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| number = ML062720099 | | number = ML062720099 | ||
| issue date = 10/10/2006 | | issue date = 10/10/2006 | ||
| title = NRC Receipt of Beaver Valley Power Station, Unit Nos. 1 and 2, (BVPS-1 and 2) Response to Generic Letter (GL) 2003-01 Control Room Habitability | | title = NRC Receipt of Beaver Valley Power Station, Unit Nos. 1 and 2, (BVPS-1 and 2) Response to Generic Letter (GL) 2003-01 Control Room Habitability | ||
| author name = Colburn T | | author name = Colburn T | ||
| author affiliation = NRC/NRR/ADRO/DORL/LPLI-1 | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-1 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:October 10, | {{#Wiki_filter:October 10, 2006 Mr. James H. Lash Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 | ||
==SUBJECT:== | ==SUBJECT:== | ||
NRC RECEIPT OF BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2,(BVPS-1 AND 2) RESPONSE TO GENERIC LETTER (GL) 2003-01 | NRC RECEIPT OF BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2, (BVPS-1 AND 2) RESPONSE TO GENERIC LETTER (GL) 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9772 AND MB9773) | ||
==Dear Mr. Lash:== | ==Dear Mr. Lash:== | ||
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to GL 2003-01 | The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to GL 2003-01 Control Room Habitability, dated December 5, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML033430285), and March 22, 2004 (ADAMS Accession No. ML040850103). 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 meets your design bases (e.g., | |||
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, 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 Item 1a); (2) determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments (GL 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 Item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (GL Item 2). | |||
You reported the results of ASTM E741 tracer gas tests for the BVPS-1 and 2 Control Room. | |||
You determined that the tested value for inleakage into the Control Room Envelope (CRE), was 5.41 scfm, which was less than the value of 10 cfm assumed in the design-basis radiological analyses for Control Room Habitability (CRH). | |||
You indicated that unfiltered inleakage is not specifically incorporated into the hazardous chemical assessment because toxic gases are not considered to be a threat based on hazard screening performed on chemicals stored onsite or transported near the BVPS. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke. | |||
P.O. Box 298 Shippingport, PA | J. Lash The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability. | ||
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 control room habitability, 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, in your December 5, 2003, response, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your March 22, 2004, letter, you revised your commitment date for submitting the revised surveillance TS from within 180 days of the submittal date of this response to Generic Letter 2003-01 to within 180 days of NRC approval of TSTF-448. | |||
Your commitment to submit a LAR 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 submission of the LAR and interact with you as necessary during the amendment process. | |||
If you have any questions regarding this correspondence, please contact me. | |||
Sincerely, | |||
/RA/ | |||
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: See next page | |||
J. Lash The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability. | |||
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 control room habitability, 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, in your December 5, 2003, response, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your March 22, 2004, letter, you revised your commitment date for submitting the revised surveillance TS from within 180 days of the submittal date of this response to Generic Letter 2003-01 to within 180 days of NRC approval of TSTF-448. | |||
Your commitment to submit a LAR 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 submission of the LAR and interact with you as necessary during the amendment process. | |||
If you have any questions regarding this correspondence, please contact me. | |||
Sincerely, | |||
/RA/ | |||
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: See next page DISTRIBUTION: | |||
PUBLIC Lpl1-1 R/F RidsNrrDorlLpl1-1 RidsNrrPMTColburn RidsNrrLASLittle JRobinson RidsNrrDssScvb RidsNrrDprPgcb ACCESSION NO. ML062720099 OFFICE LPLI-1/PM LPLI-1/LA SCVB/BC PGCB/BC LPLI-1/BC NAME TColburn SLittle RDennig CJackson RLaufer DATE 10/05/06 10/05/06 10/08/06 10/10/06 10/10/06 OFFICIAL RECORD COPY | |||
Beaver Valley Power Station, Unit Nos. 1 and 2 cc: | |||
Gary R. Leidich James H. Lash President and Chief Nuclear Officer Site Vice President FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-SEB1 Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Joseph J. Hagan Senior Vice President of Operations Lew W. Myers and Chief Operating Officer Executive Vice President, Special Projects FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-SGRP Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Danny L. Pace Senior Vice President, Fleet Engineering Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-A Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Jeannie M. Rinckel Vice President, Fleet Oversight Commissioner James R. Lewis FirstEnergy Nuclear Operating Company West Virginia Division of Labor Mail Stop A-GO-14 749-B, Building No. 6 76 South Main Street Capitol Complex Akron, OH 44308 Charleston, WV 25305 David W. Jenkins, Attorney Director, Utilities Department FirstEnergy Corporation Public Utilities Commission Mail Stop A-GO-18 180 East Broad Street 76 South Main Street Columbus, OH 43266-0573 Akron, OH 44308 Director, Pennsylvania Emergency Manager, Fleet Licensing Management Agency FirstEnergy Nuclear Operating Company 2605 Interstate Dr. | |||
