IR 05000327/2020011
| ML20079J317 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/19/2020 |
| From: | Binoy Desai NRC/RGN-II/DRS/EB3 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2020011 | |
| Download: ML20079J317 (28) | |
Text
rch 19, 2020
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - NRC INSPECTION REPORT 05000327/2020011 AND 05000328/2020011
Dear Mr. Barstow:
On February 14, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah Nuclear Plant, Units 1 and 2 and discussed the results of this inspection with Mr. Scott Honeywell and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79
Enclosure:
Inspection Report
Inspection Report
Docket Numbers: 05000327 and 05000328 License Numbers: DPR-77 and DPR-79 Report Numbers: 05000327/2020011 and 05000328/2020011 Enterprise Identifier: I-2020-011-0022 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Soddy Daisy, TN Inspection Dates: January 27, 2020 to February 14, 2020 Inspectors: S. Downey, Senior Reactor Inspector (Lead)
I. Anchondo-Lopez, Reactor Inspector A. Butcavage, Reactor Inspector B. Collins, Senior Reactor Inspector P. Cooper, Reactor Inspector Approved By: Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC inspection at Sequoyah Nuclear Plant, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===71003 - Post-Approval Site Inspection for License Renewal From January 27, 2020 to February 14, 2020, the NRC continued monitoring TVAs performance at Sequoyah by conducting a Post-Approval Site Inspection for License Renewal -
Phase II in accordance with the license renewal inspection program (LRIP). This inspection took place prior to the period of extended operation (PEO) for Units 1 and 2, which will begin on September 17, 2020 and September 15, 2021, respectively. Per Inspection Manual Chapter 2516, the LRIP is the process used by NRC staff to verify the adequacy of aging management programs (AMPs), Time Limited Aging Analyses (TLAAs), and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.
Post-Approval Site Inspection for License Renewal ===
- (1) License Conditions and Commitments for License Renewal, Implementation of Aging Management Programs and Time-Limited Aging Analyses There are a total of 45 regulatory commitments linked to the renewed operating license for Sequoyah Nuclear Plant Units 1 and 2, issued in September 2015, which include the following: 26 commitments to enhance existing AMPs; 13 commitments to implement new AMPs; 4 commitments to implement existing AMPs; and 2 standalone commitments (not associated with an AMP or TLAA). The inspectors reviewed a majority (greater than 70%) of regulatory commitments and associated AMPs and TLAAs in order to assess the adequacy and effectiveness of the license renewal program. For each item selected in the sample, the inspectors also reviewed the applicable license renewal program documents, conducted interviews with licensee staff, and performed system walkdowns to verify that the licensee completed the actions necessary to comply with the conditions listed in the renewed facility operating license. For those license renewal action items that were not completed at the time of this inspection, the inspectors verified, when possible, that there was reasonable assurance that such action items were on track for completion prior to the PEO or in accordance with an established implementation schedule consistent with the license renewal application (LRA), the NRC safety evaluation report (SER), and the Updated Final Safety Analysis Report (UFSAR) supplement. Commitment Items with pending actions requiring further inspection by the NRC are described in the Inspection Results section of this report.
The regulatory commitments selected for the inspection sample are listed below along with the completion status of the item at the time of the inspection. The full description of each commitment is available in the UFSAR supplement for license renewal, as revised, and Appendix A of the NRC SER issued as NUREG-2181 (ML15187A206).
- Commitment Item 1: Implementation of, and enhancements to, the Aboveground Metallic Tanks Program. Status: Complete
- Commitment Item 2: Enhancements to the Bolting Integrity Program. Status:
Complete.
- Commitment Item 3: Implementation of, and enhancements to, the Buried and Underground Piping and Tanks Inspection Program. Status: Incomplete, some license renewal action items have not been completed. Specifically, the final installation and activation of the cathodic protection has not been completed and is expected to be implemented prior to entering the PEO. Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #3. Therefore, no follow-up inspection is warranted.
- Commitment Item 4: Enhancements to the Compressed Air Monitoring Program. Status: Complete.
- Commitment Item 5: Enhancements to the Diesel Fuel Oil Monitoring Program: Status: Incomplete, one license renewal action item has not been completed. Specifically, the licensee has not put administrative controls in place to ensure that Commitment 5.C will be met during the PEO. To ensure the timely and technically acceptable completion of the remaining activities, Commitment Item 5 will remain open, is subject to further NRC inspection, and is presented as an observation in the Inspection Results section of this report.
- Commitment Item 6: Enhancements to the External Surfaces Monitoring Program. Status: Incomplete, some license renewal action items have not been completed. Specifically, the licensee has not put administrative controls in place to ensure that Commitment 6.A will be met during the PEO. To ensure the timely and technically acceptable completion of the remaining activities, Commitment Item 6 will remain open, is subject to further NRC inspection, and is presented as an observation in the Inspection Results section of this report
- Commitment Item 7: Enhancements to the Fatigue Monitoring Program and implantation of associated Time-limited Aging Analyses. Status: Complete.
- Commitment Item 8: Enhancements to the Fire Protection Program. Status:
Complete.
- Commitment Item 9: Implementation of the Fire Water System Program.
Status: Complete
- Commitment Item 10: Enhancements to the Flow Accelerated Corrosion Program. Status: Complete.
- Commitment Item 11: Enhancements to the Flux Thimble Tube Inspection Program. Status: Complete.
- Commitment Item 12: Enhancements to the Inservice Inspection - IWF Program. Status: Complete.
- Commitment Item 13: Enhancements to the Inspection of Overhead Heavy Load and Light Load Handling Systems. Status: Complete.
- Commitment Item 14: Implementation of, and enhancements to, the Internal Surfaces and Miscellaneous Piping and Ducting Components Program. Status: Complete.
- Commitment Item 15: Implementation of the Metal Enclosed Bus Program. Status: Complete.
- Commitment Item 16: Enhancements to the Neutron Absorbing Material Monitoring Program. Status: Complete
- Commitment Item 17: Implementation of the Non-EQ Cable Connections Program. Status: Complete.
- Commitment Item 18: Implementation of the Non-EQ Inaccessible Power Cables (400V to 35kV) Program. Status: Complete.
