|
|
(8 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML13031A626 | | | number = ML13031A626 |
| | issue date = 03/22/2013 | | | issue date = 03/22/2013 |
| | title = Joseph M. Farley Nuclear Plant, Units 1 and 2, Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Degraded Voltage Compensatory Measures (TAC Nos. MF0468 and MF0469) (NL-12-2142) | | | title = Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Degraded Voltage Compensatory Measures (TAC Nos. MF0468 and MF0469) (NL-12-2142) |
| | author name = Brown E A, Martin R E | | | author name = Brown E, Martin R |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Pierce C R | | | addressee name = Pierce C |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
| | license number = NPF-002, NPF-008 | | | license number = NPF-002, NPF-008 |
| | contact person = Brown E A | | | contact person = Brown E |
| | case reference number = NL-12-2142, TAC MF0468, TAC MF0469 | | | case reference number = NL-12-2142, TAC MF0468, TAC MF0469 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 5 | | | page count = 5 |
| | project = TAC:MF0468, TAC:MF0469 | | | project = TAC:MF0468, TAC:MF0469 |
| | stage = Other | | | stage = Acceptance Review |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 22, 2013 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. P. O. Box 1295, Bin -Birmingham, AL JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED ACTION CONCERNING DEGRADED VOLTAGE MEASURES (TAC NOS. MF0468 AND MF0469) Dear Mr. Pierce: By letter dated December 21, 2012, [Agencywide Document Access and Management System (ADAMS) No. ML 12356A470] the Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request for Joseph M. Farley Nuclear Plant, Units 1 and 2. The proposed amendment requests the addition of condition to the licensee related to the completion date for SNC to complete modifications to redesign the current degraded voltage scheme to eliminate the use of administrative controls. This application was made to support ongoing compensatory measures as a result of NRC staff inspection results in NRC Inspection Report 50-348(364)/2011-10 (ADAMS Accession No. ML 113530575). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 10 of the Code ofFederal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 22, 2013 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. |
| C. Pierce -2 Given the rare circumstances surrounding this submittal, the NRC staff has identified that in addition to the schedule request, SNC needs to submit, for NRC approval, those compensatory measures that the licensee intends to keep in place until completion of the proposed modifications at the end of the spring 2018 outage. Therefore, the NRC staff requests that SNC supplement the application to address the information requested in the enclosure by 60 days from the issuance of this letter. This will enable the NRC staff to begin its detailed technical review. Should the application be subsequently accepted for review, SNC will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and the associated timeframe in this letter were discussed with Mr. Doug McKinney of your staff on March 7,2013. If you have any questions, please contact me by phone at (301) 415-2315 or email at Eva. Brown@nrc.gov. Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Enclosure: As stated cc w/encl: Distribution via Listserv SUPPLEMENTAL INFORMATION NEEDED DEGRADED VOLTAGE SCHEDULE SOUTHERN NUCLEAR OPERATING JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND DOCKET NOS. 50-348 AND In the letter dated December 21, 2012 (the submittal [Agencywide Document Access and Management System (ADAMS) No. ML 12356A470], Southern Nuclear Operating Company (SNC, the licensee) indicates that an administrative limit has been established at a voltage level between the degraded grid voltage alarm allowable value (A V) and the automatic degraded grid voltage actuation upper AV. In the voltage range between the administrative limit and the degraded grid voltage actuation trip setpoint, a few engineered safety feature (ESF) components may not have automatic protection from inadequate voltage. The submittal further states that manual actions provide the primary means of protecting these few ESF components from a sustained, slightly low voltage condition and all components from unnecessary automatic disconnection from the preferred offsite power source. In the event of ESF actuation during degraded voltage conditions, provide details on: a) Equipment/components that may not have adequate voltage to operate; b) Equipment that may trip due to automatic protection such as overload relay actuations; c) Equipment that may trip but will require manual action to reset the protective device; and, d) Equipment that may degrade and may not be able to perform its required function. Explain the grid contingencies that were considered to ensure the switchyard voltages remain above the voltages required for safe shutdown of the plant. Provide technical basis including supporting data or analysis to show that the degraded voltage relay alarm settings would provide enough time to take operator actions in order to protect all Class 1 E equipment from the consequences of a sustained degraded voltage condition. The implementation schedule proposes Technical Specification amendment request after completion of Design. In order to expedite the schedule, explain why a concurrent amendment request is not considered to resolve any staff questions associated with proposed setpoints. Enclosure | | P. O. Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| -2 The submittal indicates that two outages are necessary to complete the modifications on each unit based on SNC's philosophy that limits electrical modifications to one electrical train per outage. In view of the high consequences of degraded voltage conditions concurrent with an ESF actuation (impact on redundant trains of ESF equipment). explain why the modification cannot be implemented in one outage with non-intrusive work performed online. APHB Identify the compensatory actions that will be relied upon to support the operation of equipment identified in Question 1 above. Include in the details of the consequences on accident analyses as a result of any delay equipment restoration by the proposed manual How long have the existing manual actions that respond to degraded voltage conditions been in place? If not since initial licensing. what were the circumstances that led to allocation of this function to operators rather than automatic systems? Discuss the alarms. annunciators. etc ... that are provided to notify personnel manual action(s) to respond to degraded voltage conditions is/are Discuss the alarms. annunciators, etc ... that are provided to notify personnel that the manual action(s) to respond to degraded voltage conditions is/are no longer required. Describe the administrative controls in place to ensure that. when the action(s) is/are no longer required, and the plant configuration is restored in the correct configuration for the plant status. a. Describe any manual actions in the normal and the emergency operating procedures in addition to those discussed in Q2 that are needed to prevent or mitigate degraded voltage conditions. If the Emergency Operating Procedures are involved. describe any verification and validation that was done to confirm that the existing manual actions are feasible. reliable. and effective. e.g .. initial start-up testing. V&V performed as part of the Detailed Control Room Design Review. post-mod or post-maintenance testing, or cyclical testing done as part of a Time-Critical Action Program. Regarding the V&V or testing discussed in Q7.b. above. did the validation include a representative sample of operators. and was it done with Technical Specification (TS) minimum staffing and nominal staffing? Discuss the time required to perform manual actions versus time available. Describe any controls or displays (including annunciators and alarms) needed to respond to degraded voltage conditions until implementation of the proposed modifications. | | |
| C. Pierce -2 Given the rare circumstances surrounding this submittal, the NRC staff has identified that in addition to the schedule request, SNC needs to submit, for NRC approval, those compensatory measures that the licensee intends to keep in place until completion of the proposed modifications at the end of the spring 2018 outage. Therefore, the NRC staff requests that SNC supplement the application to address the information requested in the enclosure by 60 days from the issuance of this letter. This will enable the NRC staff to begin its detailed technical review. Should the application be subsequently accepted for review, SNC will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and the associated timeframe in this Jetter were discussed with Mr. Doug McKinney of your staff on March 7, 2013. If you have any questions, please contact me by phone at (301) 415-2315 or email at Eva. Brown@nrc.gov. Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Enclosure: As stated cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLlI-1 Reading File RidsAcrsAcnw_MailCTR Resource RidsNrrDeEeeb Resource RidsNrrDraAhpb Resource RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsNrrLASFigueroa Resource RidsNrrPMFarley Resource RidsOgcRp Resource RidsRg2MailCenter Resource G. Lapinsky G. Matharu R. Martin ADAMS Accession No. ML13031A626 *Via email OFFICE DORULPLlI-1/PM DORULPLlI-1/LA DE/EEEB/BC(A) DRAlAPHB/BC DORULPLlI-1/BC NAME EBrown SFigueroa RMathew wi comments UShoop
| | ==SUBJECT:== |
| * RMartin for RPascareIIi DATE 3/7/13 2/6113 2/21/13 2/1113 3/22/13 OFFICIAL RECORD COPY
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION CONCERNING DEGRADED VOLTAGE COMPENSATORY MEASURES (TAC NOS. MF0468 AND MF0469) (NL-12-2142) |
| }} | | |
| | ==Dear Mr. Pierce:== |
| | |
| | By letter dated December 21, 2012, [Agencywide Document Access and Management System (ADAMS) No. ML12356A470] the Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request for Joseph M. Farley Nuclear Plant, Units 1 and 2. The proposed amendment requests the addition of condition to the licensee related to the completion date for SNC to complete modifications to redesign the current degraded voltage scheme to eliminate the use of administrative controls. This application was made to support ongoing compensatory measures as a result of NRC staff inspection results in NRC Inspection Report 50-348(364)/2011-10 (ADAMS Accession No. ML113530575). |
| | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. |
| | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| | The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment. |
| | |
