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
March 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:
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
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 Fuel Oil Monitoring Program 71003 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 Surfaces Monitoring Program 71003 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 Preventative Surveillance and Preventative Maintenance Program 71003 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 Chemistry Control - Closed Treated Water Systems Program 71003 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
Procedure
Type
Designation
Description or Title
Revision or
Date
71003
Calculations
CEB-GEN-
88PR01
Pipe Rupture Evaluation of Wear on Thimble Tubes and
Acceptance Criteria
Rev. 2
CN-MRCDA-08-2
CRDM Head Adapter Wear Justification
Rev. 1
SI File No.
1901378.301
Evaluation of Observed Thinning within 30x24 ERCW
Branch Piping Tee
11/26/2019
Corrective Action
Documents
Condition Reports
16684, 684461, 684468, 810761, 991942, 993922, 1236019,
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
Changes
28-31
SAR Change Package: Revise PSPM Program to Replace
Diesel Generator Starting Air Aluminum Valves rather than
Inspect
7-16-18
EWR No.18-EPG-
067-199
Summary of Flow Accelerated Corrosion / Erosoin Program
insepction for SQN License Renewal Commitments
114446167 & 114446284 in accordance with NPG-SPP-09.0
Section 3.2.9C.
9/29/18
PMSICHG-SQN-
TICKET-1281317
TVA PM Change/Deferral: PM #120115 (Selective Leaching
Inspections)
07/22/2019
Engineering
Evaluations
1400627.401
Flaw Tolerance Evaluation of Sequoyah Units 1 and 2 CASS
Components
Rev. 1
1400627.403
Development of a CASS Aging Management Program for
Sequoyah Unit 1 & 2
Rev. 1
CN-RIDA-12-39
Sequoyah Units 1 & 2 Lower Internals Hold Down Capacity
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Evaluation For Hold-down Spring Height Measurement
CN-RIDA-18-7
Sequoyah Units 1 & 2, Lower Internals Hold-Down Spring
Capability Evaluation for Fuel Transition
7/26/18
EWR No. 17-SIE-
018-205
SQN Emergency Diesel Generator (EDG) 550 Gallon Fuel
Oil Day Tank License Renewal Justification
11/07/2017
FS1-0037703-1.0
Summary of Evaluation Results of Degraded Baffle Bolting
on HTP Fuel at Sequoyah Unit 1, RFO-22
5/3/2018
G-55
General Engineering Specification for Technical and
Programmatic Requirements for the Protective Coating
Program for TVA Nuclear Plants
Rev. 24
LTR-AMLR-18-30
(EDMS No. B88
180514 800)
Sequoyah Unit-1, Reactor Vessel Baffle Former Bolt
Acceptable Bolting Pattern As-Found Real Time Analysis
Summary
5/14/2018
LTR-AMLR-18-72
Sequoyah Unit-2, Reactor Vessel Baffle Former Bolt
Ultrasonic Inspection Summary Report
11/27/18
PM-120115-SQN
PM #120115 (Selective Leaching Inspections) Evaluation
07/23/2019
Sequoyah Unit 1
Cycle 23
Thimble Tube Damage (Trending) Table, Cycle 16 thru 23
Oct. 2019
Sequoyah Unit 2,
Cycle 22
Thimble Tube Damage (Trending) Table, Cycle 11 thru 22
Nov. 2019
TVA065-REPT-
2
TVA, Sequoyah nuclear Plant, Application of Component
Specific License Renewal Scoping Requirements to
Components with Level III Coatings
Rev. 0
Miscellaneous
0-MI-EPM-079-
049.0
Fuel Transfer Equipment Checkout (System 79)
Rev. 28
0-MI-MRR-068-
005.0