- Commitment Item 19: Implementation of the Non-EQ Instrumentation Circuits Test Review Program. Status: Complete.
- Commitment Item 22: Implementation of the One-Time Inspection Program.
Status: Complete.
- Commitment Item 23: Implementation of the One-Time Inspection - Small Bore Piping Program. Status: Complete.
- Commitment Item 24: Enhancements to the Periodic Surveillance and Preventative Maintenance Program. Status: Complete.
- Commitment Item 25: Enhancement to the Protective Coating Program. Status: Complete.
- Commitment Item 26: Enhancement to the Reactor Head Closure Studs Program. Status: Complete
- Commitment Item 27: Enhancements to the Reactor Vessel Internals Program. Status: Complete.
- Commitment Item 28: Enhancements to the Reactor Vessel Surveillance Program
- Commitment Item 29: Implementation of the Selective Leaching Program. Status: Incomplete, some license renewal action items have not been completed. Specifically, there were eight valves in the High Pressure Fire Protection system made of gray cast iron and were therefore in the scope of the Selective Leaching Program. However, the valves were installed in 1998 and inspecting them prior to 35 years of service would not provide a true indication of whether selective leaching was occurring. This issue was documented in both the licensees FSAR and Selective Leaching Program Basis Document, and preventive maintenance tasks were scheduled to occur between 2033 and 2038. On this basis, the inspectors determined that there are appropriate administrative controls in place to ensure that Commitment 29 will be met. Therefore, no follow-up inspection is warranted.
- Commitment Item 30: Enhancement to the Steam Generator Integrity Program concerning tube plugging material. Status: Complete
- Commitment Item 31: Enhancements to the Structures Monitoring. Status:
Complete.
- Commitment Item 32: Implementation of the Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program. Status: Complete.
- Commitment Item 33: Enhancements to the Water Chemistry Control- Closed Treated Water Systems Program. Status: One license renewal action item has not been completed. Specifically, the licensee has not put administrative controls in place to ensure that Commitment Item 33.D will be met during the PEO. To ensure the timely and technically acceptable completion of the remaining activities, Commitment Item 33 will remain open, is subject to further NRC inspection, and is presented as an observation in the Inspection Results section of this report
- Commitment Item 34: Enhancement to the Containment Leak Rate Program.
Status: Complete.
- Commitment Item 35: Enhancements to Containment Inservice Inspection -
IWE Program made in response to RAI B.1.6-1 (MLA13190A276, ML13312A005, ML13294A462, ML14058A131). Status: Complete
- Commitment Item 36: Enhancements to the Inservice Inspection Program. Status: One license renewal action item has not been completed. Specifically, the licensee is unable to meet Commitment 36.A as written because there is currently no ASME or EPRI qualified technique available to detect cracking in CASS components. The issue has been entered into the licensees Corrective Action Program as CR 1582890. Under this CR, the licensee will track industry progress on developing qualified examination techniques. Once a technique is qualified, the ISI program will be revised to incorporate the inspections described in the commitment. On this basis, the inspectors determined that there are appropriate administrative controls in place to ensure that Commitment 36.A will be met. Therefore, no follow-up inspection is warranted.
- Commitment 37: Implement OE and AMPs in accordance with TVA response to RAI B.0.4-1 (ML13213A027) and 10/17/13 letter, RAIs B.0.4-1 and A.1-1a (ML13294A462). Status: Complete.
- Commitment Item 38: Enhancements to the Service Water Integrity Program.
Status: Complete.
- Commitment Item 41: Implementation of the Masonry Wall Program. Status:
Complete.
- Commitment Item 44: Implementation of the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Program. Status:
Complete for Units 1 and 2. The inspection of the submerged portion of the water-controlled structures has not been performed, however, the requirement to perform the inspection has been incorporated into program documents. Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment 44. Therefore, no follow-up inspection is warranted.
- Commitment Item 45: Implementation of the 161-kV Oil Filled Cables Program. Status: Complete.
- (2) Newly Identified Structures, Systems, and Components (SSCs)
Since the renewed license was issued, the licensee has performed two assessments to identify any SSCs that would have been subject to an aging management review or evaluation as a time-limited aging analysis in accordance with 10 CFR 54.21. The inspectors reviewed the licensees assessments and noted that the following SSCs were identified as being within the scope of license renewal and subject to aging management review:
1. Auxiliary Essential Raw Cooling Water (AERCW) Pump Structure 2. Essential Raw Cooling Water Valve Boxes 1, 3, 4, 5, and 6, and Thermometer Boxes 1 and 2 3. High Pressure Fire Protection Inaccessible Cables 4. Main Feedwater Control Mechanical Components For each newly identified SSC, the inspectors determined that the licensee took appropriate actions in accordance with 10 CFR 54.37(b). Specifically, the inspectors verified that the SSCs have been included in the FSAR update required by 10 CFR 50.71(e), and that the FSAR update described how the effects of aging are managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation. The inspectors also reviewed a list of plant modifications performed from the time the LRA was submitted to the time the renewed operating license was issued, to identify any potentially new SSCs that would have been subject to aging management review at the time the NRC was reviewing the LRA. Based on this review, the inspectors did not identify any new SSCs that were subject to the provisions of 10 CFR 54.37(b).
- (3) Description of Aging Management Programs in the UFSAR Supplement As part of the review of implementation activities for the selected AMPs, the inspectors reviewed the corresponding UFSAR sections to verify that the program descriptions were consistent with the license renewal application and the corresponding section of the NRC safety evaluation report. The inspectors reviewed three versions of the UFSAR supplement for license renewal as follows:
- The inspectors reviewed the UFSAR supplement submitted with the LRA, as revised, to identify the program attributes and future inspection activities that were originally relied upon for the approval of the renewed operating license.
- The inspectors reviewed the revision of the UFSAR submitted to the NRC pursuant to the requirements in 10 CFR 50.71(e)(4) following the issuance of the renewed operating license to verify that the UFSAR supplement for license renewal was included as required by the condition of the renewed operating license.
- The inspectors reviewed the latest revision of the UFSAR supplement for license renewal (Amendment 28) to verify that the program attributes and inspection activities were consistent with the AMPs as originally approved by the NRC and subsequent revisions performed under the provisions of 10 CFR 50.59. The inspectors also verified that any changes caused by the inclusion of newly identified SSCs were included in the UFSAR supplement.
