|
|
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:August 30, 2007Mr. J. Randy Johnson Vice President - Farley Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319 | | {{#Wiki_filter:August 30, 2007 Mr. J. Randy Johnson Vice President - Farley Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - RESPONSE TOGENERIC LETTER 2006-02 "GRID RELIABILITY AND THE IMPACT ON PLANT RISK AND THE OPERABILITY OF OFFSITE POWER" (TAC NO. MD0979 AND MD0980) | | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 2006-02 "GRID RELIABILITY AND THE IMPACT ON PLANT RISK AND THE OPERABILITY OF OFFSITE POWER" (TAC NO. MD0979 AND MD0980) |
|
| |
|
| ==Dear Mr. Johnson:== | | ==Dear Mr. Johnson:== |
|
| |
|
| On February 1, 2006, the U.S. Nuclear Regulatory Commission (NRC) issued GL 2006-02,"Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power" (Agencywide Documents Access and Management System (ADAMS) Accession No. | | On February 1, 2006, the U.S. Nuclear Regulatory Commission (NRC) issued GL 2006-02, "Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power" (Agencywide Documents Access and Management System (ADAMS) Accession No. |
| ML060180352) to all holders of operating licenses for nuclear power reactors except those who have permanently ceased operation and have certified that fuel has been removed from the reactor vessel.GL 2006-02 notified licensees of the NRC staff's need for information in four areas as follows: | | ML060180352) to all holders of operating licenses for nuclear power reactors except those who have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. |
| (1) use of protocols between the nuclear power plant (NPP) and the transmission systemoperator (TSO), independent system operator (ISO), or reliability coordinator/authority (RC/RA) and the use of transmission load flow analysis tools (analysis tools) by TSOs to assist NPPs in monitoring grid conditions to determine the operability of offsite power systems under plant technical specifications (TSs). (The TSO, ISO, or RA/RC is responsible for preserving the reliability of the local transmission system. In this GL the term TSO is used to denote these entities);(2) use of NPP/TSO protocols and analysis tools by TSOs to assist NPPs in monitoring gridconditions for consideration in maintenance risk assessments;(3) offsite power restoration procedures in accordance with Section 2 of NRC RegulatoryGuide (RG) 1.155, "Station Blackout;" and(4) losses of offsite power caused by grid failures at a frequency equal to or greater thanonce in 20 site-years in accordance with RG 1.155.Subsequent to the GL, the NRC issued a Request For Additional Information (RAI), (ADAMSAccession No. ML063380308) regarding the resolution of GL 2006-02 to 63 of 65 holders of operating licenses for nuclear power reactors. The RAI requested that licensees respond to questions in the following areas: | | GL 2006-02 notified licensees of the NRC staff's need for information in four areas as follows: |
| J. R. Johnson-2-(1) Switchyard Minimum Voltage;(2) Loss of Real-Time Contingency Analysis (RTCA) Capability; (3) Verification of RTCA Predicted Post-Trip Voltage; (4) Identification of Applicable Single Contingencies; (5) Seasonal Variation in Grid Stress (reliability and Loss-of-offsite power (LOOP)Probability;(6) Interface With Transmission System Operator During Extended Plant Maintenance.By letter(s) dated March 31, 2006 (ADAMS Accession No. ML060900618) and January 30,2007 (ADAMS Accession No. ML070300848) you responded to the information request of GL 2006-02 and the subsequent RAI. Based on the information you provided, the staff has concluded that your responses are adequate and that no further action is requested of you at this time.If you have any questions, please contact me at 301-415-1438.Sincerely,EMarinos for /RA/ Karen Cotton, Project Manager Plant Licensing Branch II-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-348 and 50-364 cc: See next page
| | (1) use of protocols between the nuclear power plant (NPP) and the transmission system operator (TSO), independent system operator (ISO), or reliability coordinator/authority (RC/RA) and the use of transmission load flow analysis tools (analysis tools) by TSOs to assist NPPs in monitoring grid conditions to determine the operability of offsite power systems under plant technical specifications (TSs). (The TSO, ISO, or RA/RC is responsible for preserving the reliability of the local transmission system. In this GL the term TSO is used to denote these entities); |
