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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 October 25, 2016 Mrs. Cheryl A. Gayheart VP Nuclear Plant Site Southern Nuclear Operating Co., Inc. | ||
Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319 | |||
Mrs. Cheryl A. Gayheart | |||
VP Nuclear Plant Site | |||
Southern Nuclear Operating Co., Inc. | |||
Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319 | |||
==SUBJECT:== | ==SUBJECT:== | ||
JOSEPH M. FARLEY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION | JOSEPH M. FARLEY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION | ||
==Dear Mrs. Gayheart:== | ==Dear Mrs. Gayheart:== | ||
From January 9 - 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) will perform a Post-Approval Inspection for License Renewal at the Farley Nuclear Plant, Units 1 and 2, in accordance with NRC inspection procedure (IP) 71003, | From January 9 - 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) will perform a Post-Approval Inspection for License Renewal at the Farley Nuclear Plant, Units 1 and 2, in accordance with NRC inspection procedure (IP) 71003, Post-Approval Site Inspection for License Renewal. Previous inspections confirm that this inspection is resource-intensive for both the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for information. | ||
The enclosed request identifies the documents that the inspectors will need upon arrival at the site, to successfully meet the inspection objectives. Requested documents should be current and complete to maximize efficiency during onsite portions of the inspection. | The enclosed request identifies the documents that the inspectors will need upon arrival at the site, to successfully meet the inspection objectives. Requested documents should be current and complete to maximize efficiency during onsite portions of the inspection. | ||
We have discussed the schedule for these inspection activities with your staff, and understand that our regulatory contact for this inspection will be Julie Collier of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Robert E. Williams Jr., at 404-997-4664. | |||
We have discussed the schedule for these inspection activities with your staff, and understand that our regulatory contact for this inspection will be Julie Collier of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Robert E. Williams Jr., at 404-997-4664. | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding, of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter, its Enclosure, and your response (if any), will be available electronically for public inspection in the NRCs Public Document Room, or from the Publicly | ||
C. Gayheart 2 Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Sincerely, | Sincerely, | ||
/RA/ | |||
Shakur A. Walker, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-348, 50-364 License No. NPF-2, NPF-8 | |||
Docket No. 50-348, 50-364 License No. NPF-2, NPF-8 | |||
==Enclosure:== | ==Enclosure:== | ||
Request for Information Post-Approval Inspection for License Renewal | Request for Information Post-Approval Inspection for License Renewal cc: Distribution via Listserv | ||
_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE REW1 SAW4 NAME RWILLIAMS SWALKER DATE 10/25/2016 10/25/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO REQUEST FOR INFORMATION POST-APPROVAL INSPECTION FOR LICENSE RENEWAL Site: Joseph M. Farley Nuclear Plant, Units 1 and 2 Inspection Dates: January 9 - 13, 2017 (onsite week 1) | |||
_________________________ | |||
Inspection Dates: | |||
January 16 - 20, 2017 (in-office review week) | January 16 - 20, 2017 (in-office review week) | ||
January 23 - 27, 2017 (onsite week 2) | January 23 - 27, 2017 (onsite week 2) | ||
Inspection Procedure: | Inspection Procedure: IP 71003, Post-Approval Site Inspection for License Renewal dated July 08, 2016 Inspectors: Alexander Butcavage, Reactor Inspector Robert Carrion, Senior Reactor Inspector Brendan Collins, Reactor Inspector Paula Cooper, Reactor Inspector Abhijit Sengupta, Reactor Inspector Robert Williams, Senior Reactor Inspector (Lead) | ||
The following information should be made available to the inspection team in hard copy or electronic format upon arrival to the site. Due to differences in license conditions and regulatory commitments among operating reactor sites associated with the license renewal process, the information requested below may not be entirely applicable to Farley Nuclear Plant. | |||
Inspectors: | The information listed in Section A of this enclosure is not aimed to a particular regulatory commitment, license condition, aging management program (AMP), or time-limited aging analysis (TLAA). Section A requests general information that will help the inspectors to understand the applicable administrative procedures and overall completion status of license renewal activities. Prior to the inspection, the lead inspector will select a sample of regulatory commitments, license conditions, and AMPs for review, including TLAAs. The information listed in Section B of this enclosure should be provided for each item selected for review. If there are any questions regarding this information request, please contact the lead inspector as soon as possible. | ||
The following information should be made available to the inspection team in hard copy or electronic format upon arrival to the site. Due to differences in license conditions and regulatory commitments among operating reactor sites associated with the license renewal process, the information requested below may not be entirely applicable to Farley Nuclear Plant. | |||
The information listed in Section | |||
possible. | |||