| | C. Pierce -2 Given the rare circumstances surrounding this submittal, the NRC staff has identified that in addition to the schedule request, SNC needs to submit, for NRC approval, those compensatory measures that the licensee intends to keep in place until completion of the proposed modifications at the end of the spring 2018 outage. Therefore, the NRC staff requests that SNC supplement the application to address the information requested in the enclosure by 60 days from the issuance of this letter. This will enable the NRC staff to begin its detailed technical review. Should the application be subsequently accepted for review, SNC will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. |
| | The information requested and the associated timeframe in this letter were discussed with Mr. Doug McKinney of your staff on March 7,2013. |
| | If you have any questions, please contact me by phone at (301) 415-2315 or email at Eva. Brown@nrc.gov. |
| | Sincerely, IRA! |
| | Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv |
| | |
| | SUPPLEMENTAL INFORMATION NEEDED FOR DEGRADED VOLTAGE SCHEDULE REQUEST SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 In the letter dated December 21, 2012 (the submittal [Agencywide Document Access and Management System (ADAMS) No. ML12356A470], Southern Nuclear Operating Company (SNC, the licensee) indicates that an administrative limit has been established at a voltage level between the degraded grid voltage alarm allowable value (AV) and the automatic degraded grid voltage actuation upper AV. In the voltage range between the administrative limit and the degraded grid voltage actuation trip setpoint, a few engineered safety feature (ESF) components may not have automatic protection from inadequate voltage. |
| | The submittal further states that manual actions provide the primary means of protecting these few ESF components from a sustained, slightly low voltage condition and all components from unnecessary automatic disconnection from the preferred offsite power source. |
| | : 1. In the event of ESF actuation during degraded voltage conditions, provide details on: |
| | a) Equipment/components that may not have adequate voltage to operate; b) Equipment that may trip due to automatic protection such as overload relay actuations; c) Equipment that may trip but will require manual action to reset the protective device; and, d) Equipment that may degrade and may not be able to perform its required function. |
| | : 2. Explain the grid contingencies that were considered to ensure the switchyard voltages remain above the voltages required for safe shutdown of the plant. |
| | : 3. Provide technical basis including supporting data or analysis to show that the degraded voltage relay alarm settings would provide enough time to take operator actions in order to protect all Class 1E equipment from the consequences of a sustained degraded voltage condition. |
| | : 4. The implementation schedule proposes Technical Specification amendment request after completion of Design. In order to expedite the schedule, explain why a concurrent amendment request is not considered to resolve any staff questions associated with proposed setpoints. |
| | Enclosure |
| | |
| | -2 |
| | : 5. The submittal indicates that two outages are necessary to complete the modifications on each unit based on SNC's philosophy that limits electrical modifications to one electrical train per outage. In view of the high consequences of degraded voltage conditions concurrent with an ESF actuation (impact on redundant trains of ESF equipment). explain why the modification cannot be implemented in one outage with non-intrusive work performed online. |
| | APHB |
| | : 1. Identify the compensatory actions that will be relied upon to support the proper operation of equipment identified in Question 1 above. Include in the response details of the consequences on accident analyses as a result of any delay in equipment restoration by the proposed manual actions. |
| | : 2. How long have the existing manual actions that respond to degraded voltage conditions been in place? If not since initial licensing. what were the circumstances that led to allocation of this function to operators rather than automatic systems? |
| | : 3. Discuss the alarms. annunciators. etc ... that are provided to notify personnel that manual action(s) to respond to degraded voltage conditions is/are required. |
| | : 4. Discuss the alarms. annunciators, etc ... that are provided to notify personnel that the manual action(s) to respond to degraded voltage conditions is/are no longer required. |
| | : 5. Describe the administrative controls in place to ensure that. when the action(s) is/are no longer required, and the plant configuration is restored in the correct configuration for the plant status. |
| | : 6. a. Describe any manual actions in the normal and the emergency operating procedures in addition to those discussed in Q2 that are needed to prevent or mitigate degraded voltage conditions. |
| | : b. If the Emergency Operating Procedures are involved. describe any verification and validation that was done to confirm that the existing manual actions are feasible. reliable. and effective. e.g .. initial start-up testing. V&V performed as part of the Detailed Control Room Design Review. post-mod or post-maintenance testing, or cyclical testing done as part of a Time-Critical Action Program. |
