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Category:Inspection Plan
MONTHYEARML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24059A4052024-02-28028 February 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-02 IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information IR 05000327/20200052020-08-18018 August 2020 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020005 and 05000328/2020005 ML20227A0082020-08-14014 August 2020 Requalification Program Inspection - Sequoyah Nuclear Plant ML19324E9992019-11-20020 November 2019 2020 SQN - POV Inspection Information Request - Rev. 1 ML19235A1972019-08-23023 August 2019 ISI 2019004 RFI Ajb ML19063D0842019-03-0404 March 2019 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2018006 and 05000328/2018006 IR 05000327/20180062019-03-0404 March 2019 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2018006 and 05000328/2018006 ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18240A3602018-08-24024 August 2018 Requalification Program Inspection ML18172A1182018-06-21021 June 2018 Notification of Inspection and Request for Information ML18059A1432018-02-28028 February 2018 EOC Assessment Letter ML18058B1632018-02-27027 February 2018 Emailed U1 ISI 2018002 RFI - Bcc IR 05000327/20170052017-08-24024 August 2017 Updated Inspection Plan for Sequoyah Updated Inspection Plant Units 1 and 2, Report 05000327/2017005 and 05000328/2017005 ML17146A1002017-05-25025 May 2017 Notification of Inspection and Request for Documents Dated May 25, 2017 ML17107A2602017-04-17017 April 2017 Notification of Inspection and Request for Information for NRC PI&R ML17115A4452017-04-17017 April 2017 Emergency Preparedness Inspection and Request for Information ML17067A4792017-03-0707 March 2017 Notification of Inspection and Request for Documents IR 05000327/20160062017-03-0101 March 2017 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 & 2 (Report 05000327/2016006 and 05000328/2016006) ML16286A0622016-10-0606 October 2016 Notification of Inspection and Request for Information IR 05000327/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 05000327/2016005, 05000328/2016005 ML16076A0612016-03-15015 March 2016 Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 05000327/2016007, 05000328/2016007 ML16062A2622016-03-0202 March 2016 Annual Assessment Letter IR 05000327/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 005000327/2015005, 005000328/2015005 ML15084A4022015-03-25025 March 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000327/20140012015-03-0404 March 2015 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 05000327/2014001, 05000328/2014001 IR 05000327/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 ML14245A1212014-09-0202 September 2014 Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 ML14072A0352014-03-10010 March 2014 Notification of Inspection and Request for Information ML14063A2472014-03-0404 March 2014 2013 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2 ML13297A0732013-10-23023 October 2013 IR 05000327-14-007 & 05000328-14-007.Sequoyah Nuclear Plant, Units 1 & 2, Notification of a Triennial Fire Protection Baseline Inspection ML13246A1952013-09-0303 September 2013 Mid Cycle Assessment Letter IR 05000327/20120012013-03-0404 March 2013 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2 (Report 05000327/2012001 and 05000328/2012001) ML12248A1042012-09-0404 September 2012 Mid Cycle Assessment Letter Sequoyah 2012 IR 05000327/20120062012-09-0404 September 2012 Mid Cycle Assessment Letter Sequoyah 2012 ML12065A3292012-03-0505 March 2012 RPT 22, Inspection/Activity Plan IR 05000382/20120012012-03-0505 March 2012 Annual Assessment Letter for Waterford Steam Electric Station-Unit 3 (Report 05000382-12-001) ML1124401842011-09-0101 September 2011 Inspection/Activity Report 22, 09/01/2011 - 12/31/2012 ML1106303542011-03-0404 March 2011 Inspection / Activity Plan, Report 22 ML1024408442010-09-0101 September 2010 Report 22 Inspection/Activity Plan 09/01/2010 - 12/31/2011 ML1006209872010-03-0303 March 2010 Inspection/Activity Plan 03/01/2010 - 06/30/2011 ML0924406512009-09-0101 September 2009 Inspection/Activity Plan 03/01/2009 - 12/31/2010 2024-05-31
[Table view] Category:Letter
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements ML24088A0332024-03-28028 March 2024 Request for Regulatory Conference (Tennessee Valley Authority) CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report 2024-09-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 March 10, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Shea:
On April 2, 2014, the Nuclear Regulatory Commission (NRC) will begin inspection activities for the Sequoyah Nuclear Plant, Units 1, and 2, in accordance with Temporary Instruction (TI) 2515-182, Review of Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks. This inspection is scheduled to be performed from April 2 - 4, 2014, and will address the inspection requirements for Phase 2 of this TI.