Sequoyah Nuclear Plant,Unit 1 & 2, Maintenance Instruction,
Removal of Reactor Pressure Vessel Head and Attachments
Rev. 0065
0-MI-MRR-068-
006.0
Sequoyah Nuclear Plant,Unit 1 & 2, Maintenance Instruction,
Removal of Reactor Pressure Vessel Head and Attachments
Rev. 0057
0-MI-MXX-000-
009.2
Routine Maintenance Involving Unistrut Clamps, Anchored
Connections, Instrument Bolting, and Miscellaneous Bolting
Rev. 6
0-MI-MXX-068-
005.0
Steam Generator Primary Side Maintenance Activities
Rev. 0027
0-PI-DXI-000-
ASME Section XI ISI/NDE Program, Unit 1 and Unit 2
Rev. 0002
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
114.4
0-PI-DXI-000-
116.3
ASME Section XI IWE/IWL Containment Inservice Inspection
(CISI) Program
Rev.0
0-PI-DXX-000-
100.06.1
Insulated Component External Surfaces Inspection
Rev. 0
0-PI-DXX-000-
100.37.1
License Renewal Operating Experience (OE), Review
Instruction
Rev. 0000
0-PI-DXX-000-
100.6.2
Uninsulated Component External Surfaces Inspection
Rev. 0
0-PI-DXX-000-
37.1
License Renewal Operating Experience (OE) Review
Instruction
Rev. 0
0-PI-DXX-000-
704.1
MIC and Cavitation Degradation Monitoring Program
Rev. 0008
0-PI-DXX-000-
704.1
MIC and Cavitation Degradation Monitoring Program
Rev. 0008
0-PI-DXX-000-
750
Piping Inspection in Tunnels and Frequency
Rev. 0
0-PI-NUC-000-
009.0
Spent Fuel Pool Coupon Tree Surveillance
Rev, 0000
0-SI-SXI-068-
114.4
Sequoyah Nuclear Plant, Unit-0, Surveillance Instruction,
Steam Generator Tubing Inservice Inspection and
Augmented Inspections
8/10/2018
0-TI-DXI-000-115-
ASME Section XI Repair and Replacement Program
Rev. 10
0-TI-DXX-000-
001.0
Flow Accelerated Corrosion Program
Rev. 11
0-TI-DXX-000-
010.0
Sequoyah Nuclear Plant, Unit-0, Technical Instruction,
Protective Coatings Program
Rev. 0004
0-TI-DXX-000-
016.0
Erosive Wear Degradation Monitoring Program
Rev. 0002
0-TI-SXX-000-
146.0
Program for Implementing NRC Generic Letter 89-13
Rev. 0007
0-TI-XXX-000-
704.0
MIC AND Cavitation Degradation Monitoring
Rev. 0009
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-TPP-DXX-00-
100.22
License Renewal Aging Management Program Basis
Document One-Time Inspection Program
Rev. 0
0-TPP-DXX-000-
100.01
License Renewal Aging Management Program Basis
Document: Aboveground Metallic Tanks Program
Rev. 0000
0-TPP-DXX-000-
100.02
License Renewal Aging Management Program Basis
Document: Bolting Integrity Program
Rev. 0000
0-TPP-DXX-000-
100.03
License Renewal Aging Management Program Basis
Document Buried and Underground Piping and Tanks
Inspection Program
Rev. 0
0-TPP-DXX-000-
100.04
License Renewal Aging Management Program Basis
Document: Compressed Air Monitoring Program
Rev. 0001
0-TPP-DXX-000-
100.05
License Renewal Aging Management Program Basis
Document, Diesel Fuel Monitoring Program
Rev. 0000
0-TPP-DXX-000-
100.06
License Renewal Aging Management Program Basis
Document: External Surface Monitoring Program
Rev. 0001
0-TPP-DXX-000-
100.08
License Renewal Aging Management Program Basis
Document, Fire Protection Program
Rev. 0001
0-TPP-DXX-000-
100.09
License Renewal Aging Management Program Basis
Document, Fire Water System Program
Rev. 0000
0-TPP-DXX-000-
100.10
License Renewal Aging Management Program Basis
Document: Flow-Accelerated Corrosion Program
Rev. 0000
0-TPP-DXX-000-
100.11
