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{{#Wiki_filter:October 11, | {{#Wiki_filter:October 11, 2006 Mr. Thomas D. Walt, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550 | ||
==SUBJECT:== | ==SUBJECT:== | ||
H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 - NRC RECEIPT | H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 - NRC RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NO. MB9848) | ||
==Dear Mr. Walt:== | ==Dear Mr. Walt:== | ||
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response | The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response to Generic Letter (GL) 2003-01, Control Room Habitability, in a letter dated December 08, 2003 (Agencywide Document and Access Management System (ADAMS) Accession No. | ||
ML033440212). This letter provides a status of your response and describes any additional information that may be necessary to consider your response to GL 2003-01 complete. GL 2003-01 requested that you confirm that your control room meet its design bases(e.g., General Design Criteria (GDC) 1, 3, 4, 5, and 19, draft GDCs, or principal design criteria), | ML033440212). This letter provides a status of your response and describes any additional information that may be necessary to consider your response to GL 2003-01 complete. | ||
with special attention to: | GL 2003-01 requested that you confirm that your control room meet its design bases (e.g., General Design Criteria (GDC) 1, 3, 4, 5, and 19, draft GDCs, or principal design criteria), | ||
and 90 cfm (Mode 3) assumed in the design basis radiological dose analyses for CRH. In your April 10, 2003, letter, you also reported that the maximum tested inleakage value for | 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 (Item 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 (Item 1.b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability (CRH), and plans to retire them (Item 2). | ||
Your response referenced an April 10, 2003, letter (ADAMS Accession No. ML031050027) in which 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 pressurized H. B. Robinson Steam Electric Plant, Unit No. 2 control room. You determined that the maximum tested value for inleakage into the control room envelope (CRE) was 141 (+/- 5) cubic feet per minute (cfm) for Mode 1; 64 (+/- 15) cfm for Mode 2; 30 (+/- 14) cfm for Mode 3. These values were all less than the values of 160 cfm loss-of-coolant accident (LOCA)-Mode 1) and 290 cfm (non-LOCA-Mode 1); 160 cfm (Mode 2); | |||
and 90 cfm (Mode 3) assumed in the design basis radiological dose analyses for CRH. | |||
In your April 10, 2003, letter, you also reported that the maximum tested inleakage value for the hazardous chemical recirculation mode was 93 (+/-3) cfm, which is less than the total intake flow of 570 cfm assumed in your design basis hazardous chemical analysis. You indicated that reactor control capability is maintained from either the control room or the alternate shutdown location in the event of smoke. | |||
ML061910159).The information you provided also supported the fact that there are no compensatory | T. D. Walt The GL further requested that you assess your technical specifications to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability, and in light of the demonstrated inadequacy of a delta () P (pressure change) measurement to alone provide such verification (Item 1.c). | ||
David T. | As permitted by the GL, you provided a schedule for revising the surveillance requirement in the technical specification (TS) to reference an acceptable surveillance methodology. In your December 9, 2003, response you indicated that you will submit a license amendment request to revise your TS utilizing Technical Specification Task Force (TSTF)Traveler TSTF-448 within 6 months of the approval of TSTF-448 by the NRC. | ||
Raleigh, North Carolina | The information you provided also supported the fact that all compensatory measures needed to demonstrate CRH have been retired following the July 11, 2006, NRC approval of your LOCA Alternate Source Term submittal (ADAMS Accession No. ML061910159). | ||
Washington, DC 20037- | The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability. | ||
The information you provided also supported the conclusion that your are committed to meet the intent of the GDC regarding control room habitability which is documented in your Safety Evaluation. | |||
Your commitment to submit a license amendment request based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submittal of the license amendment request and interact with you as necessary during the amendment process. | |||
If you have any questions regarding this correspondence, please contact me. | |||
Sincerely, | |||
/RA/ | |||
Brenda Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261 cc: See next page | |||
ML061910159). | |||
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability. | |||
The information you provided also supported the conclusion that your are committed to meet the intent of the GDC regarding control room habitability which is documented in your Safety Evaluation. | |||
