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Category:Letter
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23048A3202023-02-17017 February 2023 Response to NRC Requests for Additional Information Regarding 2022 Unit 1 Steam Generator Tube Inspections ML22090A0802022-03-31031 March 2022 Response to NRC Requests for Additional Information Regarding 2021 Unit 3 Steam Generator Tube Inspections ML22053A2122022-02-22022 February 2022 Response to Requests for Confirmation of Information for Exemption from Certain Requirements of 10 CFR 50.62(c)(1) Using Risk-Informed Process for Evaluations ML21173A3602021-06-22022 June 2021 Response to Request for Additional Information for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML21061A1562021-02-26026 February 2021 Spent Fuel Storage Installation, Response to Request for Additional Information Regarding Application for Order Approving Indirect Transfers of Control of Licenses ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML20090L9442020-03-30030 March 2020 APS Response to Request for Additional Information- Relief Request 65 Unit 2, COVID-19, Request for Relief from Bottom Mounted Instrumentation Nozzles and a Pressurizer Nozzle to Surge ML20073R7532020-03-13013 March 2020 Independent Spent Fuel Storage Installation (ISFSI) - APS Response to Request for Additional Information for Changes to PVNGS Emergency Plan Staffing Requirements ML20054A2692020-02-19019 February 2020 Response to Request for Additional Information - Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19340B2142019-12-0606 December 2019 Response to NRC Request for Additional Information Regarding 2019 Steam Generator Tube Inspections ML19331A3612019-11-26026 November 2019 Supplemental Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel ML19277J4572019-10-0404 October 2019 Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel ML19165A1402019-06-14014 June 2019 Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19137A1182019-05-17017 May 2019 Response to NRC Staff Request for Additional Information from Reactor Assessment and Human Performance Branch Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome High Thermal ML19074A1382019-03-14014 March 2019 Response to Request for Additional Information - Relief Request 62 - Third and Fourth 10-Year Inservice Inspection Intervals, Proposed Alternative - Pressurizer Heater Sleeve Repairs ML19031C9052019-01-31031 January 2019 Supplemental License Amendment Request to Revise Technical Specifications Regarding Response Time Testing of Pressure Transmitters and Request for Additional Information Response ML18296A4662018-10-18018 October 2018 Supplemental Information Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML18278A2952018-10-0505 October 2018 Response to Request for Additional Information for Risk-Informed Completion Times Supplemental Responses for Items 17.f and 21 ML18264A3182018-09-21021 September 2018 Response to Request for Additional Information for Risk-Informed Completion Times ML18194A9142018-07-13013 July 2018 Supplemental Response to Request for Additional Information 3.a for License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML18152B8742018-06-0101 June 2018 Response to Electrical Engineering Operating Reactor Branch (Eeob) Request for Additional Information for Risk-Informed Completion Times ML18138A4802018-05-18018 May 2018 Response to Request for Additional Information for Risk-Informed Completion Times ML18129A4482018-05-0909 May 2018 APS Response to Request for Additional Information for License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML17272B0332017-09-29029 September 2017 Response to Request for Additional Information Regarding Fourth 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests ML17153A3732017-06-0202 June 2017 Response to NRC Staff Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Next Generation Fuel ML17144A3762017-05-24024 May 2017 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis ML17002A0012017-01-0202 January 2017 Response to NRC Requests for Additional Information (Rais) Regarding Emergency License Amendment Request (LAR) to Extend Diesel Generator 3B Completion Time ML17066A1842017-01-0202 January 2017 Response to NRC Requests for Additional Information (Rais) Regarding Emergency License Amendment Request (LAR) to Extend Diesel Generator 3B Completion Time ML16358A7152016-12-23023 December 2016 Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Diesel Generator Completion Time ML16340A9882016-12-0101 December 2016 Addendum to Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML17167A2152016-11-23023 November 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised ... ML16321A0022016-11-0909 November 2016 Response to RAI, Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised Technical Specifications and Bases and WCAP-18030, Revision 1 ML16300A1562016-10-26026 October 2016 Response to NRC Electrical Engineering Branch Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay ... ML16286A2422016-10-0606 October 2016 Westinghouse Electric Company, WCAP-18030-NP Review, Suggested Response to Request for Additional Information ML16286A2402016-10-0606 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis ML16257A5442016-09-0909 September 2016 Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML16203A3812016-07-21021 July 2016 Response to NRC Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML16182A5192016-06-30030 June 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Critical Safety Analysis ML16147A0922016-05-20020 May 2016 Response to