License Renewal Aging Management Program Basis
Document, Flux Thimble Tube Inspection Program
Rev. 0001
0-TPP-DXX-000-
100.12
License Renewal Aging Management Program Basis
Document, Inservice Inspection - IWF Program
Rev. 0001
0-TPP-DXX-000-
100.13
License Renewal Aging Management Program Basis
Document Inspection of Overhead Heavy Load and Light
Load (Related to Refueling) Handling Systems Program
Rev.0
0-TPP-DXX-000-
100.14
License Renewal Aging Management Program Basis
Document: Internal Surfaces in Miscellaneous Piping and
Ducting Components Program
Rev. 0000
0-TPP-DXX-000-
License Renewal Aging Management Program Basis
Rev. 0001
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
100.15
Document: Metal Enclosed Bus Inspection Program
0-TPP-DXX-000-
100.17
License Renewal Aging Management Program Basis
Document, Non-EQ Cable Connections
Rev. 0000
0-TPP-DXX-000-
100.18
License Renewal Aging Management Program Basis
Document Non-EQ Inaccessible Power Cables (400 V to 35
kV) Program
Rev.0
0-TPP-DXX-000-
100.19
License Renewal Aging Management Program Basis
Document: Non-EQ Instrumentation Circuits Test Review
Rev. 0001
0-TPP-DXX-000-
100.21
License Renewal Aging Management Program Basis
Document, Oil Analysis Program
Rev. 0001
0-TPP-DXX-000-
100.23
License Renewal Aging Management Program Basis
Document: Small Bore Piping Program
Rev. 0000
0-TPP-DXX-000-
100.24
License Renewal Aging Management Program Basis
Document: Periodic Surveillance and Preventative
Maintenance Program
Rev. 0000
0-TPP-DXX-000-
100.25
License Renewal Aging Management Program Basis
Document: Protective Coating Monitoring and Maintenance
Program
Rev. 0001
0-TPP-DXX-000-
100.26
License Renewal Aging Management Program Basis
Document, Reactor Head Closure Studs Program
Rev. 0000
0-TPP-DXX-000-
100.28
Sequoyah Nuclear Plant, Unit 0, Technical Program
Procedures, License Renewal Aging Management Program
Basis Document,Reactor Vessel Surveillance Program
Rev.0001
0-TPP-DXX-000-
100.29
License Renewal Aging Management Program Basis
Document: Selective Leaching Program
Rev. 0001
0-TPP-DXX-000-
100.30
Sequoyah Nuclear Plant, Unit 0, License Renewal Aging
Management Program Basis Document, Steam Generator
Integrity Program
Rev. 0000
0-TPP-DXX-000-
100.31
License Renewal Aging Management Program Basis
Document Structures Monitoring Program
Rev. 0
0-TPP-DXX-000-
100.32
License Renewal Aging Management Program Basis
Document: Thermal Renewal Aging Embrittlement of Cast
Austenitic Stainless Steel (CASS) Program
Rev. 0001
0-TPP-DXX-000-
License Renewal Aging Management Program Basis
Rev. 0000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
100.33
Document, Closed Treated Water Program
0-TPP-DXX-000-
100.35
License Renewal Aging Management Program Basis
Document Containment Inservice Inspection - IWE Program
Rev.0
0-TPP-DXX-000-
100.36
License Renewal Aging Management Program Basis
Document: Inservice Inspection Program
Rev. 0000
0-TPP-DXX-000-
100.38
License Renewal Aging Management Program Basis
Document Service Water Integrity Program
Rev. 0000
0-TPP-DXX-000-
100.41
License Renewal Aging Management Program Basis
Document Masonry Wall Program
Rev.0
0-TPP-DXX-000-
100.44
License Renewal Aging Management Program Basis
Document RG 1.127, Inspection of Water Control Structures