- (4) Changes to license renewal commitments and the UFSAR supplement for license renewal As part of the review of license renewal commitments, AMPs, and TLAAs described in this report, the inspectors reviewed a sample of license renewal commitment change documents to verify the licensee followed the guidance in NEI 99-04, Guidelines for Managing NRC Commitment Changes, for any change to the commitments, including their elimination. Except as identified in the Inspection Results section of the report, the inspectors verified that the licensee properly evaluated, reported, and approved where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59, as required by the Renewed Operating License (Section 2.C.(31))
INSPECTION RESULTS
Observation: Observation for Commitment Item 5 - Enhancements to the Diesel 71003 Fuel Oil Monitoring Program In 2018, the licensee revised Commitment Item No. 5.C, UFSAR section 13.9.1.A.1.8, and UFSAR section 13.9.2, to remove the requirement to perform a ten-year periodic cleaning of the standby diesel fuel oil day tanks and the High Pressure Fire Protection (HPFP) diesel fuel oil storage tank. The revised commitment now requires only an inspection of the tanks to be performed at least once prior to the PEO and at succeeding ten-year intervals and states that these inspections will be supplemented by cleaning, to remove sediment, if warranted, based on the results of periodic cleaning of the fuel oil storage tanks and 7-day tanks, periodic cleaning of the fuel pump suction strainers and filters, and day tank sediment and particulate monitoring. While reviewing the licensees commitment change process documents (i.e.
commitment change evaluation form, 50.59 screen, SAR change request), the inspectors noted that no justification was provided for removing the requirement to periodically clean the HPFP diesel fuel oil storage tank. Specifically, all documents reviewed focus only on the 550-gallon diesel fuel oil day tanks and the licensees physical inability to visually inspect and clean them due to their design and configuration. It is noted that the HPFP diesel fuel oil storage tank is of a different design than the day tanks and provides the access needed to perform a 100% visual inspection, which the licensee performed in May 2018 and found no sludge or deposits that required cleaning.
During an interview with the licensees staff regarding the commitment change, the inspectors determined that the additional activities in the revised commitment that would provide a basis for cleaning the tanks (i.e. cleaning 7 day tanks, cleaning strainers and filters, etc.) are also only applicable to the fuel oil day tanks. When asked what activities would form the basis for cleaning the HPFP diesel fuel oil storage tank, the licensee responded that cleaning of the tank would be performed based on the results of the ten-year periodic visual inspections. The inspectors noted that the licensees response contrasted with what was stated in the commitment. Subsequently, the licensee informed the inspectors that the change to Commitment 5.C that removed the cleaning of the fuel oil day tanks inadvertently implied that the HPFP tank would also not be cleaned. This issue has been captured in the licensees Corrective Action Program as CR 1583386.
At the time of this inspection, this commitment item had not been completed and the licensee needed to take the necessary actions to address CR1583386. Therefore, Commitment Item 5 will require further NRC inspection to ensure timely and technically acceptable completion.
Observation: Observation for Commitment 6: Enhancements to the External 71003 Surfaces Monitoring Program After reviewing the program procedures and interviewing the responsible plant personnel regarding this program, the inspectors identified that Commitment 6.A had not been adequately implemented. Specifically, Commitment 6.A requires that External Surfaces Monitoring Program procedures be revised to clarify that periodic inspection of systems within the scope of license renewal and subject to aging management review (AMR) will be performed. The commitment also states that the inspections shall include areas surrounding the subject systems to identify hazards to those systems and that inspections of nearby systems that could impact the subject systems will include SSCs that are in scope and subject to an AMR.
The program basis document identifies procedure NPG-SPP-09.7.1, Corrosion Control -
General, Localized and Galvanic, and Stress Corrosion Cracking Program, as the implementing procedure of this commitment. The inspectors identified that procedure NPG-SPP-09.7.1 does not address the commitments specific inspection actions but references procedure NPG-SPP-09.0.1.1, System Monitoring and Trending as the implementing procedure that will define the engineering requirements for performing system walk-downs for determining the material condition of systems including documenting adverse conditions such as material wastage due to corrosion. Upon reviewing procedure NPG-SPP-09.0.1.1, the inspectors determined that the procedure did not include the specific actions needed to address Commitment 6.A. This issue was captured in the licensees Corrective Action Program as CR 1586277.
At the time of this inspection, this commitment item had not been completed and the licensee needed to take the necessary actions to address CR1586277. Therefore, Commitment Item 6 will require further NRC inspection to ensure timely and technically acceptable completion.
Observation: Observation related to the Clarity of Acceptance Criteria in the 71003 Preventative Surveillance and Preventative Maintenance Program As documented in the NRC SER (ML15187A206 - NUREG-2181, pg 3-204), RAI B.1.31-4 was issued to request that the licensee clarify whether acceptance criteria would permit degradation by verifying the absence of an aging effect or whether it would permit degradation by verifying that no unacceptable aging effect exists. In response, the licensee stated that they had revised PSPM Program Element 6 by deleting the discussion of significant changes in material properties and unacceptable loss of material, and inserting a new sentence stating that any indication or relevant condition of degradation detected is evaluated. The inspectors noted that the staff found the licensees response to RAI B.1.31-4 acceptable because the acceptance criteria were clarified to ensure that any relevant condition is evaluated, which is consistent to verifying the absence of an aging effect.
While reviewing the PSPM program, the inspectors identified that the original language that prompted the issuance of RAI B.1.31-4 was still present in the program basis document as well as in several implementing procedures. The inspectors also noted several examples where the licensee used similar unclear acceptance criteria, such as no unacceptable cracking, no significant corrosion that would impede performance, and no unacceptable loss of coating integrity, in PSPM program documents. When questioned about the acceptance criteria, the licensee acknowledged that, while clarifying changes were made to in response to RAI B.1.31-4, the original language still existed in several PSPM program documents. This issue has been entered into the licensee Corrective Action Program as CR 1586169. After further discussion with the inspectors, the licensee updated the CR to include an assessment of all of the acceptance criteria in the PSPM program.
