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{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 November 21, 2006 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 November 21, 2006 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 -PREEMPTIVE WELD OVERLAYS (PWOL) ON ALLOY 600 PRESSURIZER NOZZLE-TO-PIPE WELDS AND ASSOCIATED ALTERNATIVE REPAIR TECHNIQUES  
In the Matter of                   )                                           Docket Nos. 50-327 Tennessee Valley Authority)                                                                 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - PREEMPTIVE WELD OVERLAYS (PWOL) ON ALLOY 600 PRESSURIZER NOZZLE-TO- PIPE WELDS AND ASSOCIATED ALTERNATIVE REPAIR TECHNIQUES - GENERIC REQUEST FOR RELIEF G-RR SUPPPLEMENTAL INFORMATION (TAC NOS. MD2381 &
-GENERIC REQUEST FOR RELIEF G-RR-1 -SUPPPLEMENTAL INFORMATION (TAC NOS. MD2381 &MD2382)This letter provides follow-up to TVA's telephone conversation with NRC on November 16, 2006. NRC attendees included Doug Pickett, Acting Chief, Plant Licensing Branch 11-2, Terrence Chan, Chief, Piping and Nondestructive Examination (NDE) Branch, Kim Gruss, Chief, Flaw Evaluation and Welding Branch, and Tim Lupold, Piping and NDE Branch. TVA attendees included representatives from Corporate Licensing and SQN.During the telephone call, NRC provided verbal approval for TVA's Generic Relief Request No. G-RR-1 for SQN Unit 2 in accordance with NRC Office Instruction LIC-102, Revision 1, "Relief Request Reviews." For additional clarification, NRC requested that TVA revise and resubmit the sketches previously provided in TVA's supplemental letter to NRC dated October 20, 2006. Specifically, NRC requested that point A and D on the sketches be relocated to show polished areas of the welds.Accordingly, the revised sketches are enclosed.Pr~ited on recycld pqew U.S. Nuclear Regulatory Commission Page 2 November 21, 2006 In a follow-up conversation on November 17, 2006, NRC clarified that the issuance of the formal Safety Evaluation Report on G-RR-1 is not a SQN Unit 2 restart constraint for the fall 2006 refueling outage.SON UNITS 1 AND 2 COMMITMENTS Also, in the follow-up telephone conversation, NRC clarified that commitment note No.3 found in Enclosure 2, "List of Commitments," of TVA's letter dated October 20, 2006, is superseded by the sketches enclosed herewith.
MD2382)
Thus, TVA withdraws note No. 3 applicability from the "List of Commitments." There are no additional commitments made by this letter. If you have any questions, please contact Rob Brown at (423) 751-7228.Sincerely, B. A. Wetzel Manager, Corporate Nuclear Licensing and Industry Affairs Enclosure cc (Enclosure):
This letter provides follow-up to TVA's telephone conversation with NRC on November 16, 2006. NRC attendees included Doug Pickett, Acting Chief, Plant Licensing Branch 11-2, Terrence Chan, Chief, Piping and Nondestructive Examination (NDE) Branch, Kim Gruss, Chief, Flaw Evaluation and Welding Branch, and Tim Lupold, Piping and NDE Branch. TVA attendees included representatives from Corporate Licensing and SQN.
U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, TN 37379 Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G9A One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN)Sketches 1 and 2 ILLUSTRATION SKETCH NO.1 (R2)t0.2"-0.5" N-504-2. APPENDIX 0. FIGURE 0-4100-1 AND PDI-UT-8 OVERLAY EXAMINATION VOLUME A-B-C-D.ALLOY 600 82/182 WELD ( OVERLAY-ALLOY 52/52M J ....... .........BUTTERING ALLOY 600 82/182 STAINLESS STEEL WELD2.ER308/E308 HEAT AFFECTED ZONE (HAZ) =0.125" STAINLESS STEEL PIPE SA-376 APPLICABLE VOLUMETRIC EXAMINATION VOLUME FOR USE OF APPENDIX Q ACCEPTANCE CRITERIA 11/17/2006 10:37 AM.:\.qm-IuI-rov\pxr ovorlsoyu'pxr  
During the telephone call, NRC provided verbal approval for TVA's Generic Relief Request No. G-RR-1 for SQN Unit 2 in accordance with NRC Office Instruction LIC-102, Revision 1, "Relief Request Reviews." For additional clarification, NRC requested that TVA revise and resubmit the sketches previously provided in TVA's supplemental letter to NRC dated October 20, 2006. Specifically, NRC requested that point A and D on the sketches be relocated to show polished areas of the welds.
*.ftt not row-2S-se-for rmodug ILLUSTRATION SKETCH NO.2 (R2)POST-OVERLAY SURFACE EXAMINATION AREA I N-504-2. APPENDIX 0, FIGURE 0-4100-1 AND PDI-UT-8 OVERLAY EXAMINATION VOLUME A-B-C-D 20" ALLOY 600 82/182 WELD OVERLAY-ALLOY 52/52M 0.95" MAX OVERLAY 0.45" MIN THICKNESS NOZZLE SA-508, ASAFE END CLASS 2 SA-182, F316L c %BUTTERING ALLOY 600 82/182 STAINLESS STELWELD ER308/E308 PRESERVICE AND INSERVICE VOLUMETRIC EXAMINATION VOLUMES FOR USE OF N-504-2. APPENDIX 0, FIGURE 0-4300-1, PDI-UT-8 AND TABLE IWB-3514-2 ACCEPTANCE CRITERIA STAINLESS STEEL PIPE-- EXAMINATION VOLUME a-b-c-d -- SA-376 wt\sqo-lmI-re,\ztr ever Ieyopzr softy nt 1 e reu-28-ee-for rue~dog}}
Accordingly, the revised sketches are enclosed.
onrecycldpqew Pr~ited
 