A. General Information Request (As Applicable) | A. General Information Request (As Applicable) | ||
(1) Sections of the quality assurance program manual applicable to license renewal activities (2) Corrective Action Program (CAP) procedures (3) Regulatory Commitment Change Process procedures (4) Operating Experience (OE) Program procedures (5) Latest version of the updated final safety analysis report (UFSAR) supplement for license renewal submitted with the license renewal application (LRA). | (1) Sections of the quality assurance program manual applicable to license renewal activities (2) Corrective Action Program (CAP) procedures (3) Regulatory Commitment Change Process procedures (4) Operating Experience (OE) Program procedures (5) Latest version of the updated final safety analysis report (UFSAR) supplement for license renewal submitted with the license renewal application (LRA). | ||
(6) Last version of the UFSAR supplement for license renewal submitted to the NRC per 10 CFR 50.71. | (6) Last version of the UFSAR supplement for license renewal submitted to the NRC per 10 CFR 50.71. | ||
Enclosure | |||
(9) List of plant modifications with a brief description of the modification scope that were approved and/or implemented from the date the LRA was submitted to the date the | 2 (7) Living version of the UFSAR supplement for license renewal (8) Post-approval evaluations or assessments performed to verify that in-scope structures, systems, or components (SSCs) were not excluded from the LRA and appropriate aging management has been considered in accordance with 10CFR 54.37(b) | ||
(9) List of plant modifications with a brief description of the modification scope that were approved and/or implemented from the date the LRA was submitted to the date the renewed license was issued (10) Self-assessments performed after the renewed license was issued associated with the implementation of license renewal commitments, including AMPs and TLAAs (11) Gap analyses performed to assess the differences between the current AMPs and the recommendations in the latest revision of NUREG-1801, Generic Aging Lessons Learned (GALL), and subsequent Interim Staff Guidance (12) Site-specific responses and/or evaluations for NRC generic communications associated with license renewal that were issued after the renewed license was granted (13) Description of the overall completion status of action items associated with license renewal commitments, including AMPs and TLAAs (14) Description of administrative controls that will be used to ensure that all activities due prior to (and during) the period of extended operation (PEO) will be satisfactorily completed as described in the license renewal documents (15) Description of plans or processes that would be used during the PEO to continuously incorporate operating experience into license renewal activities B. Specific Requests for each License Renewal Commitment Selected for Review, including AMPs and TLAAs (As Applicable) | |||
(1) Program basis documents and administrative procedures describing key program attributes such as program objectives, scope, detection and monitoring methods, administrative controls, acceptance criteria, corrective actions, and scope expansion requirements (2) Implementing procedures for program activities (e.g. visual examination procedures, ultrasonic examination procedures, maintenance procedures, system walkdowns, etc) | |||
(3) Updated license renewal scoping drawings showing the SSCs within the scope of the AMP (4) Applicable sections of the LRA (5) Applicable requests for additional information (RAIs) issued by NRCs technical reviewers during the review of the LRA and corresponding responses (6) Applicable sections of the NRCs safety evaluation report | |||
3 (7) Copy or ready access to the key industry standards that will be followed during the PEO for the implementation of the program (e.g. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Electric Power Research Institute Guidelines, Nuclear Energy Institute Guidelines, etc. | |||
(8) Description of changes made to the license renewal commitment, including the associated technical and regulatory evaluations supporting the change. | |||
(9) Description of activities completed to meet license conditions, license renewal commitments, and the UFSAR. For example, this should include completed Work Orders (WOs) with associated inspection reports describing the work done and the results of the inspection. | |||
3 | |||
(8) Description of changes made to the license renewal commitment, including the associated technical and regulatory evaluations supporting the change. | |||
(9) Description of activities completed to meet license conditions, license renewal commitments, and the UFSAR. For example, this should include completed Work Orders (WOs) with associated inspection reports describing the work done and the results of the inspection. | |||
(10) Description of instances where examination scope expansion was required based on the initial examination of a SSC for license renewal. Please describe the logic to select the scope expansion, and any resulting changes to the AMP. | (10) Description of instances where examination scope expansion was required based on the initial examination of a SSC for license renewal. Please describe the logic to select the scope expansion, and any resulting changes to the AMP. | ||
(11) Description of instances where examination scope changes were required based on limitations encountered during the initial examination of a SSC for license renewal. Please describe the actions taken, and any resulting changes to the AMP. | (11) Description of instances where examination scope changes were required based on limitations encountered during the initial examination of a SSC for license renewal. Please describe the actions taken, and any resulting changes to the AMP. | ||
