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| =Text= | | =Text= |
| {{#Wiki_filter:October 13, 2006Mr. H. L. Sumner, Jr. Vice President - Farley Project Southern Nuclear Operating Company, Inc. | | {{#Wiki_filter:October 13, 2006 Mr. H. L. Sumner, Jr. |
| Post Office Box 1295 Birmingham, AL 35201-1295 | | Vice President - Farley Project Southern Nuclear Operating Company, Inc. |
| | Post Office Box 1295 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 REQUESTFOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2006-03, "POTENTIALLY NONCONFORMING HEMYC AND MT FIRE BARRIER CONFIGURATIONS" (TAC NOS. MD1578 AND MD1579) | | JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2006-03, POTENTIALLY NONCONFORMING HEMYC AND MT FIRE BARRIER CONFIGURATIONS (TAC NOS. MD1578 AND MD1579) |
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| ==Dear Mr. Sumner:== | | ==Dear Mr. Sumner:== |
| By letter dated June 9, 2006, Southern Nuclear Company (SNC) provided a response toNuclear Regulatory Commission (NRC) Generic Letter 2006-03, "Potentially Nonconforming Hemyc and MT Fire Barrier Configurations," for the Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (FNP). The NRC staff has reviewed that response and has identified a need for additional information as stated in the enclosure. This issue was discussed with the SNC staff for the FNP on July 27, 2006. We request that a response to these issues be provided within 45 days of the date of this letter. Sincerely,/RA/Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-348 and 50-364 | | |
| | By letter dated June 9, 2006, Southern Nuclear Company (SNC) provided a response to Nuclear Regulatory Commission (NRC) Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations, for the Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (FNP). The NRC staff has reviewed that response and has identified a need for additional information as stated in the enclosure. This issue was discussed with the SNC staff for the FNP on July 27, 2006. We request that a response to these issues be provided within 45 days of the date of this letter. |
| | Sincerely, |
| | /RA/ |
| | Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next page October 13, 2006Mr. H. L. Sumner, Jr. | | |
| | Request for Additional Information cc w/encl: See next page |
| | |
| | October 13, 2006 Mr. H. L. Sumner, Jr. |
| Vice President - Farley Project Southern Nuclear Operating Company, Inc. | | Vice President - Farley Project Southern Nuclear Operating Company, Inc. |
| Post Office Box 1295 Birmingham, AL 35201-1295 | | Post Office Box 1295 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 REQUESTFOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2006-03, "POTENTIALLY NONCONFORMING HEMYC AND MT FIRE BARRIER CONFIGURATIONS" (TAC NOS. MD1578 AND MD1579) | | JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2006-03, POTENTIALLY NONCONFORMING HEMYC AND MT FIRE BARRIER CONFIGURATIONS (TAC NOS. MD1578 AND MD1579) |
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| ==Dear Mr. Sumner:== | | ==Dear Mr. Sumner:== |
| By letter dated June 9, 2006, Southern Nuclear Company (SNC) provided a response toNuclear Regulatory Commission (NRC) Generic Letter 2006-03, "Potentially Nonconforming Hemyc and MT Fire Barrier Configurations," for the Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (FNP). The NRC staff has reviewed that response and has identified a need for additional information as stated in the enclosure. This issue was discussed with the SNC staff for the FNP on July 27, 2006. We request that a response to these issues be provided within 45 days of the date of this letter. Sincerely,/RA/Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-348 and 50-364 | | |
| | By letter dated June 9, 2006, Southern Nuclear Company (SNC) provided a response to Nuclear Regulatory Commission (NRC) Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations, for the Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (FNP). The NRC staff has reviewed that response and has identified a need for additional information as stated in the enclosure. This issue was discussed with the SNC staff for the FNP on July 27, 2006. We request that a response to these issues be provided within 45 days of the date of this letter. |
| | Sincerely, |
| | /RA/ |
| | Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next page DISTRIBUTION: | | |
| PublicRidsAcrsAcnwMailCenter RidsNrrPMRJervey LPL2-1 R/FRidsNrrDorlLpl2-1(EMarinos)RidsNrrPMRMartin(hard copy)
| | Request for Additional Information cc w/encl: See next page DISTRIBUTION: |
| RidsOgcRpRidsRgn2MailCenter(SShaeffer)
| | Public RidsAcrsAcnwMailCenter RidsNrrPMRJervey LPL2-1 R/F RidsNrrDorlLpl2-1(EMarinos) RidsNrrPMRMartin(hard copy) |