Associated with Nuclear Power Plants Program
Rev. 0
0-TPP-DXX-000-
100.45
License Renewal Aging Management Program Basis
Document, 161-kV Oil-Filled Cable Program
Rev. 0000
1-PI-RVI-000-
301.0
Sequoyah Nuclear Plant, Unit 1, Periodic Instruction, PWR
Reactor Vessel Internals Inspection Program
Rev. 0000
17-EPG-999-201
Summary of Small Bore Piping One Time Inspection
Program Inspections for SQN
2/28/2017
17-EPG-999-202
Summary of Structures Monitoring Program Inspections
Required for SQN License Renewal Commitment
- 114456053 and #114456121
2/12/18
2-PI-RVI-000-
301.0
Sequoyah Nuclear Plant, Unit 2, Periodic Instruction, PWR
Reactor Vessel Internals Inspection Program
Rev.0000
3002006813
Materials Reliability Program: Examination of Small Bore
Socket Welds for Vibration and Thermal Fatigue
Rev. 1
25399
Destructive Examination of Socket Weld Indications
Rev. 1
51-9199524-000
Technical Justification for Demonstrating the Capabilities of
CRDM/CEDM Examination Procedures of Nozzle Bores with
Thermal Sleeve Centering Tab Wear
Rev. 0
AMP 070.220,
LMS 50002384
Sequoyah Flux Thimble Tube Inspection Program, Job
Familiarization Guide
5/18/2015
Subsection IWF,
IWF-1300, Support and Examination Boundaries
2007
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Article IWF-1000
BP-257
Integrated Materials Issues Management Plan
Rev. 0019
CTD 114454762
Commitment Tracking Database, to Revise Reactor Closure
Studs Program Procedures
3/29/2018
CXV645J
Form 6 - Procurement Data Sheet, Plug, Tubing, Q Level:
QA 1, ASME SEC III: CLASS 1, Straight CEW Tube Plugs,
ASME SB-166 ALLOY 690, for Sequoyah Unit-1 & 2 Steam
Generators (RSG)
Rev. 0
DOWG 16-01
Resource Manual for IP-ENG-001 for IP-ENG-001, Standard
Design Process
11/12/2018
Emp. ID No.
UJ86NTACG
Learning History Completion Records for AMP 070.220 Flux
Thimble Tube
Inspection Program
7/24/2017
BFN, SQN, WBN, Corporate Engineering Personnel, TPD-
ESP, Mentoring/Position Specific Guide, Raw Water
Corrosion Inspection
Rev. 30
ESP070.234
BFN, SQN, WBN, Corporate Engineering Personnel, TPD-
ESP, Mentoring/Position Specific Guide, Protective Coating
Program Engineer
Rev. 28
EWR No. 17-
SBE-026-199
Summary of Fire Water System Program Inspections for
Rev. 2
EWR-17-EPG-
317-171
SQN License Renewal Implementation One-Time inspection
9/19/17
G-29-P.S.4.M.4.4
ASME Section III and Non-ASME Section III (Including AISC,
ANSI, B31.1, and ANSI B31.5) Bolting Material
Rev. 7
G-29B
P.S.4.M.1.1
Material Fabrication and Handling Requirements for
Austenitic Stainless Steel
Rev. 26
G-55
General Engineering Specification, Technical and
Programmatic Requirements for the Protective Coating
Program for TVA Nuclear Plants
Rev. 24
L18 140519 800
Approval of Areva Procedure 54-UT-901-003, "Automated
Ultrasonic Examination of Wear in RPV Closure Head
05/19/2014
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Thermal Sleeves"
LTR-CNL-15-095
Sequoyah Nuclear Plant - Revision to the Reactor Pressure
Vessel Surveillance Withdrawal Schedule For License
Renewal
5/14/15
LTR-RIDA-07-176 Thermal Sleeve Wear Evaluation for Sequoyah Unit 1 & 2
and Watts Bar Unit 1
Rev. 1
NCO 114446365
Commitment Tracking Database, Commitment Tracking
Sheet to Revise Flux Tube Inspection Program
3/13/2018
NPG-SPP-03.15
TVA NPG, Standard Programs and Processes
