box 2010 Baxley, GA 31515 Resident Inspector Plant Hatch Mr. K. Rosanski 11030 Hatch Parkway N. Resident Manager Baxley, GA 31531 Oglethorpe Power Corporation Edwin I. Hatch Nuclear Plant Harold Reheis, Director P.O. Box 2010 Department of Natural Resources Baxley, GA 31515 205 Butler Street, SE., Suite 1252 Atlanta, GA 30334 Mr. L. M. Stinson Vice President - Nuclear Hatch Project Steven M. Jackson Southern Nuclear Operating Company, Inc.
Senior Engineer - Power Supply P.O. Box 1295 Municipal Electric Authority of Georgia Birmingham, AL 35201-1295 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334 Arthur H. Domby, Esq.
Troutman Sanders Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 30308-2216 Chairman Appling County Commissioners County Courthouse Baxley, GA 31513