In order to minimize the impact to your on-site resources, and to ensure a productive inspection, we have enclosed a list of documents needed for the preparation and implementation of this inspection. The documents that are requested for this inspection include all relevant documents that will allow the inspector(s) to adequately complete Phase 2 of this inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. Don Sutton, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Brendan Collins at (404) 997-4420 or Brendan.Collins@nrc.gov.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
J. Shea 2 Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/ adams.html (the Public Electronic Reading Room).
Sincerely, RA Omar R. López-Santiago, Chief (Acting)
Engineering Branch 3 Division of Reactor Safety Docket Nos.: 50-327, 50-328 License Nos.: DPR-77, DPR-79
Enclosure:
Temporary Instruction (TI 2515-182)
Inspection Document Request TI-182 Phase II Questions Distribution via Listserv
__________ X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE RA RA NAME B. Collins O. López-Santiago DATE 3/6 /2014 3/10/2014 E-MAIL COPY? YES NO YES NO TEMPORARY INSTRUCTION 2515-182 INSPECTION DOCUMENT REQUEST Inspection Dates: April 2 - 4, 2014 Inspection Procedures: TI 2515-182, Review of Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks Inspector: Brendan Collins, Reactor Inspector Information Requested for the Preparation and Completion of the In-Office Inspection:
The following documents listed below are requested (electronic copy, if possible) by March 24, 2014, to facilitate the preparation for the on-site inspection week.
- 1. Contact information for plant staff responsible for the implementation of the underground piping and tanks program.
- 2. Copy of the documents governing the implementation of the sites underground piping and tanks program. For example, this includes administrative and implementing procedures for the program.
- 3. Please review the Attachment to this Enclosure, TI 2515-182, Review of Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks, Phase 2 Questions, and provide response to all the questions, as applicable.
- 4. Schedule for completion of the following NEI 09-14, Guideline for the Management of Underground Piping and Tank Integrity, Revision 3, attributes:
Buried Piping Procedures and Oversight Risk Ranking Inspection Plan Plan Implementation Asset Management Plan Underground Piping and Tanks Procedures and Oversight Prioritization Condition Assessment Plan Plan Implementation Asset Management Plan Information to be provided On-Site to the Inspector following the Entrance Meeting:
- 1. Copy or ready access to the program drawings showing the location of buried and underground piping and tanks within the scope of the program.
- 2. Copy or ready access to the industry standards and guidelines associated with the program.
Enclosure
2
- 3. Self- or third-party assessments of the underground piping and tanks program (if any have been performed).
- 4. Response to additional information requested prior to the inspection based on the response to the TI 2515-182 questions in the Attachment.
- 5. For any of the NEI 09-14 (Revision 3) attributes identified below which have been completed prior to the NRCs onsite inspection, provide written records that demonstrate that the program attribute is complete.
Buried Piping
- Asset Management Plan Underground Piping and Tanks
- Condition Assessment Plan
- Asset Management Plan Inspector Contact Information Mailing Address Brendan Collins US NRC- Region II Reactor Inspector Attn: Brendan Collins 404-997-4420 245 Peachtree Center Avenue, Suite 1200 Brendan.Collins@nrc.gov Atlanta, GA 30303
TI 2515-182 Review of Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks Phase 2 Questions Questions Response Question Subpart Number Initiative Consistency 1 a Has the licensee taken any deviations to either of Yes / No the initiatives?
b If so, what deviations have been taken and what is (are) the basis for these deviations?
2 a Does the licensee have an onsite buried piping Yes / No program manager (owner) and, potentially, a staff?
b How many buried piping program owners have there been since January 1, 2010?
c How many other site programs are assigned to the buried piping program owner?
3 a Does the licensee have requirements to capture Yes / No program performance, such as system health reports and performance indicators?
b Are these requirements periodic or event driven? Periodic /
Event Driven /
None c Are there examples where these requirements Yes / No have been successfully used to upgrade piping systems or to avert piping or tank leaks?