Given the expansive nature of the PSPM, and the number of procedures and PMs affected, the NRC will need to perform follow-up inspection activities to ensure that the acceptance criteria have all been clarified as needed to ensure that the effects of aging are adequately managed.
Observation: Observation for Commitment Item 33: Enhancements to the Water 71003 Chemistry Control - Closed Treated Water Systems Program Commitment 33.D requires the licensee to revise the Water Chemistry Control - Closed Treated Water Systems Program procedures to perform sampling and analysis of the glycol cooling system per industry standards and in no case greater than quarterly unless justified with an additional analysis. After reviewing the program procedures and interviewing the responsible plant personnel regarding the program, the inspectors identified that the wrong procedures were revised to implement Commitment 33.D. Specifically, the program basis document states that Commitment 33.D is implemented with the issue of procedures CHEM-003, Closed Cooling Water Chemistry Strategic Plan, 0-PI-CEM-000-001.0, Periodic Chemistry Requirements for Security Backup Diesel Generator and High Pressure Fire Protection Diesel Pump Engine Coolant, and 0-TI-CEM-000-001.4, Auxiliary System and Common System Chemistry Specifications. All three procedures identify the High Pressure Fire Protection (HPFP) Diesel Pump Cooling Water as the point at which glycol will be sampled quarterly to meet the commitment, while CHEM-003 and 0-TI-CEM-000-001.4 both also identify the Security Backup Diesel Generator (SBDG) Cooling Water as a sampling point to meet the commitment. However, the inspectors noted that the glycol cooling system is part of the Ice Condenser System and not the systems referenced in the implementing procedures. When asked for clarification on the sampling point(s) that are applicable to Commitment 33.D, the licensee responded that the two applicable sampling points are listed in PM 063606271, which sample the Ice Condenser System from the main header at two locations on an 18-month frequency, not quarterly as required to meet the commitment. This issue was captured in the licenses Corrective Action Program as CR 1583096.
At the time of this inspection, this commitment item had not been completed and the licensee needed to take the necessary actions to address CR1583096. Therefore, Commitment Item 33 will require further NRC inspection to ensure timely and technically acceptable completion.
Observation: Observation of Incorrect Categorization of Quality Procedures 71003 During the review of the External Surface Condition Monitoring program, the inspectors observed that the implementing periodic instructions were classified as Non-Quality Related documents. The inspectors reviewed procedure TVA-NQA-PLN89-A, Nuclear Quality Assurance Plan (NQAP) and questioned the licensees classification of the periodic instructions. As a result, the licensee performed a review of all license renewal periodic instructions and identified that seven instructions had been incorrectly classified as Non-Quality Related affecting a total of six aging management programs. The licensee placed this issue into their corrective action program as condition report CR 1585902. Since the classification of the procedures is part of the implementation of the site NAQP, and not a regulatory commitment for license renewal, no follow-up inspection is warranted
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 14, 2020, the inspectors presented the NRC inspection results to Mr. Scott Honeywell and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71003 Calculations CEB-GEN- Pipe Rupture Evaluation of Wear on Thimble Tubes and Rev. 2
88PR01 Acceptance Criteria
CN-MRCDA-08-2 CRDM Head Adapter Wear Justification Rev. 1
SI File No. Evaluation of Observed Thinning within 30x24 ERCW 11/26/2019
1901378.301 Branch Piping Tee
Corrective Action Condition Reports 16684, 684461, 684468, 810761, 991942, 993922, 1236019,
Documents 11334236, 1379157, 1407748, 1408833, 1417967, 1442339,
1467388, 1532825, 1561562, 1582509, 1582605, 1582764,
1582854, 1582858, 1582890, 1583050, 1583096, 1583351,
1583386, 1583653, 1585902, 1585757, 1585789, 1585902,
1586060, 1586169, 1586277, 1586388, 1586389, 1586461
Drawings 1,2 -47W450-6 SEQ Nuclear, Mechanical Essential Raw Cooling Water Rev.15
10005D62 Straight CEW Tube Plug, Steam Generator Rev. 2
ISI-0298-C-01 173" PWR Vessel General Arrangement Rev. 3
ISI-0298-C-02 Reactor Vessel Seam Welds Rev. 3
ISI-0298-C-03 Reactor Vessel Interior Seam Welds Rev. 3
ISI-0298-C-04 Reactor Vessel Support Locations Rev. 2
ISI-0298-C-05 Reactor Vessel Core Support Structure Rev. 0
Engineering 28-31 SAR Change Package: Revise PSPM Program to Replace 7-16-18
Changes Diesel Generator Starting Air Aluminum Valves rather than
Inspect
EWR No.18-EPG- Summary of Flow Accelerated Corrosion / Erosoin Program 9/29/18
067-199 insepction for SQN License Renewal Commitments
114446167 & 114446284 in accordance with NPG-SPP-09.0
Section 3.2.9C.