Request for Additional Information Regarding Relief Request 54, Alternative to Flaw Removal ML16133A6212016-05-12012 May 2016 ISFSI - Response to Request for Additional Information Regarding Proposed Changes to Emergency Action Levels ML16102A4632016-04-11011 April 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505 ML16029A5062016-01-29029 January 2016 Response to Request for Additional Information Regarding the Request to Change the Quality Assurance Program Description ML15273A4702015-09-30030 September 2015 IR 05000528/2015004, 05000529/2015004, and 05000530/2015004; 11/16/2015 - 11/20/2015; Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Notification of NRC Triennial Heat Sink Performance Inspection ML15258A8482015-09-15015 September 2015 Response to Request for Additional Information Regarding Exigent License Amendment Request to Amend Technical Specification Surveillance Requirement 3.1.5.3 ML15223A2062015-08-0606 August 2015 Response to Request for Additional Information Associated with Seismic Hazard and Screening Report ML16133A3262015-05-0101 May 2015 Response to NRC Request for Flood Hazard Reevaluation Model Files ML18192A3891975-12-31031 December 1975 Public Service Company of New Mexico 1974 Annual Report, as Response to Request for Additional Financial Information ML18192B2781975-10-21021 October 1975 Response to NRC Liquefaction Questions. Review of Liquefaction Analysis in Parallel with the Site Dewatering Program 2024-01-12
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Text
10 CFR 50.SSa MARIA L. LACAL Se ni or Vi ce Preside nt, Nuclea r Reg ul atory & Ove rsight Palo Verde 102-07929-MLL/MDD Nuclear Generating Station June 14, 2019 P.O. Box 52034 Phoeni x, AZ 85072 U. S. Nuclear Regulatory Commission Mai l Station 7605 ATIN: Document Control Desk Tel 623.393.649 1 Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station Unit 3 Docket No. STN 50-530 Renewed Operating License No. NPF-74 Response to Request for Additional Information - Relief Request 63 -
Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval By letter number 102-07851, dated January 10, 2019 (Agencywide Documents Access and Management System Accession No. ML19010A307), Arizona Public Service Company (APS) submitted relief request 63 in accordance with 10 CFR 50.55a(g)(S)(iii). Certain ultrasonic examinations of welds identified in letter 102-07851 required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, sub-articles IWB-2500 and IWC-2500 have been determined to be impractical for Unit 3 third 10-Year inservice inspection interval.
The Nuclear Regulatory Commission (NRC) staff has requested additional information (RAI) to complete their review with regard to ASME Code class 2 components. A clarifying phone call was held between NRC and APS on April 4, 2019, to discuss the additional information needed. The APS response to the request for additional information is provided in the enclosure to this letter. The response due date was June 7, 2019. APS has granted a week extension to June 14, 2019 for the response during a call with the NRC project manager on June 5, 2019 .
No new commitments are being made in this submittal. If you have any questions about this request, please contact Michael D. Dilorenzo, Department Leader of Nuclear Regulatory Affairs, at (623) 393 - 3945 .
Sincerely,
~
MLL/MDD
Enclosure:
Response to Request for Additional Information - Relief Request 63, Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval cc: S. A. Morris NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Pea body NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance LLC Callaway
Enclosure Response to Request for Additional Information Relief Request 63 Unit 3 Impractical Examination s for the Third 10-Year Inservice Inspection Interval
Enclosure Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval 10 CFR 50.SSa Request Number 63 Response to Request for Additional Information Unit 3 Inservice Inspection Impracticality Third 10-Year Inservice Inspection Interval By letter number 102-07851, dated January 10, 2019, Agencywide Documents Access and Management System Accession No. ML19010A307, Arizona Public Service Company (APS) submitted relief request 63 in accordance with 10 CFR 50.55a(g)(S)(iii). Certain ultrasonic examinations of welds identified in letter 102-07851 required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, sub-articles IWB-2500 and IWC-2500 have been determined to be impractical for Unit 3 third 10-Year inservice inspection interval (ISi).
The Nuclear Regulatory Commission (NRC) staff has reviewed RR 63 and requested additional information in order to complete the review with regard to ASME Code Class 2 components. A clarifying phone call was held between NRC and APS on April 4, 2019, to discuss the additional information needed. The APS response is provided after each NRC request for additional information.
NRC MPHB-RAl-1:
Please discuss whether, as a substitute, examinations were performed on similar welds in the same piping systems that essentially 100 percent coverage could be achieved.
APS Response:
There are no examinations that can formally be credited in place of the limited examinations identified in Tables 2 and 3 of Relief Request 63. However, other ultrasonic (UT) examinations were completed on similar welds of the same piping systems, often on the same lines, that have essentially 100 percent coverage and no rejectable indications. Those completed UT examinations which correspond to the limited examinations within the same piping systems are referenced in Tables 2A and 3A.
