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MONTHYEARML21342A1412021-12-0909 December 2021 Enclosure - List of Attendees for the Public Meeting in Tarrytown, Ny, Re Indian Point Units 1, 2, and 3 PSDAR ML21179A0212021-06-24024 June 2021 NRC-2021-000172 - Resp 1 - Final, Agency Records Subject to Request Enclosed ML21144A1932021-05-12012 May 2021 IP-EP-360 Revision 6 ML21144A1922021-05-12012 May 2021 IPEC-EP 21-02 Revision 29 ML20307A1972020-11-16016 November 2020 Notification of Significant Licensing Action - Proposed Issuance of Order Approving a License Transfer Application for Which a Hearing Has Been Requested ML20078L3802020-03-18018 March 2020 Briefing on Agency Practice and Procedure Issues: NRC Expert Evaluation on Gas Transmission Lines, Indian Point ML20010D3552020-01-0909 January 2020 Ti 2515/194 Inspection Documentation Request ML18269A3462018-09-26026 September 2018 LTR-18-0376-OEDO Ticket - Paul Blanch, Energy Consultant, E-mail 2.206 Petition Regarding Violations of Regulations at Indian Point Units 2 and 3 ML18212A0322018-09-17017 September 2018 Records of Decision for the Indian Point Renewed Licenses ML17068A2452017-01-0808 January 2017 Closure Agreement January 8, 2017 CNRO-2016-00024, Entergy - Form 10-K for Fiscal Year Ended December 31, 20152016-12-20020 December 2016 Entergy - Form 10-K for Fiscal Year Ended December 31, 2015 ML16349A2272016-12-0909 December 2016 FOIA/PA-2016-0457 - Resp 3 - Interim, Agency Records Subject to the Request Are Enclosed. Part 2 of 2 ML16349A2262016-12-0909 December 2016 FOIA/PA-2016-0457 - Resp 3 - Interim, Agency Records Subject to the Request Are Enclosed. Part 1 of 2 ML16285A3322016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 14-10 ML16235A1662016-08-16016 August 2016 FOIA/PA-2016-0532 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed and Are Already Available in Public ADAMS or on Microfiche in the NRC Public Document Room ML16182A0622016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Speaker List ML16172A2662016-06-17017 June 2016 FOIA/PA-2016-0148 - Resp #3 - Final. Group a, Records Already Publicly Available ML16172A2682016-06-17017 June 2016 FOIA/PA-2016-0148 - Resp #3 - Final. Group B, Records Being in Part ML16112A3682016-04-29029 April 2016 Enclosure to Indian Point Nuclear Generating Unit Nos. 2 and 3 MSFHI Letter ML15322A0252015-11-18018 November 2015 50 54(p) Review for Indian Point ML15232A3562015-08-20020 August 2015 LTR-15-0430-1 - Oedo Ticket - Plans to Proceed with Construction of the Spectra Aim Pipeline in the Vicinity of the Indian Point Nuclear Power Plant ML15167A4442015-06-13013 June 2015 Paul Blanch Email Indian Point Existing Gas Pipeline Concerns ML15162A0842015-06-11011 June 2015 GTCC Disposals at the Barnwell Low-Level Radioactive Waste Facility from 1998 to Present ML15231A3642015-05-27027 May 2015 FOIA/PA-2014-0204 - Resp 1 - Final, Group a ML15147A4972015-05-20020 May 2015 5/20/2015 - Indian Point Annual Assessment Meeting Attendee Sign-In Sheet ML15070A0862015-03-0404 March 2015 FOIA/PA-2015-0076 - Resp 1 - Partial, Group B, Safety Review and Confirmatory Analysis ML15049A3472015-02-18018 February 2015 Certificate of Service ML15020A1102015-01-16016 January 2015 Consent & Waiver Form ML14322B0052014-11-17017 November 2014 LTR-14-0666-Ticket - Representative Nita M. Lowey Ltr. Request Comprehensive Risk Assessment for Expansion of Spectra Energy'S Algonquin Pipeline - Near Indian Point ML14307B7482014-10-30030 October 2014 Plant Modifications, IP 71111.18, Pipeline Analysis NL-14-133, RAI Data Documentation Package 10-23-142014-10-27027 October 2014 RAI Data Documentation Package 10-23-14 ML14157A3812014-06-0606 June 2014 LTR-14-0315-1-Ticket - J. Capozzelli