PMSICHG-SQN- TVA PM Change/Deferral: PM #120115 (Selective Leaching 07/22/2019
TICKET-1281317 Inspections)
Engineering 1400627.401 Flaw Tolerance Evaluation of Sequoyah Units 1 and 2 CASS Rev. 1
Evaluations Components
1400627.403 Development of a CASS Aging Management Program for Rev. 1
Sequoyah Unit 1 & 2
CN-RIDA-12-39 Sequoyah Units 1 & 2 Lower Internals Hold Down Capacity Rev. 0
Inspection Type Designation Description or Title Revision or
Procedure Date
Evaluation For Hold-down Spring Height Measurement
CN-RIDA-18-7 Sequoyah Units 1 & 2, Lower Internals Hold-Down Spring 7/26/18
Capability Evaluation for Fuel Transition
EWR No. 17-SIE- SQN Emergency Diesel Generator (EDG) 550 Gallon Fuel 11/07/2017
018-205 Oil Day Tank License Renewal Justification
FS1-0037703-1.0 Summary of Evaluation Results of Degraded Baffle Bolting 5/3/2018
on HTP Fuel at Sequoyah Unit 1, RFO-22
G-55 General Engineering Specification for Technical and Rev. 24
Programmatic Requirements for the Protective Coating
Program for TVA Nuclear Plants
LTR-AMLR-18-30 Sequoyah Unit-1, Reactor Vessel Baffle Former Bolt 5/14/2018
(EDMS No. B88 Acceptable Bolting Pattern As-Found Real Time Analysis
180514 800) Summary
LTR-AMLR-18-72 Sequoyah Unit-2, Reactor Vessel Baffle Former Bolt 11/27/18
Ultrasonic Inspection Summary Report
PM-120115-SQN PM #120115 (Selective Leaching Inspections) Evaluation 07/23/2019
Sequoyah Unit 1 Thimble Tube Damage (Trending) Table , Cycle 16 thru 23 Oct. 2019
Cycle 23
Sequoyah Unit 2, Thimble Tube Damage (Trending) Table, Cycle 11 thru 22 Nov. 2019
Cycle 22
TVA065-REPT- TVA, Sequoyah nuclear Plant, Application of Component Rev. 0
2 Specific License Renewal Scoping Requirements to
Components with Level III Coatings
Miscellaneous 0-MI-EPM-079- Fuel Transfer Equipment Checkout (System 79) Rev. 28
049.0
0-MI-MRR-068- Sequoyah Nuclear Plant,Unit 1 & 2, Maintenance Instruction, Rev. 0065
005.0 Removal of Reactor Pressure Vessel Head and Attachments
0-MI-MRR-068- Sequoyah Nuclear Plant,Unit 1 & 2, Maintenance Instruction, Rev. 0057
006.0 Removal of Reactor Pressure Vessel Head and Attachments
0-MI-MXX-000- Routine Maintenance Involving Unistrut Clamps, Anchored Rev. 6
009.2 Connections, Instrument Bolting, and Miscellaneous Bolting
0-MI-MXX-068- Steam Generator Primary Side Maintenance Activities Rev. 0027
005.0
0-PI-DXI-000- ASME Section XI ISI/NDE Program, Unit 1 and Unit 2 Rev. 0002
Inspection Type Designation Description or Title Revision or
Procedure Date
114.4
0-PI-DXI-000- ASME Section XI IWE/IWL Containment Inservice Inspection Rev.0
116.3 (CISI) Program
0-PI-DXX-000- Insulated Component External Surfaces Inspection Rev. 0
100.06.1
0-PI-DXX-000- License Renewal Operating Experience (OE), Review Rev. 0000
100.37.1 Instruction
0-PI-DXX-000- Uninsulated Component External Surfaces Inspection Rev. 0
100.6.2
0-PI-DXX-000- License Renewal Operating Experience (OE) Review Rev. 0
37.1 Instruction
0-PI-DXX-000- MIC and Cavitation Degradation Monitoring Program Rev. 0008
704.1
0-PI-DXX-000- MIC and Cavitation Degradation Monitoring Program Rev. 0008
704.1
0-PI-DXX-000- Piping Inspection in Tunnels and Frequency Rev. 0
750
0-PI-NUC-000- Spent Fuel Pool Coupon Tree Surveillance Rev, 0000
009.0
0-SI-SXI-068- Sequoyah Nuclear Plant, Unit-0, Surveillance Instruction, 8/10/2018
114.4 Steam Generator Tubing Inservice Inspection and
Augmented Inspections
0-TI-DXI-000-115- ASME Section XI Repair and Replacement Program Rev. 10
0-TI-DXX-000- Flow Accelerated Corrosion Program Rev. 11
001.0
0-TI-DXX-000- Sequoyah Nuclear Plant, Unit-0, Technical Instruction, Rev. 0004
010.0 Protective Coatings Program
0-TI-DXX-000- Erosive Wear Degradation Monitoring Program Rev. 0002
016.0
0-TI-SXX-000- Program for Implementing NRC Generic Letter 89-13 Rev. 0007
146.0
0-TI-XXX-000- MIC AND Cavitation Degradation Monitoring Rev. 0009
704.0
Inspection Type Designation Description or Title Revision or
Procedure Date
0-TPP-DXX-00- License Renewal Aging Management Program Basis Rev. 0
100.22 Document One-Time Inspection Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.01 Document: Aboveground Metallic Tanks Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.02 Document: Bolting Integrity Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0
100.03 Document Buried and Underground Piping and Tanks
Inspection Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.04 Document: Compressed Air Monitoring Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.05 Document, Diesel Fuel Monitoring Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.06 Document: External Surface Monitoring Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.08 Document, Fire Protection Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.09 Document, Fire Water System Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.10 Document: Flow-Accelerated Corrosion Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.11 Document, Flux Thimble Tube Inspection Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.12 Document, Inservice Inspection - IWF Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev.0
100.13 Document Inspection of Overhead Heavy Load and Light
Load (Related to Refueling) Handling Systems Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.14 Document: Internal Surfaces in Miscellaneous Piping and
Ducting Components Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
Inspection Type Designation Description or Title Revision or