| | (2) use of NPP/TSO protocols and analysis tools by TSOs to assist NPPs in monitoring grid conditions for consideration in maintenance risk assessments; (3) offsite power restoration procedures in accordance with Section 2 of NRC Regulatory Guide (RG) 1.155, "Station Blackout;" and (4) losses of offsite power caused by grid failures at a frequency equal to or greater than once in 20 site-years in accordance with RG 1.155. |
| | Subsequent to the GL, the NRC issued a Request For Additional Information (RAI), (ADAMS Accession No. ML063380308) regarding the resolution of GL 2006-02 to 63 of 65 holders of operating licenses for nuclear power reactors. The RAI requested that licensees respond to questions in the following areas: |
|
| |
|
| ML060900618) and January 30,2007 (ADAMS Accession No. ML070300848) you responded to the information request of GL 2006-02 and the subsequent RAI. Based on the information you provided, the staff has concluded that your responses are adequate and that no further action is requested of you at this time.If you have any questions, please contact me at 301-415-1438.Sincerely,EMarinos for /RA/ Karen Cotton, Project Manager Plant Licensing Branch II-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-348 and 50-364 cc: See next page DISTRIBUTION | | J. R. Johnson (1) Switchyard Minimum Voltage; (2) Loss of Real-Time Contingency Analysis (RTCA) Capability; (3) Verification of RTCA Predicted Post-Trip Voltage; (4) Identification of Applicable Single Contingencies; (5) Seasonal Variation in Grid Stress (reliability and Loss-of-offsite power (LOOP) |
| :PublicRidsAcrsAcnwMailCenter RidsRgn2MailCenter LPL2-1 R/FRidsNrrDorlDpr RidsNrrDorlLpl2-1(EMarinos)RidsNrrPMRMartin (hard copy)
| | Probability; (6) Interface With Transmission System Operator During Extended Plant Maintenance. |
| RidsNrrLARSola (hard copy)RidsNrrPMKCotton (hard copy)ADAMS Accession No. ML072320004OFFICENRR/LPL2-1/PMNRR/LPL2-2/LAEEEB/BCNRR/LPL2-1/BCNAMEKCotton:ncRSolaGWilsonEMarinos DATE 8/24/07 8/22/07 8/28/07 8/30/07 Joseph M. Farley Nuclear Plant, Units 1 & 2 cc: | | By letter(s) dated March 31, 2006 (ADAMS Accession No. ML060900618) and January 30,2007 (ADAMS Accession No. ML070300848) you responded to the information request of GL 2006-02 and the subsequent RAI. Based on the information you provided, the staff has concluded that your responses are adequate and that no further action is requested of you at this time. |
| Mr. B. D. McKinney, Licensing ManagerSouthern Nuclear Operating Company, Inc. | | If you have any questions, please contact me at 301-415-1438. |
| 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. | | Sincerely, EMarinos for /RA/ |
| P.O. Box 1295 Birmingham, AL 35201State Health OfficerAlabama Department of Public Health 434 Monroe St. | | Karen Cotton, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: See next page |
| 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 36319William D. OldfieldSAER Supervisor Southern Nuclear Operating Company, Inc. | | |
| P.O. Box 470 Ashford, AL 36312}} | | ML060900618) and January 30,2007 (ADAMS Accession No. ML070300848) you responded to the information request of GL 2006-02 and the subsequent RAI. Based on the information you provided, the staff has concluded that your responses are adequate and that no further action is requested of you at this time. |
| | If you have any questions, please contact me at 301-415-1438. |
| | Sincerely, EMarinos for /RA/ |
| | Karen Cotton, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: See next page DISTRIBUTION: |
| | Public RidsAcrsAcnwMailCenter RidsRgn2MailCenter LPL2-1 R/F RidsNrrDorlDpr RidsNrrDorlLpl2-1(EMarinos) RidsNrrPMRMartin (hard copy) |
| | RidsNrrLARSola (hard copy) RidsNrrPMKCotton (hard copy) |
| | ADAMS Accession No. ML072320004 OFFICE NRR/LPL2-1/PM NRR/LPL2-2/LA EEEB/BC NRR/LPL2-1/BC NAME KCotton:nc RSola GWilson EMarinos DATE 8/24/07 8/22/07 8/28/07 8/30/07 |
| | |
| | Joseph M. Farley Nuclear Plant, Units 1 & 2 cc: |
| | 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 William D. Oldfield SAER Supervisor Southern Nuclear Operating Company, Inc. |
| | P.O. Box 470 Ashford, AL 36312}} |
|
---|
Category:Letter
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 NL-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 2024-09-05
[Table view] |
Text
August 30, 2007 Mr. J. Randy Johnson Vice President - Farley Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 2006-02 "GRID RELIABILITY AND THE IMPACT ON PLANT RISK AND THE OPERABILITY OF OFFSITE POWER" (TAC NO. MD0979 AND MD0980)
Dear Mr. Johnson:
On February 1, 2006, the U.S. Nuclear Regulatory Commission (NRC) issued GL 2006-02, "Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power" (Agencywide Documents Access and Management System (ADAMS) Accession No.