U.S. Nuclear Regulatory Commission Page 2 November 21, 2006 In a follow-up conversation on November 17, 2006, NRC clarified that the issuance of the formal Safety Evaluation Report on G-RR-1 is not a SQN Unit 2 restart constraint for the fall 2006 refueling outage.
SON UNITS 1 AND 2 COMMITMENTS Also, in the follow-up telephone conversation, NRC clarified that commitment note No.
3 found in Enclosure 2, "List of Commitments," of TVA's letter dated October 20, 2006, is superseded by the sketches enclosed herewith. Thus, TVA withdraws note No. 3 applicability from the "List of Commitments."
There are no additional commitments made by this letter. Ifyou have any questions, please contact Rob Brown at (423) 751-7228.
Sincerely, B. A. Wetzel Manager, Corporate Nuclear Licensing and Industry Affairs Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, TN 37379 Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G9A One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
 
ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN)
Sketches 1 and 2
 
ILLUSTRATION SKETCH NO.1 (R2) t0.2"-0.5" N-504-2. APPENDIX 0. FIGURE 0-4100-1 AND PDI-UT-8 OVERLAY EXAMINATION VOLUME A-B-C-D
                                                                      .ALLOY 600 82/182 WELD
(
* OVERLAY-ALLOY 52/52M J     ....... .........
BUTTERING ALLOY 600 82/182 STAINLESS STEEL WELD2.
ER308/E308 HEAT AFFECTED ZONE (HAZ)     =0.125" STAINLESS STEEL PIPE SA-376 APPLICABLE VOLUMETRIC EXAMINATION VOLUME FOR USE OF APPENDIX Q ACCEPTANCE CRITERIA 11/17/2006 10:37 AM
.:\.qm-IuI-rov\pxr ovorlsoyu'pxr *.ftt not row-2S-se- for rmodug
 
ILLUSTRATION SKETCH NO.2 (R2)
POST-OVERLAY SURFACE EXAMINATION AREA I           N-504-2. APPENDIX 0, FIGURE 0-4100-1 AND PDI-UT-8 OVERLAY EXAMINATION VOLUME A-B-C-D 20" ALLOY 600 82/182 WELD OVERLAY-ALLOY 52/52M 0.95" MAX OVERLAY 0.45" MIN THICKNESS NOZZLE 2 SA-508, CLASS                      ASAFE                                         SA-182, END F316L                           c           %
BUTTERING ALLOY 600 82/182 STAINLESS STELWELD ER308/E308 PRESERVICE AND INSERVICE VOLUMETRIC EXAMINATION VOLUMES FOR USE OF N-504-2. APPENDIX 0, FIGURE 0-4300-1, PDI-UT-8 AND TABLE IWB-3514-2 ACCEPTANCE CRITERIA                                                           STAINLESS STEEL PIPE
                --   EXAMINATION VOLUME a-b-c-d             --                                                           SA-376 1 nte reu-28-ee- for rue~dog wt\sqo-lmI-re,\ztr ever Ieyopzr softy}}

Latest revision as of 11:49, 23 November 2019

Preemptive Weld Overlays (Pwol) on Alloy 600 Pressurizer Nozzle-to-Pipe Welds and Associated Alternative Repair Techniques - Generic Request for Relief G-RR-1 - Supplemental Information (TAC No. MD2381 & MD2382)
ML063280025
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/21/2006
From: Wetzel B
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
G-RR-1, TAC MD2381, TAC MD2382
Download: ML063280025 (5)
v • d • e