Procedure Date
100.15 Document: Metal Enclosed Bus Inspection Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.17 Document, Non-EQ Cable Connections
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev.0
100.18 Document Non-EQ Inaccessible Power Cables (400 V to 35
kV) Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.19 Document: Non-EQ Instrumentation Circuits Test Review
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.21 Document, Oil Analysis Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.23 Document: Small Bore Piping Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.24 Document: Periodic Surveillance and Preventative
Maintenance Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.25 Document: Protective Coating Monitoring and Maintenance
Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.26 Document, Reactor Head Closure Studs Program
0-TPP-DXX-000- Sequoyah Nuclear Plant, Unit 0, Technical Program Rev.0001
100.28 Procedures, License Renewal Aging Management Program
Basis Document ,Reactor Vessel Surveillance Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.29 Document: Selective Leaching Program
0-TPP-DXX-000- Sequoyah Nuclear Plant, Unit 0, License Renewal Aging Rev. 0000
100.30 Management Program Basis Document, Steam Generator
Integrity Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0
100.31 Document Structures Monitoring Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0001
100.32 Document: Thermal Renewal Aging Embrittlement of Cast
Austenitic Stainless Steel (CASS) Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
Inspection Type Designation Description or Title Revision or
Procedure Date
100.33 Document, Closed Treated Water Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev.0
100.35 Document Containment Inservice Inspection - IWE Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.36 Document: Inservice Inspection Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.38 Document Service Water Integrity Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev.0
100.41 Document Masonry Wall Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0
100.44 Document RG 1.127, Inspection of Water Control Structures
Associated with Nuclear Power Plants Program
0-TPP-DXX-000- License Renewal Aging Management Program Basis Rev. 0000
100.45 Document, 161-kV Oil-Filled Cable Program
1-PI-RVI-000- Sequoyah Nuclear Plant, Unit 1, Periodic Instruction, PWR Rev. 0000
301.0 Reactor Vessel Internals Inspection Program
17-EPG-999-201 Summary of Small Bore Piping One Time Inspection 12/28/2017
Program Inspections for SQN
17-EPG-999-202 Summary of Structures Monitoring Program Inspections 2/12/18
Required for SQN License Renewal Commitment
- 114456053 and #114456121
2-PI-RVI-000- Sequoyah Nuclear Plant, Unit 2, Periodic Instruction, PWR Rev.0000
301.0 Reactor Vessel Internals Inspection Program
3002006813 Materials Reliability Program: Examination of Small Bore Rev. 1
Socket Welds for Vibration and Thermal Fatigue
25399 Destructive Examination of Socket Weld Indications Rev. 1
51-9199524-000 Technical Justification for Demonstrating the Capabilities of Rev. 0
CRDM/CEDM Examination Procedures of Nozzle Bores with
Thermal Sleeve Centering Tab Wear
AMP 070.220, Sequoyah Flux Thimble Tube Inspection Program, Job 5/18/2015
LMS 50002384 Familiarization Guide
ASME Section XI, IWF-1300, Support and Examination Boundaries 2007
Subsection IWF,
Inspection Type Designation Description or Title Revision or
Procedure Date
Article IWF-1000
BP-257 Integrated Materials Issues Management Plan Rev. 0019
CTD 114454762 Commitment Tracking Database, to Revise Reactor Closure 3/29/2018
Studs Program Procedures
CXV645J Form 6 - Procurement Data Sheet, Plug, Tubing, Q Level: Rev. 0
QA 1, ASME SEC III: CLASS 1, Straight CEW Tube Plugs,
ASME SB-166 ALLOY 690, for Sequoyah Unit-1 & 2 Steam
Generators (RSG)
DOWG 16-01 Resource Manual for IP-ENG-001 for IP-ENG-001, Standard 11/12/2018
Design Process
Emp. ID No. Learning History Completion Records for AMP 070.220 Flux 7/24/2017
UJ86NTACG Thimble Tube
Inspection Program
ESP-070.531 BFN, SQN, WBN, Corporate Engineering Personnel, TPD- Rev. 30
ESP , Mentoring/Position Specific Guide, Raw Water
Corrosion Inspection
ESP070.234 BFN, SQN, WBN, Corporate Engineering Personnel, TPD- Rev. 28
ESP, Mentoring/Position Specific Guide, Protective Coating
Program Engineer
EWR No. 17- Summary of Fire Water System Program Inspections for Rev. 2
SBE-026-199 SQN License Renewal
EWR-17-EPG- SQN License Renewal Implementation One-Time inspection 9/19/17
317-171
G-29-P.S.4.M.4.4 ASME Section III and Non-ASME Section III (Including AISC, Rev. 7
ANSI, B31.1, and ANSI B31.5) Bolting Material
G-29B Material Fabrication and Handling Requirements for Rev. 26
P.S.4.M.1.1 Austenitic Stainless Steel
G-55 General Engineering Specification, Technical and Rev. 24
Programmatic Requirements for the Protective Coating
Program for TVA Nuclear Plants
L18 140519 800 Approval of Areva Procedure 54-UT-901-003, "Automated 05/19/2014
Ultrasonic Examination of Wear in RPV Closure Head
Inspection Type Designation Description or Title Revision or
Procedure Date
Thermal Sleeves"
LTR-CNL-15-095 Sequoyah Nuclear Plant - Revision to the Reactor Pressure 5/14/15
Vessel Surveillance Withdrawal Schedule For License
Renewal
LTR-RIDA-07-176 Thermal Sleeve Wear Evaluation for Sequoyah Unit 1 & 2 Rev. 1
and Watts Bar Unit 1
NCO 114446365 Commitment Tracking Database, Commitment Tracking 3/13/2018