(12) Description of pending activities due prior to the PEO, which are necessary to meet license conditions, license renewal commitments, and the activities described in the UFSAR. For example, this may include a list of pending WOs with a brief description of the work to be performed. | (12) Description of pending activities due prior to the PEO, which are necessary to meet license conditions, license renewal commitments, and the activities described in the UFSAR. For example, this may include a list of pending WOs with a brief description of the work to be performed. | ||
(13) Copy of any correspondence between the licensee and the NRC, after the license was issued, associated with regulatory issues affecting the license renewal commitment. For example, this may include notifications of commitment changes, or license amendment requests, affecting a license condition or a license renewal commitment. | |||
(13) Copy of any correspondence between the licensee and the NRC, after the license was issued, associated with regulatory issues affecting the license renewal commitment. For example, this may include notifications of commitment changes, or license amendment requests, affecting a license condition or a license renewal commitment. | |||
(14) List of CAP documents (e.g., Condition Reports) associated with the implementation of the AMP. This includes unacceptable aging effects identified during the implementation of license renewal activities, and programmatic deficiencies requiring resolution. | (14) List of CAP documents (e.g., Condition Reports) associated with the implementation of the AMP. This includes unacceptable aging effects identified during the implementation of license renewal activities, and programmatic deficiencies requiring resolution. | ||
(15) Copy of evaluations performed for applicable external and internal OE issues associated with license renewal. This request is limited to OE items issued after the renewed operating license was granted. | (15) Copy of evaluations performed for applicable external and internal OE issues associated with license renewal. This request is limited to OE items issued after the renewed operating license was granted. | ||
Inspector Contact Information: Mailing Address: | |||
Inspector Contact Information: | Robert Williams USNRC Region 2 Senior Reactor Inspector Attn: Robert Williams 404-997-4664 Marquis One Tower Robert.Williams@nrc.gov 245 Peachtree Center Avenue NE Suite 1200 Atlanta, GA 30303}} |
Latest revision as of 23:36, 4 February 2020
ML16303A003 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 10/25/2016 |
From: | Sandra Walker NRC/RGN-II/DRS/EB3 |
To: | Gayheart C Southern Nuclear Operating Co |
References | |
Download: ML16303A003 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 October 25, 2016 Mrs. Cheryl A. Gayheart VP Nuclear Plant Site Southern Nuclear Operating Co., Inc.
Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mrs. Gayheart:
From January 9 - 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) will perform a Post-Approval Inspection for License Renewal at the Farley Nuclear Plant, Units 1 and 2, in accordance with NRC inspection procedure (IP) 71003, Post-Approval Site Inspection for License Renewal. Previous inspections confirm that this inspection is resource-intensive for both the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for information.
The enclosed request identifies the documents that the inspectors will need upon arrival at the site, to successfully meet the inspection objectives. Requested documents should be current and complete to maximize efficiency during onsite portions of the inspection.
We have discussed the schedule for these inspection activities with your staff, and understand that our regulatory contact for this inspection will be Julie Collier of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Robert E. Williams Jr., at 404-997-4664.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding, of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter, its Enclosure, and your response (if any), will be available electronically for public inspection in the NRCs Public Document Room, or from the Publicly
C. Gayheart 2 Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Shakur A. Walker, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-348, 50-364 License No. NPF-2, NPF-8
Enclosure:
Request for Information Post-Approval Inspection for License Renewal cc: Distribution via Listserv
_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE REW1 SAW4 NAME RWILLIAMS SWALKER DATE 10/25/2016 10/25/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO REQUEST FOR INFORMATION POST-APPROVAL INSPECTION FOR LICENSE RENEWAL Site: Joseph M. Farley Nuclear Plant, Units 1 and 2 Inspection Dates: January 9 - 13, 2017 (onsite week 1)
January 16 - 20, 2017 (in-office review week)
January 23 - 27, 2017 (onsite week 2)
Inspection Procedure: IP 71003, Post-Approval Site Inspection for License Renewal dated July 08, 2016 Inspectors: Alexander Butcavage, Reactor Inspector Robert Carrion, Senior Reactor Inspector Brendan Collins, Reactor Inspector Paula Cooper, Reactor Inspector Abhijit Sengupta, Reactor Inspector Robert Williams, Senior Reactor Inspector (Lead)
The following information should be made available to the inspection team in hard copy or electronic format upon arrival to the site. Due to differences in license conditions and regulatory commitments among operating reactor sites associated with the license renewal process, the information requested below may not be entirely applicable to Farley Nuclear Plant.