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 November 21, 2006 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - PREEMPTIVE WELD OVERLAYS (PWOL) ON ALLOY 600 PRESSURIZER NOZZLE-TO- PIPE WELDS AND ASSOCIATED ALTERNATIVE REPAIR TECHNIQUES - GENERIC REQUEST FOR RELIEF G-RR SUPPPLEMENTAL INFORMATION (TAC NOS. MD2381 &

MD2382)

This letter provides follow-up to TVA's telephone conversation with NRC on November 16, 2006. NRC attendees included Doug Pickett, Acting Chief, Plant Licensing Branch 11-2, Terrence Chan, Chief, Piping and Nondestructive Examination (NDE) Branch, Kim Gruss, Chief, Flaw Evaluation and Welding Branch, and Tim Lupold, Piping and NDE Branch. TVA attendees included representatives from Corporate Licensing and SQN.

During the telephone call, NRC provided verbal approval for TVA's Generic Relief Request No. G-RR-1 for SQN Unit 2 in accordance with NRC Office Instruction LIC-102, Revision 1, "Relief Request Reviews." For additional clarification, NRC requested that TVA revise and resubmit the sketches previously provided in TVA's supplemental letter to NRC dated October 20, 2006. Specifically, NRC requested that point A and D on the sketches be relocated to show polished areas of the welds.

Accordingly, the revised sketches are enclosed.

onrecycldpqew Pr~ited

U.S. Nuclear Regulatory Commission Page 2 November 21, 2006 In a follow-up conversation on November 17, 2006, NRC clarified that the issuance of the formal Safety Evaluation Report on G-RR-1 is not a SQN Unit 2 restart constraint for the fall 2006 refueling outage.

SON UNITS 1 AND 2 COMMITMENTS Also, in the follow-up telephone conversation, NRC clarified that commitment note No.

3 found in Enclosure 2, "List of Commitments," of TVA's letter dated October 20, 2006, is superseded by the sketches enclosed herewith. Thus, TVA withdraws note No. 3 applicability from the "List of Commitments."

There are no additional commitments made by this letter. Ifyou have any questions, please contact Rob Brown at (423) 751-7228.

Sincerely, B. A. Wetzel Manager, Corporate Nuclear Licensing and Industry Affairs Enclosure cc (Enclosure):

U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, TN 37379 Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G9A One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN)

Sketches 1 and 2

ILLUSTRATION SKETCH NO.1 (R2) t0.2"-0.5" N-504-2. APPENDIX 0. FIGURE 0-4100-1 AND PDI-UT-8 OVERLAY EXAMINATION VOLUME A-B-C-D

.ALLOY 600 82/182 WELD

(

  • OVERLAY-ALLOY 52/52M J ....... .........

BUTTERING ALLOY 600 82/182 STAINLESS STEEL WELD2.

ER308/E308 HEAT AFFECTED ZONE (HAZ) =0.125" STAINLESS STEEL PIPE SA-376 APPLICABLE VOLUMETRIC EXAMINATION VOLUME FOR USE OF APPENDIX Q ACCEPTANCE CRITERIA 11/17/2006 10:37 AM

.:\.qm-IuI-rov\pxr ovorlsoyu'pxr *.ftt not row-2S-se- for rmodug

ILLUSTRATION SKETCH NO.2 (R2)

POST-OVERLAY SURFACE EXAMINATION AREA I N-504-2. APPENDIX 0, FIGURE 0-4100-1 AND PDI-UT-8 OVERLAY EXAMINATION VOLUME A-B-C-D 20" ALLOY 600 82/182 WELD OVERLAY-ALLOY 52/52M 0.95" MAX OVERLAY 0.45" MIN THICKNESS NOZZLE 2 SA-508, CLASS ASAFE SA-182, END F316L c  %

BUTTERING ALLOY 600 82/182 STAINLESS STELWELD ER308/E308 PRESERVICE AND INSERVICE VOLUMETRIC EXAMINATION VOLUMES FOR USE OF N-504-2. APPENDIX 0, FIGURE 0-4300-1, PDI-UT-8 AND TABLE IWB-3514-2 ACCEPTANCE CRITERIA STAINLESS STEEL PIPE

-- EXAMINATION VOLUME a-b-c-d -- SA-376 1 nte reu-28-ee- for rue~dog wt\sqo-lmI-re,\ztr ever Ieyopzr softy

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