Your commitment to submit a license amendment request based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submittal of the license amendment request and interact with you as necessary during the amendment process. | |||
If you have any questions regarding this correspondence, please contact me. | |||
Sincerely, | |||
/RA/ | |||
Brenda Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261 cc: See next page DISTRIBUTION: | |||
PUBLIC LPL2-2 r/f J. Robinson, NRR RidsNrrDorlLpl2-2 RidsNrrLACSola RidsNrrDssScvb RidsNrrPMBMozafari RidsOgcRp RidsNrrDprPgcb RidsAcrsAcnwMailCenter RidsRgn2MailCenter Accession Number: ML062500055 OFFICE LPL2-2/PM LPL2-2/ LA SCVB/BC PGCB/BC LPL2-2/BC(A) | |||
NAME BMozafari RSola RDennig CJackson LRaghavan DATE 10/4/06 10/4/06 10/5/06 10/6/06 10/11/06 | |||
Mr. T. D. Walt H. B. Robinson Steam Electric Plant, Carolina Power & Light Company Unit No. 2 cc: | |||
David T. Conley Mr. C. T. Baucom Associate General Counsel II - Legal Supervisor, Licensing/Regulatory Programs Department H. B. Robinson Steam Electric Plant, Progress Energy Service Company, LLC Unit No. 2 Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602-1551 3581 West Entrance Road Hartsville, South Carolina 29550 Ms. Margaret A. Force Assistant Attorney General Ms. Beverly Hall, Section Chief State of North Carolina N.C. Department of Environment Post Office Box 629 and Natural Resources Raleigh, North Carolina 27602 Division of Radiation Protection 3825 Barrett Dr. | |||
U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27609-7721 Resident Inspectors Office H. B. Robinson Steam Electric Plant Mr. Robert P. Gruber 2112 Old Camden Road Executive Director Hartsville, South Carolina 29550 Public Staff - NCUC 4326 Mail Service Center Mr. Dan Stoddard Raleigh, North Carolina 27699-4326 Plant General Manager H. B. Robinson Steam Electric Plant, Mr. Henry H. Porter, Assistant Director Unit No. 2 South Carolina Department of Health Carolina Power & Light Company Bureau of Land & Waste Management 3581 West Entrance Road 2600 Bull Street Hartsville, South Carolina 29550 Columbia, South Carolina 29201 Mr. William G. Noll Mr. Chris L. Burton Director of Site Operations Manager H. B. Robinson Steam Electric Plant, Performance Evaluation and Unit No. 2 Regulatory Affairs PEB 7 Carolina Power & Light Company Progress Energy 3581 West Entrance Road Post Office Box 1551 Hartsville, South Carolina 29550 Raleigh, North Carolina 27602-1551 Public Service Commission Mr. John H. ONeill, Jr. | |||
State of South Carolina Shaw, Pittman, Potts, & Trowbridge Post Office Drawer 11649 2300 N Street NW. | |||
Columbia, South Carolina 29211 Washington, DC 20037-1128 J. F. Lucas Mr. J. W. Moyer, Vice President Manager - Support Services - Nuclear Carolina Power & Light Company H. B. Robinson Steam Electric Plant, H. B. Robinson Steam Electric Plant Unit No. 2 Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road 3581 West Entrance Road Hartsville, South Carolina 29550-0790 Hartsville, South Carolina 29550}} | |||
Revision as of 15:23, 23 November 2019
| ML062500055 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/11/2006 |
| From: | Mozafari B NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Walt T Carolina Power & Light Co |
| Mozafari B, NRR/ADRO/DORL, 415-2020 | |
| References | |
| GL-03-001, TAC MB9848 | |
| Download: ML062500055 (4) | |
Text
October 11, 2006 Mr. Thomas D. Walt, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 - NRC RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NO. MB9848)
Dear Mr. Walt:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response to Generic Letter (GL) 2003-01, Control Room Habitability, in a letter dated December 08, 2003 (Agencywide Document and Access Management System (ADAMS) Accession No.
ML033440212). This letter provides a status of your response and describes any additional information that may be necessary to consider your response to GL 2003-01 complete.
GL 2003-01 requested that you confirm that your control room meet its design bases (e.g., General Design Criteria (GDC) 1, 3, 4, 5, and 19, draft GDCs, 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 (Item 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 (Item 1.b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability (CRH), and plans to retire them (Item 2).
Your response referenced an April 10, 2003, letter (ADAMS Accession No. ML031050027) in which 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 pressurized H. B. Robinson Steam Electric Plant, Unit No. 2 control room. You determined that the maximum tested value for inleakage into the control room envelope (CRE) was 141 (+/- 5) cubic feet per minute (cfm) for Mode 1; 64 (+/- 15) cfm for Mode 2; 30 (+/- 14) cfm for Mode 3. These values were all less than the values of 160 cfm loss-of-coolant accident (LOCA)-Mode 1) and 290 cfm (non-LOCA-Mode 1); 160 cfm (Mode 2);
and 90 cfm (Mode 3) assumed in the design basis radiological dose analyses for CRH.