Ltr. Urges the Commission to Deny Relicensing of Indian Point Nuclear Power ML13242A0232014-04-24024 April 2014 50.54 Review Indian Point Security Plan Revision 14 ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML13281A4992013-10-0303 October 2013 Response to Request for Additional Information Regarding P-T Limits and Ltop Requirements Vessels and Internals Integrity Branch (Evib) ML13231A2242013-08-19019 August 2013 G20130601/LTR-13-0682-Ticket - Representative Nita Lowey Ltr. Signed Petition by Residents of New York and New Jersey, Urging the NRC to Deny the Relicensing Renewal Requests for Reactors 2 and 3 at Indian Point Entergy Center in Buchanan, ML13200A0362013-07-10010 July 2013 LTR-13-0619 - Mary Saari, Village of Cold Spring, Ny, Ltr. Resolution for Public Health and Safety Regarding Indian Point Nuclear Plants ML13161A4512013-06-10010 June 2013 Certificate of Service ML13156A1882013-06-0303 June 2013 G20130435/LTR-13-0485-Ticket Dorice Madronero, Ny, E-mail/Letter Desalination Plant for Drinking Water within 3.5 Miles of Indian Point ML12300A4682012-10-0202 October 2012 LTR-12-0629 - Joan Agro Concerns Resolution for Public Health and Safety Regarding Indian Point Nuclear Plants ML12278A4262012-09-24024 September 2012 LTR-12-0560 - Catherine Howard (Dominican Sisters) Concerns Resolution for Public Health and Safety Regarding Indian Point Nuclear Plants ML12256A9902012-08-23023 August 2012 LTR-12-0500 - Marie Haughney Concerns Resolution for Public Health and Safety Regarding Indian Point Nuclear Plants ML15153A2142012-06-20020 June 2012 LTR-15-0270 - Congresswoman Nita Lowey, Letter Investigation of Fire at Indian Point Energy Center (Enclosure) ML12172A3702012-06-20020 June 2012 List of Exemptions, 1968-2012 ML12163A3522012-06-11011 June 2012 Annual Assessment Meeting Attendee List ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1131306672011-11-0909 November 2011 Lr Hearing - NIA-93 ML11327A0462011-10-28028 October 2011 Attachment 1 to NL-11-118 - Response to Request for Additional Information (Non-Proprietary) ML1127100332011-09-28028 September 2011 ROP Tabletop Examples and Results ML11230A0242011-08-18018 August 2011 Lr Hearing - NIA-096 2021-06-24
[Table view] Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - 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Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - 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Entergy Nuclear Northeast Indian Point Energy Center En tergy 450 Broadway, GSB Buchanan, NY 10511-0249 Robert Walpole Licensing Manager Tel (914) 734-6710 October 5, 2007 Re: Indian Point Unit 3 Docket 50-286 NL-07-121 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Second Request for Additional Information Regarding Relief Request 3-43 for Temporary Repair to Service Water Pipe
References:
- 1. Entergy letter NL-07-1 18 dated September 27, 2007 regarding Relief Request 3-43 for Temporary Repair to Service Water Pipe.
- 2. Entergy letter NL-07-120 dated October 3, 2007 regarding Response to Request for Additional Information for Relief Request RR 3-43.
Dear Sir or Madam:
Entergy Nuclear Operations, Inc (Entergy) is providing this response to a request for additional information regarding Relief Request RR 3-43 (Reference 1) as revised by Reference 2. NRC staff discussed this request for additional information with Entergy during a conference call on October 4, 2007. The additional information being provided (Attachments 1 and 2) does not result in a change to the Relief Request 3-43, Revision 1 submitted in Reference 2.
There are no new commitments being made in this submittal. If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Licensing at (914) 734-6710.