4 a Does the licensee have a program or procedure Yes / No to confirm the as-built location of buried and underground piping and tanks at the plant?
b Has the licensee used this program? Yes / No c Was the program effective in identifying the Yes / No location of buried pipe?
Attachment
2 5 For a sample of buried pipe and underground Yes / No piping and tanks (sample size at least 1 high and Sample size 1 low risk/priority pipe or tank), did the risk examined ranking and/or prioritization process utilized by _____
the licensee produce results in accordance with the initiative guidelines, i.e., which emphasize the importance of components which have a high likelihood and consequence of failure and deemphasize the importance of components which have a low likelihood and consequence of failure?
6 a As part of its risk ranking process did the Yes / No licensee estimate/determine the total length of buried/ underground piping included in the initiatives?
b As part of its risk ranking process did the Yes / No licensee estimate/determine the total length of high risk buried/underground piping included in the initiatives?
Preventive Actions / System Maintenance 1 a For uncoated steel piping, has the licensee Yes / No / Not developed a technical basis for concluding that Applicable (no structural (e.g. ASME Code minimum wall, if uncoated applicable) and leaktight integrity of buried piping buried steel can be maintained? pipe) b Is the technical basis provided as justification by Yes / No the licensee consistent with the initiative (including its reference documents) or industry standards (e.g. NACE SP0169) 2 a For buried steel, copper, or aluminum piping or Yes / No / Not tanks which are not cathodically protected, has Applicable (no the licensee developed a technical basis for buried steel, concluding that structural (e.g. ASME Code copper, or minimum wall, if applicable) and leaktight aluminum integrity of buried piping can be maintained? piping which is not cathodically protected) b Is the technical basis provided as justification by Yes / No the licensee consistent with the initiative (including its reference documents) or industry standards (e.g. NACE SP0169)
3 3 a For licensees with cathodic protection systems, Yes / No / Not does the licensee have procedures for the Applicable (no maintenance, monitoring and surveys of this cathodic equipment? protection systems) b Are the licensee procedures consistent with the Yes / No initiative (including its reference documents) or industry standards (e.g. NACE SP0169)?
c Is the cathodic protection system, including the Yes / No evaluation of test data, being operated and maintained by personnel knowledgeable of, or trained in, such activities 4 Is there a program to ensure chase and vault Yes / No / N/A areas which contain piping or tanks subject to the (No piping in underground piping and tanks initiative are chases or monitored for, or protected against, accumulation vaults) of leakage from these pipes or tanks?
Inspection Activities / Corrective Actions 1 a Has the licensee prepared an inspection plan for Yes / No its buried piping and underground piping and tanks?
b Does the plan specify dates and locations where Yes / No inspections are planned?
c Have inspections, for which the planned dates Occurred as have passed, occurred as scheduled or have a scheduled /
substantial number of inspections been deferred? Deferred 2 a Has the licensee experienced leaks and/or Leaks Yes / No significant degradation in safety related piping or Degradation piping carrying licensed material since January 1, Yes / No 2009?
b If leakage or significant degradation did occur, Yes / No did the licensee determine the cause of the leakage or degradation?
4 c Based on a review of a sample of root cause Yes / No / N/A analyses for leaks from buried piping or (no leaks) underground piping and tanks which are safety related or contain licensed material, did the licensee's corrective action taken as a result of the incident include addressing the cause of the degradation?
d Did the corrective action include an evaluation of Yes / No / N/A extent of condition of the piping or tanks and (no leaks) possible expansion of scope of inspections?
(Preference should be given to high risk piping and significant leaks where more information is likely to be available).
3 a Based on a review of a sample of NDE activities Yes / No which were either directly observed or for which records were reviewed, were the inspections conducted using a predetermined set of licensee/contractor procedures?
b Were these procedures sufficiently described and Yes / No recorded such that the inspection could be reproduced at a later date?
c Were the procedures appropriate to detect the Yes / No targeted degradation mechanism?
d For quantitative inspections, were the procedures Yes / No used adequate to collect quantitative information?
4 Did the licensee disposition direct or indirect NDE Yes / No results in accordance with their procedural requirements?
5 Based on a sample of piping segments, is there Yes / No evidence that licensees are substantially meeting the pressure testing requirements of ASME Section XI IWA-5244?