The information listed in Section A of this enclosure is not aimed to a particular regulatory commitment, license condition, aging management program (AMP), or time-limited aging analysis (TLAA). Section A requests general information that will help the inspectors to understand the applicable administrative procedures and overall completion status of license renewal activities. Prior to the inspection, the lead inspector will select a sample of regulatory commitments, license conditions, and AMPs for review, including TLAAs. The information listed in Section B of this enclosure should be provided for each item selected for review. If there are any questions regarding this information request, please contact the lead inspector as soon as possible.
A. General Information Request (As Applicable)
(1) Sections of the quality assurance program manual applicable to license renewal activities (2) Corrective Action Program (CAP) procedures (3) Regulatory Commitment Change Process procedures (4) Operating Experience (OE) Program procedures (5) Latest version of the updated final safety analysis report (UFSAR) supplement for license renewal submitted with the license renewal application (LRA).
(6) Last version of the UFSAR supplement for license renewal submitted to the NRC per 10 CFR 50.71.
Enclosure
2 (7) Living version of the UFSAR supplement for license renewal (8) Post-approval evaluations or assessments performed to verify that in-scope structures, systems, or components (SSCs) were not excluded from the LRA and appropriate aging management has been considered in accordance with 10CFR 54.37(b)
(9) List of plant modifications with a brief description of the modification scope that were approved and/or implemented from the date the LRA was submitted to the date the renewed license was issued (10) Self-assessments performed after the renewed license was issued associated with the implementation of license renewal commitments, including AMPs and TLAAs (11) Gap analyses performed to assess the differences between the current AMPs and the recommendations in the latest revision of NUREG-1801, Generic Aging Lessons Learned (GALL), and subsequent Interim Staff Guidance (12) Site-specific responses and/or evaluations for NRC generic communications associated with license renewal that were issued after the renewed license was granted (13) Description of the overall completion status of action items associated with license renewal commitments, including AMPs and TLAAs (14) Description of administrative controls that will be used to ensure that all activities due prior to (and during) the period of extended operation (PEO) will be satisfactorily completed as described in the license renewal documents (15) Description of plans or processes that would be used during the PEO to continuously incorporate operating experience into license renewal activities B. Specific Requests for each License Renewal Commitment Selected for Review, including AMPs and TLAAs (As Applicable)
(1) Program basis documents and administrative procedures describing key program attributes such as program objectives, scope, detection and monitoring methods, administrative controls, acceptance criteria, corrective actions, and scope expansion requirements (2) Implementing procedures for program activities (e.g. visual examination procedures, ultrasonic examination procedures, maintenance procedures, system walkdowns, etc)
(3) Updated license renewal scoping drawings showing the SSCs within the scope of the AMP (4) Applicable sections of the LRA (5) Applicable requests for additional information (RAIs) issued by NRCs technical reviewers during the review of the LRA and corresponding responses (6) Applicable sections of the NRCs safety evaluation report
3 (7) Copy or ready access to the key industry standards that will be followed during the PEO for the implementation of the program (e.g. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Electric Power Research Institute Guidelines, Nuclear Energy Institute Guidelines, etc.
(8) Description of changes made to the license renewal commitment, including the associated technical and regulatory evaluations supporting the change.
(9) Description of activities completed to meet license conditions, license renewal commitments, and the UFSAR. For example, this should include completed Work Orders (WOs) with associated inspection reports describing the work done and the results of the inspection.
(10) Description of instances where examination scope expansion was required based on the initial examination of a SSC for license renewal. Please describe the logic to select the scope expansion, and any resulting changes to the AMP.
(11) Description of instances where examination scope changes were required based on limitations encountered during the initial examination of a SSC for license renewal. Please describe the actions taken, and any resulting changes to the AMP.
(12) Description of pending activities due prior to the PEO, which are necessary to meet license conditions, license renewal commitments, and the activities described in the UFSAR. For example, this may include a list of pending WOs with a brief description of the work to be performed.
(13) Copy of any correspondence between the licensee and the NRC, after the license was issued, associated with regulatory issues affecting the license renewal commitment. For example, this may include notifications of commitment changes, or license amendment requests, affecting a license condition or a license renewal commitment.
(14) List of CAP documents (e.g., Condition Reports) associated with the implementation of the AMP. This includes unacceptable aging effects identified during the implementation of license renewal activities, and programmatic deficiencies requiring resolution.
(15) Copy of evaluations performed for applicable external and internal OE issues associated with license renewal. This request is limited to OE items issued after the renewed operating license was granted.
Inspector Contact Information: Mailing Address:
Robert Williams USNRC Region 2 Senior Reactor Inspector Attn: Robert Williams 404-997-4664 Marquis One Tower Robert.Williams@nrc.gov 245 Peachtree Center Avenue NE Suite 1200 Atlanta, GA 30303