ML060180352) to all holders of operating licenses for nuclear power reactors except those who have permanently ceased operation and have certified that fuel has been removed from the reactor vessel.
GL 2006-02 notified licensees of the NRC staff's need for information in four areas as follows:
(1) use of protocols between the nuclear power plant (NPP) and the transmission system operator (TSO), independent system operator (ISO), or reliability coordinator/authority (RC/RA) and the use of transmission load flow analysis tools (analysis tools) by TSOs to assist NPPs in monitoring grid conditions to determine the operability of offsite power systems under plant technical specifications (TSs). (The TSO, ISO, or RA/RC is responsible for preserving the reliability of the local transmission system. In this GL the term TSO is used to denote these entities);
(2) use of NPP/TSO protocols and analysis tools by TSOs to assist NPPs in monitoring grid conditions for consideration in maintenance risk assessments; (3) offsite power restoration procedures in accordance with Section 2 of NRC Regulatory Guide (RG) 1.155, "Station Blackout;" and (4) losses of offsite power caused by grid failures at a frequency equal to or greater than once in 20 site-years in accordance with RG 1.155.
Subsequent to the GL, the NRC issued a Request For Additional Information (RAI), (ADAMS Accession No. ML063380308) regarding the resolution of GL 2006-02 to 63 of 65 holders of operating licenses for nuclear power reactors. The RAI requested that licensees respond to questions in the following areas:
J. R. Johnson (1) Switchyard Minimum Voltage; (2) Loss of Real-Time Contingency Analysis (RTCA) Capability; (3) Verification of RTCA Predicted Post-Trip Voltage; (4) Identification of Applicable Single Contingencies; (5) Seasonal Variation in Grid Stress (reliability and Loss-of-offsite power (LOOP)
Probability; (6) Interface With Transmission System Operator During Extended Plant Maintenance.
By letter(s) dated March 31, 2006 (ADAMS Accession No. ML060900618) and January 30,2007 (ADAMS Accession No. ML070300848) you responded to the information request of GL 2006-02 and the subsequent RAI. Based on the information you provided, the staff has concluded that your responses are adequate and that no further action is requested of you at this time.
If you have any questions, please contact me at 301-415-1438.
Sincerely, EMarinos for /RA/
Karen Cotton, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: See next page
ML060900618) and January 30,2007 (ADAMS Accession No. ML070300848) you responded to the information request of GL 2006-02 and the subsequent RAI. Based on the information you provided, the staff has concluded that your responses are adequate and that no further action is requested of you at this time.
If you have any questions, please contact me at 301-415-1438.
Sincerely, EMarinos for /RA/
Karen Cotton, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: See next page DISTRIBUTION:
Public RidsAcrsAcnwMailCenter RidsRgn2MailCenter LPL2-1 R/F RidsNrrDorlDpr RidsNrrDorlLpl2-1(EMarinos) RidsNrrPMRMartin (hard copy)
RidsNrrLARSola (hard copy) RidsNrrPMKCotton (hard copy)
ADAMS Accession No. ML072320004 OFFICE NRR/LPL2-1/PM NRR/LPL2-2/LA EEEB/BC NRR/LPL2-1/BC NAME KCotton:nc RSola GWilson EMarinos DATE 8/24/07 8/22/07 8/28/07 8/30/07
Joseph M. Farley Nuclear Plant, Units 1 & 2 cc:
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 William D. Oldfield SAER Supervisor Southern Nuclear Operating Company, Inc.
P.O. Box 470 Ashford, AL 36312