Sincerely, Robert Walp ee Licensing Manager Indian Point Energy Center cc: next page AWGL7
NL-07-121 Docket 50-286 Page 2 of 2 cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector, IP3 Mr. Paul D. Tonko, President NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service
ATTACHMENT 1 TO NL-07-121 REPLY TO SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIAN POINT 3 RELIEF REQUEST 3-43 FOR TEMPORARY NON-CODE REPAIR TO SERVICE WATER PIPING ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
NL-07-121 Attachment 1 Page 1 of 4 REPLY TO SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 3-43 The following information is being provided based on a conference call between NRC staff and Entergy Nuclear Operations, Inc on October 4, 2007 regarding Relief Request (RR) 3-43 submitted September 27, 2007 (NL-07-118) and as revised October 3, 2007 (NL-07-120). This additional information does not change Revision 1 of RR 3-43 provided in the October 3, 2007 submittal.
NRC Question 1:
In Attachment 3, page 6, Section 6.3, the licensee stated that the minimum required wall thickness was determined by UT readings. In Section 6.4, the licensee stated that the wall thickness used for the Code case N-513-1 evaluation was based on the average value of the thickness around the thinned area of the pipe.
(a) Discuss why two different approaches are used to in determining the wall thickness.
(b) Discuss for each approach whether the conservative wall thickness is used.
(c) Explain Item 2 in Section 6.3.
Entergy Response:
a) There are two thickness values established for two different purposes in the flaw evaluation provided as Attachment 3 to the Entergy letter dated October 3, 2007.
- 1. The minimum required wall thickness was calculated based on the USAS B31.1.0 Power Piping Code using the highest value of:
i) The stress value based on the pressure / hoop stress, ii) The mechanical stress, or iii) The administrative limit of 20%.
For this situation, the pressure / hoop stress is limiting. This is the approach used for establishing the wall thickness acceptance criterion limit for identifying a flaw.
- 2. The other wall thickness value used in Attachment 3 is developed based on results of field measurements obtained using ultrasonic testing (UT). This wall thickness value is used for evaluating flaw acceptability per Code Case N-513-1.
b) The wall thickness values for both purposes are conservative. Calculation of minimum required wall thickness incorporates the inherent conservatism from the Power Piping Code.
Determination of wall thickness based on UT measurements conservatively used that average thickness in the vicinity of the flaw instead of averaging the larger thickness around the entire pipe.
c) The method discussed in item 2 of section 6.3 of the calculation describes the method of increasing the calculated pipe stress to account for the reduced section of the metal due to corrosion. There are two methods that can be used; 1) assume the pipe is uniformly thinned around the entire pipe based on the lowest measured value or 2) calculate the section modulus and other properties based on actual UT measurements. For this situation, Entergy used method 2. Code Case N-513-1 requires that periodic examinations of no more than 90-
NL-07-121 Attachment 1 Page 2 of 4 day intervals be conducted to verify values used in the flaw growth evaluation. Entergy expects to implement a repair before the next examination is due.
NRC Question 2:
In Attachment 3, page 6, Section 6.6, the licensee referenced the 1995 edition of the ASME Code, Section Xl, Appendix H in evaluating the flaw(s). However, as stated on page 1 of , the code of record is the 1989 edition. Explain why the 1995 edition of the code is used.
Entercv Response:
The Klc and JIc values needed for the flaw evaluation are not reported in the 1989 Edition of Section XI, so the procedure for flaw evaluation references the 1995 Edition for these values.
The current code of record for repair and replacement activities at IP3 is the 2001 Edition through 2003 Addenda, as explained on page 1 of Attachment 2. Entergy has confirmed that coefficient values used in the flaw evaluation are consistent with the code of record.
NRC Question 3:
In Attachment 3, page 7, the licensee used 1.00 for the stress intensification factor (SIF) of the leak location. As the licensee indicated the value of 1.00 is for a pipe configuration. However, the pinholes are located in the part of the elbow, albeit on the straight end/section of the elbow, as shown in the photos that the licensee provided to the NRC. In addition, the pin holes are located close to the weld joining the elbow to the flange. The pinhole location would experience stress concentration because of their proximity to the weld. The purpose of the SIF is to model the piping loads in the analysis to account for the stress concentration at a piping location due to configuration or discontinuity. The staff believes that a SIF for the elbow should be used which is higher than 1.0. Justify why the SIF of 1.0 is acceptable.