| RidsNrrLARSola(hard copy)RidsNrrDraAfpbAccession No.: ML062780449OFFICENRR/LPL2-1/PMNRR/LPL2-1/LANRR/AFPB/BCNRR/LPL2-1/BCNAMERMartinRSolaSWeerakkodyEMarinos DATE10/11/0610/6/0609/07/0610/13/06OFFICIAL RECORD COPY EnclosureREQUEST FOR ADDITIONAL INFORMATIONGENERIC LETTER 2006-03POTENTIALLY NONCONFORMING HEYMC AND MT FIRE BARRIER CONFIGURATIONSJOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2FOR RENEWED FACILITY OPERATING LICENSE NO. NPF-2, DOCKET NO. 50-348AND RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364For the Farley Nuclear Plant (FNP), the Promat H board is described as a fire barrier thatseparates redundant trains within the same fire area (for example, cable tray enclosures). The response states that Promat H board is tested in accordance with Underwriter Laboratories document UL 263, American Society for Testing and Materials document ASTM E119, and the National Fire Protection Association document NFPA 251. Use of these tests and standards identifies fire testing for building members and assemblies, but does not specifically address 1 and 3-hour fire barrier systems protecting electrical raceways.This issue was discussed during a phone call with the FNP staff on July 27, 2006. Thefollowing are follow-up questions from that phone call to confirm the Nuclear Regulatory Commission staff's understanding of the FNP Promat configuration. 1.How was the Promat tested? Confirm that, per the phone call, the ASTM E119 timetemperature, full scale fire testing was used.2.What acceptance criteria were used? Confirm that, per the phone call, the 325 degreesFarenheit temperature criterion was used.3.How were installed configurations that were different from tested configurationsevaluated? Confirm that, per the phone call, the field installation deviations from the tested configurations were evaluated in accordance with the Generic Letter 86-10, Section 3.2.2 criteria. | | RidsOgcRp RidsRgn2MailCenter(SShaeffer) |
| | RidsNrrLARSola(hard copy) RidsNrrDraAfpb Accession No.: ML062780449 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/AFPB/BC NRR/LPL2-1/BC NAME RMartin RSola SWeerakkody EMarinos DATE 10/11/06 10/6/06 09/07/06 10/13/06 OFFICIAL RECORD COPY |
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| | REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 2006-03 POTENTIALLY NONCONFORMING HEYMC AND MT FIRE BARRIER CONFIGURATIONS JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 FOR RENEWED FACILITY OPERATING LICENSE NO. NPF-2, DOCKET NO. 50-348 AND RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 For the Farley Nuclear Plant (FNP), the Promat H board is described as a fire barrier that separates redundant trains within the same fire area (for example, cable tray enclosures). The response states that Promat H board is tested in accordance with Underwriter Laboratories document UL 263, American Society for Testing and Materials document ASTM E119, and the National Fire Protection Association document NFPA 251. Use of these tests and standards identifies fire testing for building members and assemblies, but does not specifically address 1 and 3-hour fire barrier systems protecting electrical raceways. |
| | This issue was discussed during a phone call with the FNP staff on July 27, 2006. The following are follow-up questions from that phone call to confirm the Nuclear Regulatory Commission staffs understanding of the FNP Promat configuration. |
| | : 1. How was the Promat tested? Confirm that, per the phone call, the ASTM E119 time temperature, full scale fire testing was used. |
| | : 2. What acceptance criteria were used? Confirm that, per the phone call, the 325 degrees Farenheit temperature criterion was used. |
| | : 3. How were installed configurations that were different from tested configurations evaluated? Confirm that, per the phone call, the field installation deviations from the tested configurations were evaluated in accordance with the Generic Letter 86-10, Section 3.2.2 criteria. |
| | Enclosure |
| | |
| Joseph M. Farley Nuclear Plant, Units 1 & 2 cc: | | Joseph M. Farley Nuclear Plant, Units 1 & 2 cc: |
| Mr. J. R. JohnsonGeneral Manager Southern Nuclear Operating Company, Inc. | | Mr. J. R. Johnson General Manager Southern Nuclear Operating Company, Inc. |
| P.O. Box 470 Ashford, AL 36312Mr. B. D. McKinney, Licensing ManagerSouthern Nuclear Operating Company, Inc. | | P.O. Box 470 Ashford, AL 36312 Mr. B. D. McKinney, Licensing Manager Southern Nuclear Operating Company, Inc. |
| P.O. Box 1295 Birmingham, AL 35201-1295Mr. M. Stanford BlantonBalch and Bingham Law Firm P.O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201Mr. J. GasserExecutive Vice President Southern Nuclear Operating Company, Inc. | | P.O. Box 1295 Birmingham, AL 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm P.O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 Mr. J. Gasser Executive Vice President Southern Nuclear Operating Company, Inc. |
| P.O. Box 1295 Birmingham, AL 35201State Health OfficerAlabama Department of Public Health 434 Monroe St. | | P.O. Box 1295 Birmingham, AL 35201 State Health Officer Alabama Department of Public Health 434 Monroe St. |
| Montgomery, AL 36130-1701Chairman Houston County Commission P.O. Box 6406 Dothan, AL 36302Resident InspectorU.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319}} | | Montgomery, AL 36130-1701 Chairman Houston County Commission P.O. Box 6406 Dothan, AL 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319}} |
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MONTHYEARML0627804492006-10-13013 October 2006 Request for Additional Information for Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations Project stage: RAI ML0712800452007-05-14014 May 2007 Receipt of Response to Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations (TAC Nos. MD1578 and MD1579) Project stage: Other 2006-10-13
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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-01-30
[Table view] |
Text
October 13, 2006 Mr. H. L. Sumner, Jr.