| | : 7. Regarding the V&V or testing discussed in Q7.b. above. did the validation include a representative sample of operators. and was it done with Technical Specification (TS) minimum staffing and nominal staffing? Discuss the time required to perform manual actions versus time available. |
| | : 8. Describe any controls or displays (including annunciators and alarms) needed to respond to degraded voltage conditions until implementation of the proposed modifications. |
| | |
| | ML13031A626 *Via email OFFICE DORULPLlI-1/PM DORULPLlI-1/LA DE/EEEB/BC(A) DRAlAPHB/BC DORULPLlI-1/BC NAME EBrown SFigueroa RMathew US hoop |
| | * RMartin for wi comments RPascareIIi DATE 3/7/13 2/6113 2/21/13 2/1113 3/22/13}} |
Letter Sequence Acceptance Review |
---|
|
|
MONTHYEARML13031A6262013-03-22022 March 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Degraded Voltage Compensatory Measures (TAC Nos. MF0468 and MF0469) (NL-12-2142) Project stage: Acceptance Review ML14069A3442014-05-13013 May 2014 Issuance of Amendments to Incorporate the Schedule for Degraded Grid Voltage Modification Project stage: Approval 2013-03-22
[Table View] |
|
---|
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] Category:Request for Additional Information (RAI)
MONTHYEARML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21127A1132021-05-0606 May 2021 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012 ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML20149K4392020-05-21021 May 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2 ML20121A1472020-04-29029 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate Follow-up RAI Emib No. 1 ML20115E3922020-04-24024 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding TS 3.3.1 and TS 3.3.7 License Amendment Request ML20084G5272020-03-23023 March 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Measurement Uncertainty Recapture Power Uprate ML20055E9752020-02-28028 February 2020 Request for Additional Information Update the Spent Fuel Pool Criticality Safety Analysis (EPID L-2019-LLA-0212) Non-Proprietary Version ML19150A1022019-05-29029 May 2019 Request for Additional Information Regarding Relief Request FNP-ISI-05-04, Version 1.0 (L-2019-LLR-0020) ML19066A0422019-03-0707 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0 ML19056A2142019-02-25025 February 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18239A1542018-08-24024 August 2018 Emergency Preparedness Inspection and Request for Information ML18087A1462018-05-0101 May 2018 Request for Additional Information TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program ML17194A7872017-07-21021 July 2017 Request for Additional Information ML17095A4152017-04-17017 April 2017 Request for Additional Information ML17065A2012017-03-24024 March 2017 Request for Additional Information ML17069A2792017-03-16016 March 2017 Unit 2, Request for Additional Information ML17058A1132017-03-15015 March 2017 Request for Additional Information ML17061A0792017-03-0202 March 2017 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request RR-PR-03 ML17010A0142017-01-19019 January 2017 Request for Additional Information Regarding License Aging Management Program ML16243A1992016-08-30030 August 2016 Notification of Inspection and Request for Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16204A0422016-07-26026 July 2016 Acceptance Letter, Unacceptable, with Opportunity to Supplement ML16187A3082016-06-28028 June 2016 Requalification Program Inspection - Joseph M. Farley Nuclear Plant 2024-01-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 22, 2013 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P. O. Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION CONCERNING DEGRADED VOLTAGE COMPENSATORY MEASURES (TAC NOS. MF0468 AND MF0469) (NL-12-2142)
Dear Mr. Pierce:
By letter dated December 21, 2012, [Agencywide Document Access and Management System (ADAMS) No. ML12356A470] the Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request for Joseph M. Farley Nuclear Plant, Units 1 and 2. The proposed amendment requests the addition of condition to the licensee related to the completion date for SNC to complete modifications to redesign the current degraded voltage scheme to eliminate the use of administrative controls. This application was made to support ongoing compensatory measures as a result of NRC staff inspection results in NRC Inspection Report 50-348(364)/2011-10 (ADAMS Accession No. ML113530575).
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
C. Pierce -2 Given the rare circumstances surrounding this submittal, the NRC staff has identified that in addition to the schedule request, SNC needs to submit, for NRC approval, those compensatory measures that the licensee intends to keep in place until completion of the proposed modifications at the end of the spring 2018 outage. Therefore, the NRC staff requests that SNC supplement the application to address the information requested in the enclosure by 60 days from the issuance of this letter. This will enable the NRC staff to begin its detailed technical review. Should the application be subsequently accepted for review, SNC will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and the associated timeframe in this letter were discussed with Mr. Doug McKinney of your staff on March 7,2013.