Enterqy Response:
The SIF of 1.0, actually a value of .75i equal to 1.0, was used to remove the over conservatism caused by using the Elbow SIF over the entire length of the elbow. As the Companion Guide to the ASME BPVC, page 555 states "the SIF at an elbow is maximum at the 45 degrees location."
This accounts for the bucking at the out of plane which occurs at the center of the elbow only.
Since the leak and thinned area is approximately 3" from the elbow weld, an SIF for a straight pipe was used. In addition, since the flaw is near the weld to the flange an as-welded SIF can be used. For the B31.1 1967 edition of the code the as-welded SIF is 1.3, therefore the .75i would also be 1.0.
NRC Question 4:
In Attachment 3, page 10, the licensee showed the equations for Fm and Fb, the parameters for circumferential flaw, are calculated. However, the equations and associated coefficients do not seem to be consistent with that of Appendix H of the ASME Code Section Xl (the 1995 edition).
Explain.
NL-07-121 Attachment 1 Page 3 of 4 Enterqy Response:
The equations and coefficients are taken from Appendix I of Code Case N-513-1. The numbers displayed on calculation sheet are truncated to fit the spreadsheet format used for the calculation.
NRC Question 5:
In Attachment 3, page 11, the licensee stated that after weld overlay the SIF needs to be 2.1 for even a straight pipe. Explain why a SIF of 2.1 is used after weld overlay.
Enterqy Response:
This is from the requirement of Code Case N-661. The calculation was performed assuming the possible repair was going to be a weld overlay. If an overlay was performed then the code case requires an SIF of 2.1. This is derived from the as-welded SIF requirements contained in the later code versions. The statement is intended to state that stress requirements are met with the repair and an SIF of 2.1.
NRC Question 6:
Section 2(e), 2(f), 2(g), and 2(h) of Code case N-513-1 requires frequent periodic inspection or performing a flaw growth evaluation. Please address the requirements in each of these sections because it is not evident in the submittal that the licensee has met the requirements of N-513-1.
Enterpy Response:
Entergy is implementing the requirements of Sections 2(e), 2(f), 2(g), and 2(h) of Code case N-513-1, where applicable for this situation. Evaluation of the flaw has been completed per Section 2(e) and as documented in the calculation IP-CALC-07-00083 provided to NRC (Attachment 3 of Entergy Letter NL-07-120 dated October 3, 2007). The operability evaluation performed for this condition recommended a 30-day time frame for completing a repair.
Therefore, Code Case 513-1 requirements in section 2(e) that extend beyond 30 days would not be applicable, unless new data and an updated evaluation support a repair timeframe of longer than 30 days. Daily walkdowns are being performed per Section 2(f). Sections (g) and (h) pertain to performing a repair or replacement. Entergy is requesting NRC approval of Relief Request 3-43, Revision 1 to support our planned repair.
NRC Question 7:
For the flaw characterization and evaluation, identify any deviation from Code Case N-513-1 and other applicable code guidance or requirements including justification.
Enterqy Response:
Entergy is following the requirements of Code Case N-513-1 for flaw characterization and evaluation as documented in Entergy Calculation IP-CALC-07-00083.
NL-07-121 Attachment 1 Page 4 of 4 NRC Question 8:
Discuss and provide a report to show how the corrosion rate of 0.012 inches per year was determined. Discuss and provide the results of local corrosion rate.
Enterqy Response:
The corrosion rate value of 0.024 inches per cycle, or 0.012 inches per year is a historical value developed over several years of evaluating service water piping systems and corrosion degradation at IP2 and IP3. There is not a reference document for this value. Local corrosion rates can depend on many factors and Entergy has not developed a standard value to be assumed for local corrosion. The proposed repair does not depend on a precise value for corrosion rate, because Entergy will be monitoring for additional degradation and repair integrity by daily walkdowns and periodic UT examinations as stated in Section E.4 of Relief Request 3-43 and in response to NRC Question 10.