Vice President - Farley Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2006-03, POTENTIALLY NONCONFORMING HEMYC AND MT FIRE BARRIER CONFIGURATIONS (TAC NOS. MD1578 AND MD1579)
Dear Mr. Sumner:
By letter dated June 9, 2006, Southern Nuclear Company (SNC) provided a response to Nuclear Regulatory Commission (NRC) Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations, for the Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (FNP). The NRC staff has reviewed that response and has identified a need for additional information as stated in the enclosure. This issue was discussed with the SNC staff for the FNP on July 27, 2006. We request that a response to these issues be provided within 45 days of the date of this letter.
Sincerely,
/RA/
Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
Request for Additional Information cc w/encl: See next page
October 13, 2006 Mr. H. L. Sumner, Jr.
Vice President - Farley Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2006-03, POTENTIALLY NONCONFORMING HEMYC AND MT FIRE BARRIER CONFIGURATIONS (TAC NOS. MD1578 AND MD1579)
Dear Mr. Sumner:
By letter dated June 9, 2006, Southern Nuclear Company (SNC) provided a response to Nuclear Regulatory Commission (NRC) Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations, for the Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (FNP). The NRC staff has reviewed that response and has identified a need for additional information as stated in the enclosure. This issue was discussed with the SNC staff for the FNP on July 27, 2006. We request that a response to these issues be provided within 45 days of the date of this letter.
Sincerely,
/RA/
Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Public RidsAcrsAcnwMailCenter RidsNrrPMRJervey LPL2-1 R/F RidsNrrDorlLpl2-1(EMarinos) RidsNrrPMRMartin(hard copy)
RidsOgcRp RidsRgn2MailCenter(SShaeffer)
RidsNrrLARSola(hard copy) RidsNrrDraAfpb Accession No.: ML062780449 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/AFPB/BC NRR/LPL2-1/BC NAME RMartin RSola SWeerakkody EMarinos DATE 10/11/06 10/6/06 09/07/06 10/13/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 2006-03 POTENTIALLY NONCONFORMING HEYMC AND MT FIRE BARRIER CONFIGURATIONS JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 FOR RENEWED FACILITY OPERATING LICENSE NO. NPF-2, DOCKET NO. 50-348 AND RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 For the Farley Nuclear Plant (FNP), the Promat H board is described as a fire barrier that separates redundant trains within the same fire area (for example, cable tray enclosures). The response states that Promat H board is tested in accordance with Underwriter Laboratories document UL 263, American Society for Testing and Materials document ASTM E119, and the National Fire Protection Association document NFPA 251. Use of these tests and standards identifies fire testing for building members and assemblies, but does not specifically address 1 and 3-hour fire barrier systems protecting electrical raceways.
This issue was discussed during a phone call with the FNP staff on July 27, 2006. The following are follow-up questions from that phone call to confirm the Nuclear Regulatory Commission staffs understanding of the FNP Promat configuration.
- 1. How was the Promat tested? Confirm that, per the phone call, the ASTM E119 time temperature, full scale fire testing was used.
- 2. What acceptance criteria were used? Confirm that, per the phone call, the 325 degrees Farenheit temperature criterion was used.
- 3. How were installed configurations that were different from tested configurations evaluated? Confirm that, per the phone call, the field installation deviations from the tested configurations were evaluated in accordance with the Generic Letter 86-10, Section 3.2.2 criteria.
Enclosure
Joseph M. Farley Nuclear Plant, Units 1 & 2 cc:
Mr. J. R. Johnson General Manager Southern Nuclear Operating Company, Inc.
P.O. Box 470 Ashford, AL 36312 Mr. B. D. McKinney, Licensing Manager Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm P.O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 Mr. J. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201 State Health Officer Alabama Department of Public Health 434 Monroe St.
Montgomery, AL 36130-1701 Chairman Houston County Commission P.O. Box 6406 Dothan, AL 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319