Management, FSAR Management
Rev. 0002
NPG-SPP-06.2
TVA, NPG Standard Programs and Processes, Preventive
Maintenance
Rev. 13
NPG-SPP-08.1
Nuclear Fuel Management, Att. 8, Spent Fuel Pool Neutron
Absorber Material Monitoring Program
Rev. 0018
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 Letter (GL) 89-13 Implementation
Rev. 0005
NPG-SPP-09.15
Underground Piping and Tanks Integrity Program
Rev. 8
NPG-SPP-
09.26.16
TVA, NPG Standard Programs and Processes, PWR
Reactor Vessel Internals Program
Rev. 0002
NPG-SPP-
09.26.19
Pressurized Water Reactor Pressure Vessel Integrity
Rev. 0004
NPG-SPP-09.7
Corrosion Control Program
Rev. 0008
NPG-SPP-09.7.1
Corrosion Control - General, Localized and Galvanic, and
Stress Corrosion Cracking Program
Rev. 0004
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
Procedure
Type
Designation
Description or Title
Revision or
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
Resolution of Generic Safety Issue 29, Bolting Degradation
or Failure in Nuclear Power Plants
June 1990
PTLR-1
Sequoyah Unit-1, RCS Pressure Temperature Limit Report,
Rev. 6, September 2017
4/30/2018
PTLR-2
Sequoyah Unit 2, Pressure Temperature Limits Report,
Revision 7, September 2017
4/30/18
S10191029803
Diesel Fuel Monitoring Program Commitment Closure
Package, Unit 2
08/15/2018
SQN-1&2-FAC-
SQN-1& 2 Susceptible Non-modeled Analysis for Flow
Accelerated Corrosion
SQN-1&2-FAC-
SQN-1&2 system Susceptibility Evaluation for Flow
Accelerated Corrosion
SQN-1-ESE
SQN-1 Erosion Susceptibility Evaluation (ESE)
SQN-2-ESE
SQN-2 Erosion Susceptibility Evaluation (ESE)
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,
Surveillance Program for Reactor Irradiation Specimens
Rev. 0006
TI-70
Cleanliness of Fluid Systems
Rev. 0037
Tracking #:
1356623
TVA PM Change/Deferral (Regulatory Impact Example)
7/22/19
TVA Letter CNL-
15-095
Sequoyah Nuclear Plant, Revision to the Reactor Pressure
Vessel Surveillance Capsule Withdrawal Schedule for
5/14/19
Change/Deferral
No.1356623
Inspect and clean After-cooler to Aux Control Air
Compressor A-
(Regulatory)
7/22/2019
TVA065-REPT-
Sample Plan Review, Non-EQ Cable Connections Program
Rev. 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
054
UFSAR Table
5.2.4-1
Mechanical Property Data for the Closure Head Bolting
Material of the Sequoyah Unit 1 and 2 Reactor Vessel
SQN-25
USNRC Reg,
Guide 1.65
Materials and Inspection for Reactor Vessel Closure Studs
Rev.1
NDE Reports
180-9250039-000
Sequoyah SQN2-R20, Reactor Vessel Internals Visual
Examinations
EDMS #: L18
180410 800
In-Service Inspection Report No. R-0189, Eddy Current
Examination Report, In-core Flux Thimble Tubes, Sequoyah
Nuclear Plant Unit 1, Cycle 22
April 2018
R0066
Record of Reactor Vessel Examination
04/20/2015
Procedures
0-MI-ECR-079-
095
Spent Fuel Bridge Crane Periodic Inspection
Rev. 19
0-MI-ECR-079-
930.0
Manipulator Crane Checkout
Rev. 15
0-MI-ECR-303-
911.0
Reactor Building (Polar) Crane Periodic Inspection
Rev.21
0-MI-ECR-303-
21.0
Auxiliary Building Crane Periodic Inspection
Rev.2
0-MI-MIN-000-
070.0
Cleanliness of Fluid Systems for Maintenance Activities
Rev. 0015
0-MI-MRR-068-
005.0
Removal of Reactor Pressure Vessel Head and Attachments
Rev. 0065
0-MI-MRR-068-
006.0
Installation Of Reactor Pressure Vessel Head And
Attachments