NRC Question 9:
Identify the code requirements for design, fabrication and NDE of the proposed repair (plate and weld). Identify any deviations from such code requirements with justification.
Enterqy Response:
The code requirements for design, fabrication, and NDE of the proposed repair are per original design requirements in B31.1 (1967). There have been no deviations from this code.
NRC Question 10:
Perform UT examination on pipe area adjacent to the repair weld (a band of three inches) to monitor the extent of degradation.
Enterqy Response:
The scope of the inservice monitoring described in Section E.4 of Relief Request 3-43, Revision 1 will include UT within a 3-inch band around the top and side perimeters of the repair weld to monitor for degradation. The base of the repair weld is adjacent to the bolting flange for this elbow, so that a full 3-inch band is not available. The UT will extend as far as practical beyond the base of the repair.
NRC Question 11:
Please provide the UT report for the measurements recently taken using a 1/4-inch grid.
Entergy Response:
UT Report IP3-UT-07-1 11 using the 1/1/4-inch grid is provided in Attachment 2. This UT exam provides for a more detailed inspection of two regions within the coverage of the UT exam previously performed with a 1-inch grid as documented in UT Report IP3-UT-07-110.
ATTACHMENT 2 TO NL-07-121 REPLY TO SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIAN POINT 3 RELIEF REQUEST 3-43 FOR TEMPORARY NON-CODE REPAIR TO SERVICE WATER PIPING Ultrasonic Test Results for Area Downstream of SWN-38 IP3-UT-07-1 11, September 2007 (1/4" grid)
ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
EIN.,,I Dt*- .! N)ic10 MI/A
. . .i..- 1 Rup)orl, No.: lP3-UIT-07-1 vi V/OilP01det No.: 00123409-02 Page: 1 01 4 AI 1'i'.1 1967 Ed. l hru 1969 Add. Catiltem. N/A Location: PAB / Minim Containment m', ;niav o..'
¢: 9321-F-27223 Descriplion: Characterize areas of wall thinning, reference report IP3-UT-07-110.
System ID. Service Watel Colipunr-SCo, ID: 18" Line t 408 DIS of valve SWN-38 Size/Length: 18" Sch STD Thickn ess/Diameter: 0.375" Lniiiiatlsonrm N'one Component File No.: SWN38-SM1 & SM2 Start Time: 1200 Finish Time: 1530 Calibration Information Partitioning Information Component Information
-r Calibration Times / Initials Component Begin/Col/Row Ending/Col/Row Component Geometry: Pipe Elbow
.040" .500" Start: 1300 REA M. UPST Ext. N/A Outside Diameter: 18" Grid Size: .25"x.25"
.100" N/A Verity: 1325 REA Main UPST. N/A Max. Thickness: .254" Min. Thickness: .032"
.200" N/A Verify: N/A Main N/A Nominal Thickness: .375" Tmin.: .090"
.300" N/A Verity: N/A Main DNST. N/A Min. Thickness Location: SM2 location J5 & K5
.400" N/A Final: 1355 REA M. DNST Ext. N/A Branch N/A Max. Thickness Location: SM2 location A9 Branch Ext. N/A Instrument:
Transducer: Reference/Simulator Block: Temp. Tool:
Maaer Pnmti Manufacturer: Panametrics Serial No.: A23867 Manufacturer: Control Co., Inc Mel. 31010 Serial No.: 536066 Type: C/S .04"-.5" Serial No.: OS-77 Serialno.: 03111106 dSize: 0.2" Freq.: 7.5 MHZ RefiSimulator Block Temp.: 87.1 'F Couplant:
Gain: 50 dB Model: D798 Type: Ultragel Range: 1.0" # of Elements: Dual Material/Component Temp.: 84.7 "F Batch No.: 05325 Comnents/Obstructions: Sub-micro grid of the thinner elbow areas show by report iP3-UT-07-110.
Results: Accept Reject ': Info Tmin = .090" per IP-CALC-07-00083.