NRC MPHB-RAl-2:
One of the notes associated with Tables 2 and 3 of the relief request states that " ... All piping material for C-F-1 welds in the Table above are Austenitic Stainless Steel ... " Please discuss the exact weld metal (material specification) used in the welds of Tables 2 and 3 APS Response:
Tables 2B and 3B have been provided as supplemental information to Tables 2 and 3 that were originally submitted as part of Relief Request 63. Tables 2B and 3B provide two weld material specifications for each weld. Specification "SFA-5.9 / ER316 / F6 / GTAW" was used for the initial passes (root) of each weld. The balance of each weld was completed using either SFA-5.9 / ER316 / F6 / GTAW or SFA-5.4 / ER316 / F5 / SMAW.
Enclosure Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval NRC MPH8-RAl-3:
Tables 2 and 3 of the relief request show that welds are located in various zones. Please describe the location of these zones (inside or outside of the containment), how the zones are designated, operational leakage monitoring and radiation dose, if any, in these zones.
APS Response:
The location of the applicable zones are provided in Tables 28 and 38. The ISi program is subdivided into zones for convenience of program management. Each zone may represent a room within the plant or a portion of a system separated by building penetrations, code classification boundaries, or otherwise. The Unit 3 Inservice Inspection program currently defines zones 1 through 6, and zones 16 through 129. Zones 7 through 15 are not currently used as zone designations within the program. The physical locations of each weld have been provided in Tables 28 and 38, however the piping/line description resides in Tables 2 and 3 of Relief Request 63. Leak detection/monitoring is provided for the areas and/or rooms and includes control room indication. Dose rates for each room have been provided in Tables 28 and 38 as averages during the previous 5 years.
NRC MPH8-RAl-4:
Please discuss the design and operating conditions (e.g., temperature and pressure) of the welds in Tables 2 and 3 of the relief request.
APS Response:
Design and operating conditions (e.g., temperature and pressure) of the welds identified in Tables 2 and 3 have been provided in Tables 28 and 38.
2
Enclosure Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 2A - SUQQlemental Information for Category C-F-1, Item CS.11 Welds Limited Exam Weld Information Similar Code Required Volume Weld Information ISI Zone Weld No.(s) Comments Pipe No. Pipe Diam. Credited with Weld Configuration Weld No. Weld Configuration Diam.
(inches) Code Required (in direction of flow)
(inches)
Volume 83 74-105 14 sweepolet to pipe 74-115 14 pipe to elbow Same line 90 85-9 24 flange to pipe 85-29 24 pipe to elbow Same line 90 85-11 24 pipe to valve 85-29 24 pipe to elbow Same line pipe to elbow (76-8),
91 76-7 12 orifice to pipe 76-8, 76-2 12 Same line reducer to pipe (76-2) 91 77-7 12 orifice to pipe 77-8 12 pipe to elbow Same line 91 77-14 12 pipe to valve 77-8 12 pipe to elbow Same line 91 77-16 12 valve to pipe 77-8 12 pipe to elbow Same line elbow to pipe (78-45),
78-45, 78-44, Same line 98 78-47 12 pipe to valve 12 pipe to elbow (78-44),
78-43 elbow to pipe (78-43) pipe to elbow (22-21),
22-21, 22-17, 101 71-123 16 valve to pipe 16 pipe to elbow (22-17), Same line 22-14 pipe to elbow (22-14) 104 85-46 20 pipe to valve 85-44 20 elbow to pipe Same line 104 85-47 20 valve to pipe 85-44 20 elbow to pipe Same line 3
Enclosure Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 3A - Sui:;1i:;1lemental Information for Category C-F-1, Item CS.21 Welds Limited Exam Weld Information Similar Code Required Volume Weld Information
!SI Zone Weld No.(s)
Pipe Comments No. Pipe Diam. Credited with Weld Configuration Weld No. Weld Configuration Diam.
(inches) Code Required (in direction of flow)
(inches)
Volume This line changes line number and tee to pipe (110-25),
110-25, 110-33, size, but runs continuous with the 110 110-17 2 pipe to valve 4 orifice to pipe (110-33),
110-34 line of the three welds identified as pipe to elbow (110-34) similar welds This line changes line number and tee to pipe (110-25),
110-25, 110-33, size, but runs continuous with the 110 110-52 2 pipe to tee 4 orifice to pipe (110-33),
110-34 line of the three welds identified as pipe to elbow (110-34) similar welds This line changes line number and size, but runs continuous with the 111 111-34 4 pipe to orifice 111-21 2 pipe to elbow line of the weld identified as a similar weld This line changes line number and 4 (113-2), elbow to pipe (113-2), size, but runs continuous with the 113 113-28 2 valve to pipe 113-2, 113-9 line of the two welds identified as 2 (113-9) elbow to pipe (113-9) similar welds Pipe to elbow (118-47),
118 118-46 3 penetration to pipe 118-47, 118-48 3 Same line elbow to pipe (118-48)
Pipe to elbow (118-47),
118 118-49 3 pipe to valve 118-47, 118-48 3 Same line elbow to pipe (118-48) 119 119-52 3 pipe to valve 119-26 3 tee to pipe Same line This line changes line number and size, but runs continuous with the 119 119-53 2 valve to pipe 119-26 3 tee to pipe line of the weld identified as a similar weld 4
Enclosure Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 2B - SURRlemental Information for Category C-F-1, Item CS.11 Welds Typical Design Conditions Operating Conditions ISI Pipe Area Dose Leakage Weld Filler Material Specifications Zone Diam. Plant Location Pressure Temp. Pressure Temp.