Sheet to Revise Flux Tube Inspection Program
NPG-SPP-03.15 TVA NPG, Standard Programs and Processes Rev. 0002
Management, FSAR Management
NPG-SPP-06.2 TVA, NPG Standard Programs and Processes, Preventive Rev. 13
Maintenance
NPG-SPP-08.1 Nuclear Fuel Management, Att. 8, Spent Fuel Pool Neutron Rev. 0018
Absorber Material Monitoring Program
NPG-SPP-09.0.6 Conduct of Engineering Programs Rev. 0005
NPG-SPP-09.1 ASME Code and Augmented Programs Rev. 0010
NPG-SPP-09.1.5 ASME Section XI Containment ISI Program Rev.0
NPG-SPP-09.1.7 Steam Generator Program Rev. 0000
NPG-SPP-09.14 TVA, NPG Standard Programs and Processes Generic Rev. 0005
Letter (GL) 89-13 Implementation
NPG-SPP-09.15 Underground Piping and Tanks Integrity Program Rev. 8
NPG-SPP- TVA, NPG Standard Programs and Processes, PWR Rev. 0002
09.26.16 Reactor Vessel Internals Program
NPG-SPP- Pressurized Water Reactor Pressure Vessel Integrity Rev. 0004
09.26.19
NPG-SPP-09.7 Corrosion Control Program Rev. 0008
NPG-SPP-09.7.1 Corrosion Control - General, Localized and Galvanic, and Rev. 0004
Stress Corrosion Cracking Program
NPG-SPP-09.7.3 Raw Water Corrosion Program Rev. 0005
NPG-SPP-09.7.5 Erosion Program Rev.0000
NPG-SPP-17.2- Engineering Training Needs Analysis for Job Specific ESP's, 4/8/19
Inspection Type Designation Description or Title Revision or
Procedure Date
ESPO7O.234, ESPO7O.531 and EGT2O2.950
NPG-SPP-22.300 Corrective Action Program Rev. 0017
NRC Bulletin 88- Thimble Tube Thinning in Westinghouse Reactors 7/26/1988
NUREG-1339 Resolution of Generic Safety Issue 29, Bolting Degradation June 1990
or Failure in Nuclear Power Plants
PTLR-1 Sequoyah Unit-1, RCS Pressure Temperature Limit Report, 4/30/2018
Rev. 6, September 2017
PTLR-2 Sequoyah Unit 2, Pressure Temperature Limits Report, 4/30/18
Revision 7, September 2017
S10191029803 Diesel Fuel Monitoring Program Commitment Closure 08/15/2018
Package, Unit 2
SQN-1&2-FAC- SQN-1& 2 Susceptible Non-modeled Analysis for Flow 2
SNM Accelerated Corrosion
SQN-1&2-FAC- SQN-1&2 system Susceptibility Evaluation for Flow 1
SSE Accelerated Corrosion
SQN-1-ESE SQN-1 Erosion Susceptibility Evaluation (ESE) 0
SQN-2-ESE SQN-2 Erosion Susceptibility Evaluation (ESE) 0
TBA-TSP-18.802 Requirements for the Safe Operations Cranes Rev.19
TI-1 Elastomer and Polymer Aging Management Rev. 0000
TI-255 Sequoyah Nuclear Plant, Unit 0, Technical Instruction, Rev. 0006
Surveillance Program for Reactor Irradiation Specimens
TI-70 Cleanliness of Fluid Systems Rev. 0037
Tracking #: TVA PM Change/Deferral (Regulatory Impact Example) 7/22/19
1356623
TVA Letter CNL- Sequoyah Nuclear Plant, Revision to the Reactor Pressure 5/14/19
15-095 Vessel Surveillance Capsule Withdrawal Schedule for
TVA PM Inspect and clean After-cooler to Aux Control Air 7/22/2019
Change/Deferral Compressor A-
No.1356623 (Regulatory)
TVA065-REPT- Sample Plan Review, Non-EQ Cable Connections Program Rev. 3
Inspection Type Designation Description or Title Revision or
Procedure Date
054
UFSAR Table Mechanical Property Data for the Closure Head Bolting SQN-25
5.2.4-1 Material of the Sequoyah Unit 1 and 2 Reactor Vessel
USNRC Reg, Materials and Inspection for Reactor Vessel Closure Studs Rev.1
Guide 1.65
NDE Reports 180-9250039-000 Sequoyah SQN2-R20, Reactor Vessel Internals Visual
Examinations
EDMS #: L18 In-Service Inspection Report No. R-0189, Eddy Current April 2018
180410 800 Examination Report, In-core Flux Thimble Tubes, Sequoyah
Nuclear Plant Unit 1, Cycle 22
R0066 Record of Reactor Vessel Examination 04/20/2015
Procedures 0-MI-ECR-079- Spent Fuel Bridge Crane Periodic Inspection Rev. 19
095
0-MI-ECR-079- Manipulator Crane Checkout Rev. 15
930.0
0-MI-ECR-303- Reactor Building (Polar) Crane Periodic Inspection Rev.21
911.0
0-MI-ECR-303- Auxiliary Building Crane Periodic Inspection Rev.2
21.0
0-MI-MIN-000- Cleanliness of Fluid Systems for Maintenance Activities Rev. 0015
070.0
0-MI-MRR-068- Removal of Reactor Pressure Vessel Head and Attachments Rev. 0065
005.0
0-MI-MRR-068- Installation Of Reactor Pressure Vessel Head And Rev. 57
006.0 Attachments
0-MI-MXX-068- Steam Generator Primary Side Maintenance Activities 3/22/2019
005.0
0-PI-CEM-000- Ground Water Monitoring for License Renewal Rev. 1
010.5
0-PI-CEM-082- Standby Diesel Generator Starting Air Quality Test Rev. 0000
001.0
0-PI-DXX-000- Buried and Underground Tanks Inspection Rev.3
100.03.1
0-PI-DXX-000- Periodic Rectifier Monitoring Rev.0
Inspection Type Designation Description or Title Revision or
Procedure Date
100.03.2
0-PI-DXX-000- Periodic InTellusCRM Monitoring Rev.0
100.03.3
0-PI-DXX-000- Annual Cathodic Protection Survey Rev.0
100.03.4
0-PI-DXX-000- Environmentally Assisted Fatigue Monitoring Rev. 0000
100.07.1
0-PI-DXX-000- Internal Surfaces in Miscellaneous Piping and Ducting Rev. 0002
100.14.1 Components Program Inspections
0-PI-DXX-000- Oil Analysis Inspection, 161 kV Oil-Filled Cables Rev. 0001
100.21.1
0-PI-DXX-000- Structures Monitoring for Maintenance Rule and License Rev. 2
100.31.1 Renewal
0-PI-DXX-000- Water Chemistry Control - Closed Treated Water Inspection Rev. 0003
100.33.1
0-PI-DXX-000- Boric Acid Leak Monitoring Program 4
105
0-PI-DXX-090- Radiation Monitor Test Data Review Rev. 0000
000.0
0-PI-ENV-000- Inspection of Ponds, Channels, Dikes, and Water Control Rev. 2
2.0 Structures
0-PI-MIN-032- Visual Inspection of the Turbine Building Control Air System Rev. 0002
001.0
0-PI-MIN-032- Visual Inspection of Surface Conditions in the Auxiliary Rev. 0001