Mail Stop A-GHE-107 Harrisburg, PA 17110-9364 395 Ghent Road Akron, OH 44333 Ohio EPA-DERR ATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 | |||
Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc: | |||
Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077}} | |||
Latest revision as of 00:19, 23 March 2020
| ML062720099 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/10/2006 |
| From: | Colburn T NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Lash J FirstEnergy Nuclear Operating Co |
| Colburn T, NRR/DORL, 415-1402 | |
| References | |
| GL-03-001, TAC MB9772, TAC MB9773 | |
| Download: ML062720099 (5) | |
Text
October 10, 2006 Mr. James H. Lash Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
NRC RECEIPT OF BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2, (BVPS-1 AND 2) RESPONSE TO GENERIC LETTER (GL) 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9772 AND MB9773)
Dear Mr. Lash:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to GL 2003-01 Control Room Habitability, dated December 5, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML033430285), and March 22, 2004 (ADAMS Accession No. ML040850103). 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 meets your design bases (e.g.,
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, 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 Item 1a); (2) determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments (GL 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 Item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (GL Item 2).
You reported the results of ASTM E741 tracer gas tests for the BVPS-1 and 2 Control Room.
You determined that the tested value for inleakage into the Control Room Envelope (CRE), was 5.41 scfm, which was less than the value of 10 cfm assumed in the design-basis radiological analyses for Control Room Habitability (CRH).
You indicated that unfiltered inleakage is not specifically incorporated into the hazardous chemical assessment because toxic gases are not considered to be a threat based on hazard screening performed on chemicals stored onsite or transported near the BVPS. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
J. Lash The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability.
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 control room habitability, 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, in your December 5, 2003, response, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your March 22, 2004, letter, you revised your commitment date for submitting the revised surveillance TS from within 180 days of the submittal date of this response to Generic Letter 2003-01 to within 180 days of NRC approval of TSTF-448.
Your commitment to submit a LAR 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 submission of the LAR and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: See next page
J. Lash The information you provided also supported the fact that there are no compensatory measures in place to demonstrate control room habitability.
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 control room habitability, 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, in your December 5, 2003, response, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your March 22, 2004, letter, you revised your commitment date for submitting the revised surveillance TS from within 180 days of the submittal date of this response to Generic Letter 2003-01 to within 180 days of NRC approval of TSTF-448.
Your commitment to submit a LAR 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 submission of the LAR and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: See next page DISTRIBUTION:
PUBLIC Lpl1-1 R/F RidsNrrDorlLpl1-1 RidsNrrPMTColburn RidsNrrLASLittle JRobinson RidsNrrDssScvb RidsNrrDprPgcb ACCESSION NO. ML062720099 OFFICE LPLI-1/PM LPLI-1/LA SCVB/BC PGCB/BC LPLI-1/BC NAME TColburn SLittle RDennig CJackson RLaufer DATE 10/05/06 10/05/06 10/08/06 10/10/06 10/10/06 OFFICIAL RECORD COPY
Beaver Valley Power Station, Unit Nos. 1 and 2 cc:
Gary R. Leidich James H. Lash President and Chief Nuclear Officer Site Vice President FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-SEB1 Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Joseph J. Hagan Senior Vice President of Operations Lew W. Myers and Chief Operating Officer Executive Vice President, Special Projects FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-SGRP Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Danny L. Pace Senior Vice President, Fleet Engineering Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-A Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Jeannie M. Rinckel Vice President, Fleet Oversight Commissioner James R. Lewis FirstEnergy Nuclear Operating Company West Virginia Division of Labor Mail Stop A-GO-14 749-B, Building No. 6 76 South Main Street Capitol Complex Akron, OH 44308 Charleston, WV 25305 David W. Jenkins, Attorney Director, Utilities Department FirstEnergy Corporation Public Utilities Commission Mail Stop A-GO-18 180 East Broad Street 76 South Main Street Columbus, OH 43266-0573 Akron, OH 44308 Director, Pennsylvania Emergency Manager, Fleet Licensing Management Agency FirstEnergy Nuclear Operating Company 2605 Interstate Dr.
Mail Stop A-GHE-107 Harrisburg, PA 17110-9364 395 Ghent Road Akron, OH 44333 Ohio EPA-DERR ATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149
Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:
Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077