If you have any questions, please contact me by phone at (301) 415-2315 or email at Eva. Brown@nrc.gov.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
As stated cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED FOR DEGRADED VOLTAGE SCHEDULE REQUEST SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 In the letter dated December 21, 2012 (the submittal [Agencywide Document Access and Management System (ADAMS) No. ML12356A470], Southern Nuclear Operating Company (SNC, the licensee) indicates that an administrative limit has been established at a voltage level between the degraded grid voltage alarm allowable value (AV) and the automatic degraded grid voltage actuation upper AV. In the voltage range between the administrative limit and the degraded grid voltage actuation trip setpoint, a few engineered safety feature (ESF) components may not have automatic protection from inadequate voltage.
The submittal further states that manual actions provide the primary means of protecting these few ESF components from a sustained, slightly low voltage condition and all components from unnecessary automatic disconnection from the preferred offsite power source.
- 1. In the event of ESF actuation during degraded voltage conditions, provide details on:
a) Equipment/components that may not have adequate voltage to operate; b) Equipment that may trip due to automatic protection such as overload relay actuations; c) Equipment that may trip but will require manual action to reset the protective device; and, d) Equipment that may degrade and may not be able to perform its required function.
- 2. Explain the grid contingencies that were considered to ensure the switchyard voltages remain above the voltages required for safe shutdown of the plant.
- 3. Provide technical basis including supporting data or analysis to show that the degraded voltage relay alarm settings would provide enough time to take operator actions in order to protect all Class 1E equipment from the consequences of a sustained degraded voltage condition.
- 4. The implementation schedule proposes Technical Specification amendment request after completion of Design. In order to expedite the schedule, explain why a concurrent amendment request is not considered to resolve any staff questions associated with proposed setpoints.
Enclosure
-2
- 5. The submittal indicates that two outages are necessary to complete the modifications on each unit based on SNC's philosophy that limits electrical modifications to one electrical train per outage. In view of the high consequences of degraded voltage conditions concurrent with an ESF actuation (impact on redundant trains of ESF equipment). explain why the modification cannot be implemented in one outage with non-intrusive work performed online.
APHB
- 1. Identify the compensatory actions that will be relied upon to support the proper operation of equipment identified in Question 1 above. Include in the response details of the consequences on accident analyses as a result of any delay in equipment restoration by the proposed manual actions.
- 2. How long have the existing manual actions that respond to degraded voltage conditions been in place? If not since initial licensing. what were the circumstances that led to allocation of this function to operators rather than automatic systems?
- 3. Discuss the alarms. annunciators. etc ... that are provided to notify personnel that manual action(s) to respond to degraded voltage conditions is/are required.
- 4. Discuss the alarms. annunciators, etc ... that are provided to notify personnel that the manual action(s) to respond to degraded voltage conditions is/are no longer required.
- 5. Describe the administrative controls in place to ensure that. when the action(s) is/are no longer required, and the plant configuration is restored in the correct configuration for the plant status.
- 6. a. Describe any manual actions in the normal and the emergency operating procedures in addition to those discussed in Q2 that are needed to prevent or mitigate degraded voltage conditions.
- b. If the Emergency Operating Procedures are involved. describe any verification and validation that was done to confirm that the existing manual actions are feasible. reliable. and effective. e.g .. initial start-up testing. V&V performed as part of the Detailed Control Room Design Review. post-mod or post-maintenance testing, or cyclical testing done as part of a Time-Critical Action Program.
- 7. Regarding the V&V or testing discussed in Q7.b. above. did the validation include a representative sample of operators. and was it done with Technical Specification (TS) minimum staffing and nominal staffing? Discuss the time required to perform manual actions versus time available.
- 8. Describe any controls or displays (including annunciators and alarms) needed to respond to degraded voltage conditions until implementation of the proposed modifications.
ML13031A626 *Via email OFFICE DORULPLlI-1/PM DORULPLlI-1/LA DE/EEEB/BC(A) DRAlAPHB/BC DORULPLlI-1/BC NAME EBrown SFigueroa RMathew US hoop
- RMartin for wi comments RPascareIIi DATE 3/7/13 2/6113 2/21/13 2/1113 3/22/13