2.0 Control Air System
0-PI-MIN-082- Inspection of Surface Conditions in the Diesel Starting Air Rev. 0005
001.0 Subsystem
0-PI-NXX-094- Sequoyah Nuclear Plant, Unit-0, In-Core Seal Table Rev. 0043
001.0 Rev. Maintenance
0043
0-PI-SFT-067- ERCW Train "A", Manipulation for Plant Activities Rev. 0008
003.A
0-PI-SFT-070- Performance Testing of Component Cooling Heat Rev. 0015
2.0 Exchangers OB1, OB2
Inspection Type Designation Description or Title Revision or
Procedure Date
0-SI-FPU-302- Fire Barrier Visual Inspection - Auxiliary Building and Control Rev. 0015
001.R Building
0-SI-FPU-302- Fire Barrier Visual Inspection - Diesel Generator Building, Rev. 0009
004.R ERCW Pumping Station and HPFP Pump House
0-SI-FPU-302- Fire Barrier Visual Inspection - ERCW Manholes and Rev. 0009
005.R Handholes
0-SI-FPU-302- Visual Inspection of Electrical Raceway Fire Barrier Systems Rev. 0017
007.R
0-SI-FPU-410- Inspection of Reactor Building Airlocks and Blast Doors, Unit Rev. 0009
2.R 2 Radiant Energy Shield and Unit 1 Accumulator Room 1
Floor
0-SI-MIN-302- Testing of the Divider Barrier Seal Rev. 0010
239.0
0-SI-NXX-000- Monitoring Component Cyclic or Transient Limits Rev. 0027
009
0-TI-CEM-032- Turbine Building Control Air Quality Test Rev. 0002
001.0
0-TI-CEM-032- Auxiliary Building Control Air Quality Test Rev. 0002
2.0
0-TI-DXX-000- Protective Coatings Program Rev. 0004
010.0
0-TI-SPT-000- ASME Section XI Pressure Testing Program Basis 9
301.0 Document
1-AR-M15-B Miscellaneous 1-XA-55-15B (Annunciator Response) Rev. 0045
1-PI-IXX-092- Nuclear Instrumentation Power Range Cable Testing Rev. 0001
2.0
1-SI-FPU-302- Fire Barrier Visual Inspection - Unit 1 Reactor Building Shield Rev. 0008
001.R Wall
2-PI-IXX-092- Nuclear Instrumentation Power Range Cable Testing Rev. 0001
2.0
2-SI-FPU-302- Fire Barrier Visual Inspection - Auxiliary Building Rev. 0003
2.R
54-ISI-603-007 Automated Ultrasonic Examination of RPV Closure Head 7
Penetrations Containing Thermal Sleeves
Inspection Type Designation Description or Title Revision or
Procedure Date
54-UT-901-003 Automated Ultrasonic Examination of Wear in RPV Closure 3
Head Thermal Sleeves
DS-M4.2.1 Flow Accelerated Corrosion Program Methods 10
HSP-209 Physical Properties Measurement Procedure for Aluminum Rev. 1
Based Neutron Absorber Surveillance Coupons
M&AI-5.3 Application and Repair of Protective Coatings Rev. 0016
M&AI-9.1 Bolted Structural Connections (A-307, A-325 and A-490) 8
M&AI-9.2 Bolted Connections for Unistrut Clamps, Anchor Bolts, 16
Instrument Bolting, and Miscellaneous Bolting
M&AI-9.3 Pipe Clamps for Snubbers/Struts and Associated Bolting 8
MMTP-104 Guidelines And Methodology For Assembling And 10
Tensioning Threaded Connections
N-VT-1 Visual Examination Procedure for ASME Section XI Rev. 0048
Preservice and Inservice Non-Destructive Examination
N-VT-22 Visual Examination Procedure for License Renewal Rev. 0001
Programs
N-VT-8 Remote Visual Examination of PWR Vessel Interiors and 14
Core Support Structures
NEDP-21.0.2 License Renewal Activities Prior to Period of Extended 1
Operation
NEDP-21.0.3 License Renewal Implementation During the Period of 1
Extended Operation (PEO)
NFDP-111 Nuclear Design and Core Analysis, MRP-227 Assumptions, Rev. 0004
Ref. 6.2 FFF
NPG-SPP-03.3 NRC Commitment Management Rev. 0007
NPG-SPP-06.9.2 Surveillance Test Program 9
NPG-SPP-09.0 Conduct of Engineering 10
NPG-SPP-09.1 Conduct of System Engineering and Equipment Reliability 6
NPG-SPP-09.1.1 System Monitoring and Trending 2
NPG-SPP-09.7 Corrosion Control Program 7
NPG-SPP-09.7.1 Corrosion Control - General, Localized and Galvanic, and 3
Stress Corrosion Cracking Program
NPG-SPP-09.7.2 Flow Accelerated Corrosion Control Program 4
Inspection Type Designation Description or Title Revision or
Procedure Date
NPG-SPP-09.7.4 Boric Acid Corrosion Control Program 5
NPG-SPP-09.7.5 Erosion Program 0
NPG-SPP-22.500 Operating Experience Program 10
NPG-SPP-6.2 Preventive Maintenance 13
TVA-NQA- Nuclear Quality Assurance Plan (NQAP) 37
PLN89-A
Self-Assessments W50191107003 Review of SQN Plant Documents for the Identification of 11/06/2019
Newly Identified Systems, Structures, and Components as
required by 10 CFR 54.37(b)
W51071031001 Review of SQN Plant Documents for the Identification of 08/21/2017
Newly Identified Systems, Structures, and Components as
required by 10 CFR 54.37(b)
Work Orders All Work Orders 114073526, 115364783, 115453612, 116593467,
116880207, 117080857, 117968680, 117977989,
118121028, 118132638, 118193768, 118611647,
118611657, 118611668, 119169548, 119991743,
20158600
Preventative P1300, P7704, P7772, P7773, P7786, P7907
Maintenance
Tasks (4 digit P-
Number)
Preventative 16385, 74433, 74436, 74444, 74447, 78325
Maintenance
Tasks (5 digit PM
Number)
Preventative 112883, 120398, 120399, 120446, 120478, 120749, 126922,
Maintenance 126923, 126924
Tasks (6-digit PM
Number)
Preventative 014500000, 014510000, 014880001, 014880002,
Maintenance 014880003, 018160000, 030330000, 050201000,
Tasks (9 digit PM 050202000, 058370000, 056860004, 056860005,
Number) 056860006, 056860007, 058780001, 058780002,
058780005, 058780006, 058780007, 062950001,
Inspection Type Designation Description or Title Revision or
Procedure Date
063040001, 063601499, 063604819, 063604820,
063604821, 063604822, 063605536, 063605537,
063605538, 063605648, , 800170889, 800170966,
800170967, 800170978, 800170980, 800170981,
800170983, 800170988, 800170989
26