In your April 10, 2003, letter, you also reported that the maximum tested inleakage value for the hazardous chemical recirculation mode was 93 (+/-3) cfm, which is less than the total intake flow of 570 cfm assumed in your design basis hazardous chemical analysis. You indicated that reactor control capability is maintained from either the control room or the alternate shutdown location in the event of smoke.
T. D. Walt The GL further requested that you assess your technical specifications to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability, and in light of the demonstrated inadequacy of a delta () P (pressure change) measurement to alone provide such verification (Item 1.c).
As permitted by the GL, you provided a schedule for revising the surveillance requirement in the technical specification (TS) to reference an acceptable surveillance methodology. In your December 9, 2003, response you indicated that you will submit a license amendment request to revise your TS utilizing Technical Specification Task Force (TSTF)Traveler TSTF-448 within 6 months of the approval of TSTF-448 by the NRC.
The information you provided also supported the fact that all compensatory measures needed to demonstrate CRH have been retired following the July 11, 2006, NRC approval of your LOCA Alternate Source Term submittal (ADAMS Accession No. ML061910159).
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability.
The information you provided also supported the conclusion that your are committed to meet the intent of the GDC regarding control room habitability which is documented in your Safety Evaluation.
Your commitment to submit a license amendment request based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submittal of the license amendment request and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Brenda Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261 cc: See next page
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability.
The information you provided also supported the conclusion that your are committed to meet the intent of the GDC regarding control room habitability which is documented in your Safety Evaluation.
Your commitment to submit a license amendment request based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submittal of the license amendment request and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Brenda Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261 cc: See next page DISTRIBUTION:
PUBLIC LPL2-2 r/f J. Robinson, NRR RidsNrrDorlLpl2-2 RidsNrrLACSola RidsNrrDssScvb RidsNrrPMBMozafari RidsOgcRp RidsNrrDprPgcb RidsAcrsAcnwMailCenter RidsRgn2MailCenter Accession Number: ML062500055 OFFICE LPL2-2/PM LPL2-2/ LA SCVB/BC PGCB/BC LPL2-2/BC(A)
NAME BMozafari RSola RDennig CJackson LRaghavan DATE 10/4/06 10/4/06 10/5/06 10/6/06 10/11/06
Mr. T. D. Walt H. B. Robinson Steam Electric Plant, Carolina Power & Light Company Unit No. 2 cc:
David T. Conley Mr. C. T. Baucom Associate General Counsel II - Legal Supervisor, Licensing/Regulatory Programs Department H. B. Robinson Steam Electric Plant, Progress Energy Service Company, LLC Unit No. 2 Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602-1551 3581 West Entrance Road Hartsville, South Carolina 29550 Ms. Margaret A. Force Assistant Attorney General Ms. Beverly Hall, Section Chief State of North Carolina N.C. Department of Environment Post Office Box 629 and Natural Resources Raleigh, North Carolina 27602 Division of Radiation Protection 3825 Barrett Dr.
U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27609-7721 Resident Inspectors Office H. B. Robinson Steam Electric Plant Mr. Robert P. Gruber 2112 Old Camden Road Executive Director Hartsville, South Carolina 29550 Public Staff - NCUC 4326 Mail Service Center Mr. Dan Stoddard Raleigh, North Carolina 27699-4326 Plant General Manager H. B. Robinson Steam Electric Plant, Mr. Henry H. Porter, Assistant Director Unit No. 2 South Carolina Department of Health Carolina Power & Light Company Bureau of Land & Waste Management 3581 West Entrance Road 2600 Bull Street Hartsville, South Carolina 29550 Columbia, South Carolina 29201 Mr. William G. Noll Mr. Chris L. Burton Director of Site Operations Manager H. B. Robinson Steam Electric Plant, Performance Evaluation and Unit No. 2 Regulatory Affairs PEB 7 Carolina Power & Light Company Progress Energy 3581 West Entrance Road Post Office Box 1551 Hartsville, South Carolina 29550 Raleigh, North Carolina 27602-1551 Public Service Commission Mr. John H. ONeill, Jr.
State of South Carolina Shaw, Pittman, Potts, & Trowbridge Post Office Drawer 11649 2300 N Street NW.
Columbia, South Carolina 29211 Washington, DC 20037-1128 J. F. Lucas Mr. J. W. Moyer, Vice President Manager - Support Services - Nuclear Carolina Power & Light Company H. B. Robinson Steam Electric Plant, H. B. Robinson Steam Electric Plant Unit No. 2 Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road 3581 West Entrance Road Hartsville, South Carolina 29550-0790 Hartsville, South Carolina 29550