No. ASME / AWS / F No. / Process Rates Monitoring No. (inches) (mR/hr) (psi) (Deg. F) (psi) (Deg. F)
Auxiliary Bldg. -
SFA-5.9 / ER316 / F6 / GTAW Shutdown Cooling 0.3 - 9.0 Yes 650 400 370 350 83 74-105 14 SFA-5.4 / ER316 / F5 / SMAW HTX'A' Room Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW 0.2 - 22.0 Yes 100 350 100 120 90 85-9 24 East Mechanical SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW East Mechanical 0.2 - 22.0 Yes 100 350 100 120 90 85-11 24 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW West Mechanical 0.2 - 11.0 Yes 650 550 370 350 91 76-7 12 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW West Mechanical 0.2 - 11.0 Yes 650 550 370 350 91 77-7 12 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW West Mechanical 0.2 - 11.0 Yes 650 550 370 350 91 77-14 12 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW West Mechanical 0.2 - 11.0 Yes 2485 650 370 350 91 77-16 12 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Containment -
SFA-5.9 / ER316 / F6 / GTAW 103' el. Outside <0.2 Yes 2485 650 370 350 98 78-47 12 SFA-5.4 / ER316 / F5 / SMAW Bio-Shield Containment - 90' SFA-5.9 / ER316 / F6 / GTAW el. Outside Bio- 0.5 - 4.0 Yes 485 400 370 350 101 71-123 16 SFA-5.4 / ER316 / F5 / SMAW Shield Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW Low Pressure 100 350 100 120 104 85-46 20 0.4 - 33.0 Yes SFA-5.4 / ER316 / F5 / SMAW Safety Injection Pump Room 42' el.
Auxiliary Bldg -
SFA-5.9 / ER316 / F6 / GTAW Low Pressure 100 350 100 120 104 85-47 20 0.4 - 33.0 Yes SFA-5.4 / ER316 / F5 / SMAW Safety Injection Pump Room 42' el.
5
Enclosure Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 3B - SUQQlemental Information for Category C-F-1, Item CS.21 Welds Operating Design Conditions Conditions Pipe Typical Area Dose Leakage
!SI Zone Weld Filler Material Specifications Diam. Plant Location No. No. ASME / AWS / F No./ Process Rates (mR/hr) Monitoring Pressure Temp. Pressure Temp.
(inches) (psi) (Deg. F) (psi) (Deg. F)
Auxiliary Bldg - West SFA-5.9 / ER316 / F6 / GTAW 0.2 - 11.0 Yes 2050 350 1822 350 110 110-17 2 Mechanical SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg - West SFA-5.9 / ER316 / F6 / GTAW Mechanical 0.2 - 11.0 Yes 2485 650 1822 350 110 110-52 2 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg - West SFA-5.9 / ER316 / F6 / GTAW Mechanical 0.2 - 11.0 Yes 2485 650 1822 350 111 111-34 4 SFA-5.4 / ER316 / F5 / SMAW Penetration Room Auxiliary Bldg - East SFA-5.9 / ER316 / F6 / GTAW 0.2 - 22 Yes 2485 650 1822 350 113 113-28 2 Mechanical SFA-5.4 / ER316 / F5 / SMAW Penetration Room Containment - 90' SFA-5.9 / ER316 / F6 / GTAW 0.5 - 4.0 Yes 2485 650 1822 350 118 118-46 3 el. Outside Bio-SFA-5.4 / ER316 / F5 / SMAW Shield Containment - 90' SFA-5.9 / ER316 / F6 / GTAW el. Outside Bio- 0.5 - 4.0 Yes 2485 650 1822 350 118 118-49 3 SFA-5.4 / ER316 / F5 / SMAW Shield Containment - 90' SFA-5.9 / ER316 / F6 / GTAW el. Outside Bio- 0.5 - 4.0 Yes 2485 650 1822 350 119 119-52 3 SFA-5.4 / ER316 / F5 / SMAW Shield Auxiliary Bldg - CH SFA-5.9 / ER316 / F6 / GTAW Pump Valve Gallery 0.2 - 2.0 Yes 2485 650 1822 350 119 119-53 2 SFA-5.4 / ER316 / F5 / SMAW 100' el.
6