Rev. 57
0-MI-MXX-068-
005.0
Steam Generator Primary Side Maintenance Activities
3/22/2019
0-PI-CEM-000-
010.5
Ground Water Monitoring for License Renewal
Rev. 1
0-PI-CEM-082-
001.0
Standby Diesel Generator Starting Air Quality Test
Rev. 0000
0-PI-DXX-000-
100.03.1
Buried and Underground Tanks Inspection
Rev.3
0-PI-DXX-000-
Periodic Rectifier Monitoring
Rev.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
100.03.2
0-PI-DXX-000-
100.03.3
Periodic InTellusCRM Monitoring
Rev.0
0-PI-DXX-000-
100.03.4
Annual Cathodic Protection Survey
Rev.0
0-PI-DXX-000-
100.07.1
Environmentally Assisted Fatigue Monitoring
Rev. 0000
0-PI-DXX-000-
100.14.1
Internal Surfaces in Miscellaneous Piping and Ducting
Components Program Inspections
Rev. 0002
0-PI-DXX-000-
100.21.1
Oil Analysis Inspection, 161 kV Oil-Filled Cables
Rev. 0001
0-PI-DXX-000-
100.31.1
Structures Monitoring for Maintenance Rule and License
Renewal
Rev. 2
0-PI-DXX-000-
100.33.1
Water Chemistry Control - Closed Treated Water Inspection
Rev. 0003
0-PI-DXX-000-
105
Boric Acid Leak Monitoring Program
0-PI-DXX-090-
000.0
Radiation Monitor Test Data Review
Rev. 0000
0-PI-ENV-000-
2.0
Inspection of Ponds, Channels, Dikes, and Water Control
Structures
Rev. 2
0-PI-MIN-032-
001.0
Visual Inspection of the Turbine Building Control Air System
Rev. 0002
0-PI-MIN-032-
2.0
Visual Inspection of Surface Conditions in the Auxiliary
Control Air System
Rev. 0001
0-PI-MIN-082-
001.0
Inspection of Surface Conditions in the Diesel Starting Air
Subsystem
Rev. 0005
0-PI-NXX-094-
001.0 Rev.
0043
Sequoyah Nuclear Plant, Unit-0, In-Core Seal Table
Maintenance
Rev. 0043
0-PI-SFT-067-
003.A
ERCW Train "A", Manipulation for Plant Activities
Rev. 0008
0-PI-SFT-070-
2.0
Performance Testing of Component Cooling Heat
Exchangers OB1, OB2
Rev. 0015
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-SI-FPU-302-
001.R
Fire Barrier Visual Inspection - Auxiliary Building and Control
Building
Rev. 0015
0-SI-FPU-302-
004.R
Fire Barrier Visual Inspection - Diesel Generator Building,
ERCW Pumping Station and HPFP Pump House
Rev. 0009
0-SI-FPU-302-
005.R
Fire Barrier Visual Inspection - ERCW Manholes and
Handholes
Rev. 0009
0-SI-FPU-302-
007.R
Visual Inspection of Electrical Raceway Fire Barrier Systems
Rev. 0017
0-SI-FPU-410-
2.R
Inspection of Reactor Building Airlocks and Blast Doors, Unit
Radiant Energy Shield and Unit 1 Accumulator Room 1
Floor
Rev. 0009
0-SI-MIN-302-
239.0
Testing of the Divider Barrier Seal
Rev. 0010
0-SI-NXX-000-
009
Monitoring Component Cyclic or Transient Limits
Rev. 0027
0-TI-CEM-032-
001.0
Turbine Building Control Air Quality Test
Rev. 0002
0-TI-CEM-032-
2.0
Auxiliary Building Control Air Quality Test
Rev. 0002
0-TI-DXX-000-
010.0
Protective Coatings Program
Rev. 0004
0-TI-SPT-000-
301.0
ASME Section XI Pressure Testing Program Basis
Document
1-AR-M15-B
Miscellaneous 1-XA-55-15B (Annunciator Response)
Rev. 0045
1-PI-IXX-092-
2.0
Nuclear Instrumentation Power Range Cable Testing
Rev. 0001
1-SI-FPU-302-
001.R
Fire Barrier Visual Inspection - Unit 1 Reactor Building Shield
Wall
Rev. 0008
2-PI-IXX-092-
2.0
Nuclear Instrumentation Power Range Cable Testing
Rev. 0001
2-SI-FPU-302-
2.R
Fire Barrier Visual Inspection - Auxiliary Building
Rev. 0003
54-ISI-603-007
Automated Ultrasonic Examination of RPV Closure Head
