Letter Sequence Response to RAI |
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Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 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 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
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JULY 25, 2007 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-390 Tennessee Valley Authority )
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) INSERVICE INSPECTION (ISI) PROGRAM REQUEST FOR RELIEF PDI RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (TAC No. MD4448)
The purpose of this letter is to respond to the NRCs request for additional information dated July 9, 2007, concerning the subject request for relief. TVA submitted the request for relief on February 7, 2007.
There are no regulatory commitments associated with this submittal. If you have any questions concerning this matter, please call me at (423) 365-1824.
Sincerely, ORIGINAL SIGNED BY J. D. Smith Manager, Site Licensing and Industry Affairs (Acting)
Enclosure cc: See Page 2
U.S. Nuclear Regulatory Commission Page 2 July 25, 2007 JDS:
Enclosures cc (Enclosures):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. Brendan T. Moroney, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
INSERVICE INSPECTION (ISI) PROGRAM REQUEST FOR RELIEF PDI-2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By letter dated February 7, 2007, TVA submitted for staff review and approval the proposed Request for Relief (RR) PDI-2. This request was seeking relief from the requirements of ASME Code,Section XI, for the second 10-year inservice inspection (ISI) interval to WBN Unit 1. In order to complete the review, the staff has requested the following additional information by letter dated June 7, 2007.
QUESTION 1 The Justification For Granting Relief, states that the examination volume required by [ASME Code,Section XI, Figures]
IWB-2500-7(a) and (b) for the pressure retaining nozzle-to-vessel welds extends far beyond the weld and the heat effected zones into the base metal, and is unnecessarily large.
Question 1a:
Provide supplemental sketches showing the specific configuration nozzle-to-vessel weld and revised examination volume (including dimensions).
Response
The examination volumes for the nozzle to vessel welds are provided in Figures 1 and 2. Specific configurations and dimensions of the shell (ts), nozzles, and cladding are shown in figures 3 and 4.
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Figure 1 E1-2
Figure 2 E1-3
Figure 3 E1-4
Figure 4 E1-5
QUESTION 1b Provide a listing of components for which relief is being requested.
Response
RR No. PDI-2 requests relief for the items in Examination Category B-D, Full Penetration Welded Nozzles in Vessels -
Inspection Program B, Item No. B3.90, Reactor Vessel Nozzle-to-Vessel Welds. This inspection and the subject RR applies specifically to the following locations and ISI weld inspection numbers.
Loop 1 Hot Leg Nozzle-to-Vessel Weld ISI Weld No. N18 Loop 1 Cold Leg Nozzle-to-Vessel Weld ISI Weld No. N14 Loop 2 Hot Leg Nozzle-to-Vessel Weld ISI Weld No. N17 Loop 2 Cold Leg Nozzle-to-Vessel Weld ISI Weld No. N12 Loop 3 Hot Leg Nozzle-to-Vessel Weld ISI Weld No. N16 Loop 3 Cold Leg Nozzle-to-Vessel Weld ISI Weld No. N13 Loop 4 Hot Leg Nozzle-to-Vessel Weld ISI Weld No. N15 Loop 4 Cold Leg Nozzle-to-Vessel Weld ISI Weld No. N11 QUESTION 1c Identify the ultrasonic technique (manual or automated), nominal pipe diameters, and weldment material (ferritic, austenitic stainless steel, Inconel) that TVA is proposing to inspect.
Response
For the eight welds within the scope of RR No. PDI-2, Watts Bar currently plans to perform future inspections using the same examination methods used during the Cycle 6 refueling outage.
This method of examination utilizes two automated ultrasonic inspection processes. The first examination uses an Appendix VIII qualified bi-directional examination technique, requiring four search units for the clockwise/counterclockwise scans and three search units for the toward/away scans. This multi-high angle, multi modal, and multi directional ultrasonic technique is performed from the inside of the reactor vessel shell to cover the cladding and innermost 10% of the weld and adjacent base material. This examination for detection of radial flaws also includes a technique to interrogate the remaining weld and base metal thickness. The second examination uses an Appendix VIII qualified multi angle, phased-array technique performed from the nozzle bore to detect circumferentially oriented reflectors located within the full examination volume.
Figures 3 and 4 depict the applicable nozzle configuration, dimensions, and weldment materials.
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QUESTION 1d Since TVA is complying with Title 10 Code of Federal Regulations (10 CFR) 50.55a(b)(2)(xv)(K)(1), and 10 CFR 50.55a(b)(2)(xv)(K)(2), will TVA be performing any examinations from the outside surface of the subject nozzles?
