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Category:Inspection Plan
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request IR 05000390/20220062023-03-0101 March 2023 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022006 and 05000391/2022006 ML22327A1902022-11-28028 November 2022 – Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000390 2023403; 05000391 2023403 ML22250A4852022-09-0707 September 2022 Requalification Program Inspection IR 05000390/20220052022-08-31031 August 2022 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022005 and 05000391/2022005 - Final IR 05000390/20210062022-03-0202 March 2022 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 (Report No. 05000390/2021006 and 05000391/2021006) ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar IR 05000390/20200062021-03-0303 March 2021 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020006 and 05000391/2020006 ML20338A3202020-12-0303 December 2020 Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information ML20268B8672020-09-24024 September 2020 Document Request for Watts Bar Nuclear Plant Radiation Protection Inspection Inspection Report 2020-04 ML20253A1782020-09-0909 September 2020 Emergency Preparedness Program Inspection Request for Information IR 05000390/20200052020-08-31031 August 2020 Assessment Followup Letter and Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020005 and 05000391/2020005 ML20266G4592020-08-14014 August 2020 Notification of Inspection and Request for Information IR 05000390/20190062020-03-0303 March 2020 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - NRC Report 05000390/2019006 and 05000391/2019006 ML20028D4882019-12-0202 December 2019 Notification of Inspection and Request for Information IR 05000390/20180062019-03-0404 March 2019 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2018006 and 05000391/2018006 ML19063B8992019-02-28028 February 2019 ISI Sgisi RFI 2019002 Combined ML18282A4462018-10-0909 October 2018 Emergency Preparedness Program Inspection Request for Information ML18215A1362018-08-0202 August 2018 Radiation Safety Baseline Inspection RFI 2018003 Public ML18191B2472018-07-10010 July 2018 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000390/2018011 and 05000391/2018011 ML18187A0142018-07-0303 July 2018 RP Inspection Document Request - August 2018 ML18059A1502018-02-28028 February 2018 EOC Assessment Letter ML17271A0052017-09-21021 September 2017 Notification of Inspection and Request for Information ML17142A1862017-05-19019 May 2017 Emergency Preparedness Inspection and Request for Information Dated: May 19, 2017 IR 05000390/20160062017-03-0101 March 2017 Annual Assessment Letter for Watts Bar Nuclear Plant, NRC Inspection Report 05000390/2016006 and 05000391/2016006 ML17059C9572017-02-23023 February 2017 Notification of Inspection and Request for Information IR 05000391/20166112016-08-31031 August 2016 Mid-Cycle Assessment Letter - Watts Bar Nuclear Plant Unit 2 (NRC Inspection Report 05000391/2016611) IR 05000390/20160052016-08-31031 August 2016 Mid Cycle Assessment Letter for Watts Barr Nuclear Plant Unit 1, NRC Inspection Report 05000390/2016005 ML16062A2862016-03-0202 March 2016 Annual Assessment Letter IR 05000391/20166072016-03-0202 March 2016 End-Of-Cycle Assessment Letter - Watts Bar, Unit 2 (NRC Inspection Report 05000391/2016607) IR 05000391/20156062015-09-0101 September 2015 Mid-Cycle Assessment Letter - Watts Bar Nuclear Plant Unit 2 (NRC Inspection Report 05000391/2015606) IR 05000390/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Watts Bar Nuclear Plant Unit 1, NRC Inspection Report 005000390/2015005 IR 05000390/20140012015-03-0404 March 2015 Annual Assessment Letter for Watts Bar Nuclear Plant Unit 1, NRC Inspection Report 05000390/2014001 IR 05000391/20156012015-02-27027 February 2015 End-Of-Cycle Assessment Letter - Watts Bar Nuclear Plant, Unit 2 (NRC Inspection Report 05000391/2015601) IR 05000391/20146062014-09-0303 September 2014 Mid-Cycle Assessment Letter Watts Bar Nuclear Plant, Unit 2 (NRC Inspection Report 05000391/2014606) ML14245A1232014-09-0202 September 2014 Mid-Cycle Letter ML14125A0452014-05-0505 May 2014 Plant, Notification of Inspection and Request for Information IR 05000390/20130012014-03-0404 March 2014 Annual Assessment Letter Watts Bar Nuclear Plant Unit 1 (Report 05000390/2013001) IR 05000391/20136062013-09-0303 September 2013 Mid-Cycle Assessment Letter - Watts Bar Nuclear Plant Unit 2 (NRC Inspection Report 05000391/2013606) ML13246A1912013-09-0303 September 2013 Mid Cycle Assessment Letter ML13123A2732013-05-0303 May 2013 Ti 2515-182 Phase 1 RFI - MSC IR 05000390/20136012013-03-0404 March 2013 Annual Assessment Letter for Watts Bar Nuclear Plant Unit 2 (IR 05000390-13-601) IR 05000390/20120012013-03-0404 March 2013 Annual Assessment Letter for Watts Bar Nuclear Plant Unit 1 (Report 05000390/2012001) ML12248A1022012-09-0404 September 2012 Mid Cycle Assessment Letter Watts Bar 2012 IR 05000390/20120062012-09-0404 September 2012 Mid Cycle Assessment Letter Watts Bar 2012 ML12065A3502012-03-0505 March 2012 Inspection/Activity Plan, 03/01/2012 - 06/30/2013 2024-02-28
[Table view] Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-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 IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 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 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 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 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 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 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public 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), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS 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) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 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 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information 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 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) 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 ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) 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 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 May 5, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Shea:
On June 2, 2014, the Nuclear Regulatory Commission will begin inspection activities for the Watts Bar Nuclear Plant 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 June 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 in-office preparation activities and the implementation of this inspection on-site. If there are any questions about this inspection or the material requested, please contact the lead inspector, Joel Rivera-Ortiz, at (404) 997-4825 or Joel.Rivera-Ortiz@nrc.gov.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter and its Enclosure will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the
J. Shea 2 NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/ adams.html (the Public Electronic Reading Room).
Sincerely, RA Omar López-Santiago, Chief (Acting)
Engineering Branch 3 Division of Reactor Safety Docket No.: 50-390 License No.: NPF-90
Enclosures:
Temporary Instruction (TI 2515-182)
Inspection Documents Request TI-182 Phase II Questions cc: Distribution via Listserv
__________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE RA RA NAME J. Rivera-Ortiz O. Lopez-Santiago DATE 05/02/2014 05/05 /2014 E-MAIL COPY? YES NO YES NO TEMPORARY INSTRUCTION 2515-182 INSPECTION DOCUMENTS REQUEST Inspection Dates: June 2 - 4, 2014 Inspection Procedures: TI 2515-182, Review of Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks Inspector: Joel Rivera-Ortiz, Senior Reactor Inspector Information Requested for In-Office Preparation Activities:
The following documents listed below are requested (electronic copy, if possible) by May 28, 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 Joel Rivera-Ortiz US NRC- Region II Sr. Reactor Inspector Attn: Joel Rivera-Ortiz 404-997-4825 245 Peachtree Center Avenue, Suite 1200 Joel.Rivera-Ortiz@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 Yes / No January 1, 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?