Examiner Level III-PDI Sib re Date I Reviewe1 Signature Date Allen II, Robert E. -\-r,,*j ,. 9/20/20071 Examiner Level N/A Sid'tature Date 'Site Revie N/A N/A L ovt I N/A h2T3U Date ANII Review A-Ll i lare SignatureI V qj a 1 N/A r ~Date.
stippIerflCoftal R~eport I tP2'ý-UT-O7-1 11 I: !//0r2X' 2 nI 4 un iiry No.: 18" Line V 408 L:Xarnincr: Level: III-PDI Reviewer: Dale:
Allen I1,Robert E.
Oh xaminer: N/A LeveL: N/A Site Review: ItI1&// k Daii' Other: N/A Level: N/A ANtI Review: e4 Date:
Comments: Sketch of sub-mirco grid shown below superimposed over the micro grid established by report IP3-UT-07-110.
Sketch or Photo:
42~ S*I~I c F 14
WinmDLPWus,.ta Grid 18" Line # 408, DIS . lve SWN-38 I Fife Name *SWN38-SM1 Survey Date: 9j2012007 File Type. 2D Grid Minimum thickness; .061" 65 File De-crlpticiil Sub-Micro Grid 1 Maximum thickness: .184" A9 Lo :ation Note :P3 Report No,; IP3-UT-07-1 II lrerec ID : Page 3 or 4 R:'c'efl Aireri 4A1 FeLwr UU I.:A JB I c D jE (nIMax V Abg Color Legend OJS3 0.140 e,122 D.115 0,140 0,115 0,153 0.134 0.128 1 0.116 4 o..ill 0,152 0.184 0.168 0.117 f-0.s50- 0.184 0.150 0.16, 0.162 0.118 0.125 0,146 0.115 ~4-409-0.0 0.154 0.IZ4 0,14J, 0.114 0 148 0.140 0.134 0.116 0.184 0.142 Fo-..-
S0,030 0.168 0.1311 0.118; O.14 TAvg Page 1 Report Date: 9i24i2007
Win37DLPlus).ta Grid 18"Line # 408, D;S Ave SWN-38 SWVN38-S(\2 Survey Date : W12012007 FOLe Type 2D Grid Minimum thickness: .032"l J5 & K6 Fi eE i, :,i ion c~.; Sub-vMiro Grid 2 Maximum thickness: .254- Ag lPS, Report No,: IP3-UT-07-1 11 Luc a~tion Not Page 4 of 4 Rev iwer 'JfLA.#~~ d i
IL IM IN' 10 IP IQ Coloi Legend IC ID E IF IG IH I'1 11 1 IMin I Max jAvg 0,187 0,181 0.156 0.172 0.200 0.205 0,216 0.225 0.226 0.156 0.26 0.1" MJL 0.208 0.211 0.192*J 0.1.9 0.202 0,157 0.143 0.11IS 0.i18 0.135 0.211 0205 0.215 UP7 0.237 0.171 0.179 0.212 4 0.m 0.193 0.216 0228 0238 0.238 0.150 0.186 0.197 0.175 0,130 0,..114 Ol 0.180 0.179 0215 0234 0.234 0,140 0 .17 0.166 0.178 0.161 0.199 0.216 0.233 0.233 .2 2 0.176 0.159 0 .162 o1,2 0.164 0.141 0.149 0.114 ~ON 0127 0.14S 0*148 0.126 0. 110 0.1" 0.21 o13 0.13- 0.126 0.130 0.221 0200 0.229 0.229 0.118 0 12 0.152 0.112 0.141 0.172 0,221 0,222 o0226 0o226 o.0 0,174 01,2 0.166 0,19S 0 121 01157 0.175 0.112 0.122 0.114 0,119 0. 123 0,149 0.156 0.197 0.186 020 1 0,228 0 254
.12 0.163 0.1060 0-254
" 0ý o.147 0.12& &jjj-..` 0.179 0.200 0.221 oL123 0.208 0.212 0202 0.199 0.187 0.181 0.156 0,172 0.200 0.211 0221. 0228 0 238 0.254 0.166 0.19 0,152 0,170 0.140 0.127 - 7 0.131 0.16S 0204 0.215 0.230 0.171 0.117 0,125 0.112 0.167 f-Under Rzr~gý 0.254 TA ;.1 0.,145, Page 1 Report Date: 9W24J2007