Response
Watts Bar does not currently plan to perform any examinations of the reactor vessel nozzle-to-vessel weld from the outside surface of the vessel. As stated in the response to question 1c, inspections are to be performed from the vessel inside surface and nozzle bore.
Based on the results of the reactor vessel examinations performed during RFO6 by IHI Southwest Technologies, Inc. the following are the maximum obtainable coverages for the hot-leg and cold-leg nozzle-to-vessel welds utilizing the inspection requirements of ASME Section XI, Appendix VIII.
Outlet nozzles - ISI Weld No. N18, N17, N16, and N15 76%
Inlet nozzles - ISI Weld No. N14, N13, N12, and N11 99%
As a result of the coverage limitations for the outlet nozzle-to-vessel weld examination from inside the reactor vessel and nozzle bore, and the lack of coverage obtainable from the vessel outside surface, RR 1-ISI-19 was submitted to the NRC to formally request the inspection coverage be limited to the maximum extent practical given the physical limitations present. RR 1-ISI-19 was approved by the NRC in a safety evaluation dated October 27, 2006.
In performing past and future inspections in accordance with Examination Category B-D, Item No. B3.90, Watts Bar Nuclear (WBN) has and will fully comply with the requirements of Title 10 Code of Federal Regulations 10 CFR 50.55a (b)(2)(xv)(K)(1).
Additionally, WBN has and will comply with the requirements of 10 CFR 50.55a (b)(2)(xv)(K)(2) except as allowed by the NRC based on approval of RR 1-ISI-19.
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QUESTION 1e Clarify how TVAs personnel will be able to locate the widest portion of the nozzle-to-vessel weld precisely. It is unclear how repaired areas extending beyond the ideal weld cross-sectional area are identified and how these areas will be examined. If personnel are to identify widest sections of the nozzle-to-vessel weld, specify what positive means of examination will be used to identify the weld extremities. Will the extremities be identified on both the inside and outside diameters of the nozzle to ensure complete coverage of the welds?
Response
The location of the widest portion of the nozzle-to-vessel weld is determined from the as-built vessel fabrication drawings; and the automated ultrasonic equipment is programmed accordingly.
Since the inside of the nozzles and vessel are cladded, the location of the weld can not be seen from the vessel ID. Since the examinations have been performed from the vessel ID and nozzle bore, identification of the weld from the vessel OD does not provide any practical information to positively identify the weld extremities.
The construction code NDE performed in accordance with ASME Section III, NB-5000, required radiography of the weld volume and a surface examination of the weld plus 1/2 of adjacent base material. Had there been indications identified in this volume, which required repair, the repaired area would still be interrogated by the examination volume proposed in relief request PDI-2. In addition, all eight nozzle welds were examined utilizing the greater volume (1/2t) specified in ASME Section XI during preservice; and the four outlet nozzle welds were examined again inservice in 1999 to the greater (1/2t) volume with no unacceptable indications.
The phased array examinations performed from the nozzle bore have electronic gates extending 1/2 of metal path past the required examination volume. This extended gate allows an additional 1/2 buffer zone beyond the 1/2 of base material.
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QUESTION 1f Have the subject welds been previously ultrasonically examined using the examination volumes of ASME Code,Section XI, Figures IWB-2500-7(a) and (b)?
Response
Preservice examination of the eight RPV inlet and outlet nozzles was performed in 1978 by Southwest Research Institute. The examination was performed to the requirements of ASME Section XI, 1974 Edition, Summer 1975 Addenda for the Code specified volume.
Inservice examination of the four outlet RPV nozzles (N-15, N-16, N-17, and N-18) was performed in 1999 by Southwest Research Institute. The examination was performed to the requirements of ASME Section XI, 1989 Edition for the Code specified volume.
Inservice examination of the eight RPV inlet and outlet nozzles was performed in 2005 by Southwest Research Institute to the requirements of ASME Section XI, 1995 Edition, 1996 Addenda, for a modified inspection volume including the weld plus 1/2 on both sides, in accordance with Request for Relief PDI-2. Utilizing the modified inspection volume, essentially 100% coverage was not obtained for the outlet nozzles and Request for Relief 1-ISI-19 was submitted to the NRC for approval. Relief was granted in a safety evaluation issued October 27, 2006 (Accession number ML062480232).
The preservice and inservice inspections of the subject nozzle-to-vessel welds have shown the ASME Code volume to be free of unacceptable indications.
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