Penetrations Containing Thermal Sleeves
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
54-UT-901-003
Automated Ultrasonic Examination of Wear in RPV Closure
Head Thermal Sleeves
DS-M4.2.1
Flow Accelerated Corrosion Program Methods
HSP-209
Physical Properties Measurement Procedure for Aluminum
Based Neutron Absorber Surveillance Coupons
Rev. 1
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)
M&AI-9.2
Bolted Connections for Unistrut Clamps, Anchor Bolts,
Instrument Bolting, and Miscellaneous Bolting
M&AI-9.3
Pipe Clamps for Snubbers/Struts and Associated Bolting
MMTP-104
Guidelines And Methodology For Assembling And
Tensioning Threaded Connections
N-VT-1
Visual Examination Procedure for ASME Section XI
Preservice and Inservice Non-Destructive Examination
Rev. 0048
N-VT-22
Visual Examination Procedure for License Renewal
Programs
Rev. 0001
N-VT-8
Remote Visual Examination of PWR Vessel Interiors and
Core Support Structures
NEDP-21.0.2
License Renewal Activities Prior to Period of Extended
Operation
NEDP-21.0.3
License Renewal Implementation During the Period of
Extended Operation (PEO)
NFDP-111
Nuclear Design and Core Analysis, MRP-227 Assumptions,
Ref. 6.2 FFF
Rev. 0004
NPG-SPP-03.3
NRC Commitment Management
Rev. 0007
NPG-SPP-06.9.2
Surveillance Test Program
NPG-SPP-09.0
Conduct of Engineering
NPG-SPP-09.1
Conduct of System Engineering and Equipment Reliability
NPG-SPP-09.1.1
System Monitoring and Trending
NPG-SPP-09.7
Corrosion Control Program
NPG-SPP-09.7.1
Corrosion Control - General, Localized and Galvanic, and
Stress Corrosion Cracking Program
NPG-SPP-09.7.2
Flow Accelerated Corrosion Control Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NPG-SPP-09.7.4
Boric Acid Corrosion Control Program
NPG-SPP-09.7.5
Erosion Program
NPG-SPP-22.500
Operating Experience Program
NPG-SPP-6.2
Preventive Maintenance
TVA-NQA-
PLN89-A
Nuclear Quality Assurance Plan (NQAP)
Self-Assessments W50191107003
Review of SQN Plant Documents for the Identification of
Newly Identified Systems, Structures, and Components as
required by 10 CFR 54.37(b)
11/06/2019
W51071031001
Review of SQN Plant Documents for the Identification of
Newly Identified Systems, Structures, and Components as
required by 10 CFR 54.37(b)
08/21/2017
Work Orders
All Work Orders
114073526, 115364783, 115453612, 116593467,
116880207, 117080857, 117968680, 117977989,
118121028, 118132638, 118193768, 118611647,
118611657, 118611668, 119169548, 119991743,
20158600
Preventative
Maintenance
Tasks (4 digit P-
Number)
P1300, P7704, P7772, P7773, P7786, P7907
Preventative
Maintenance
Tasks (5 digit PM
Number)
16385, 74433, 74436, 74444, 74447, 78325
Preventative
Maintenance
Tasks (6-digit PM
Number)
2883, 120398, 120399, 120446, 120478, 120749, 126922,
26923, 126924
Preventative
Maintenance
Tasks (9 digit PM
Number)
014500000, 014510000, 014880001, 014880002,
014880003, 018160000, 030330000, 050201000,
050202000, 058370000, 056860004, 056860005,
056860006, 056860007, 058780001, 058780002,
058780005, 058780006, 058780007, 062950001,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
063040001, 063601499, 063604819, 063604820,
063604821, 063604822, 063605536, 063605537,
063605538, 063605648,, 800170889, 800170966,
800170967, 800170978, 800170980, 800170981,
800170983, 800170988, 800170989