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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210H0861999-07-28028 July 1999 Forwards Insp Rept 50-263/99-04 on 990521-0701.No Violations Noted.Licensee Conduct at Monticello Facility Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209G5621999-07-14014 July 1999 Forwards Insp Rept 50-263/99-11 on 990621-24.No Violations Noted.Objective of Insp,To Determine Whether Monticello Nuclear Generating Station Emergency Plan Adequate & If Station Personnel Properly Implemented Emergency Plan ML20196J5351999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950515 & NSP Responses & 980917 for Monticello Npp.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206N5601999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Monticello Npp.Organization Chart Encl ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant ML20206G4901999-05-0404 May 1999 Forwards Staff Review of Licensee 960508 Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Rc or Over Safety-Related Equipment, .Overall, Responses Acceptable.Tac M95610 Closed ML20206G7741999-05-0303 May 1999 Forwards Insp Rept 50-263/99-02 on 990223-0408.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20205N0821999-04-12012 April 1999 Forwards SE of NSP Response to NRC GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Licensee Adequately Addressed Actions Requested in GL ML20205N4811999-04-0909 April 1999 Forwards Licensing Requalification Insp Rept 50-263/99-10 on 990308-12.No Violations Noted.However,Inspectors Through Observation of Simulator Scenario Exams Noted Difficulties in Ability of SM to Simultaneously Implement Duties of SM ML20205N5301999-04-0909 April 1999 Discusses Arrangements Made on 990406 for Administration of Licensing Exams at Monticello Nuclear Generating Station During Wk of 990823.Requests That Exam Outlines Be Submitted by 990128 & Supporting Ref Matls by 990719 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C4851999-03-26026 March 1999 Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20205A5881999-03-24024 March 1999 Forwards Request for Addl Info Re Submittal Requesting Rev of pressure-temperature Limits & Surveillance Capsule Withdrawal Schedule ML20204H4711999-03-18018 March 1999 Forwards SER Concluding That Util Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello & Adequately Addressed Actions Requested in GL 96-05 ML20207H5161999-03-11011 March 1999 Forwards Insp Rept 50-263/99-01 on 990112-0222.No Violations Noted ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203A3081999-01-28028 January 1999 Forwards TS Page 60d,as Supplement 3 to 971125 LAR Re CST Low Level Hpci/Rcic Suction Transfer.Page Includes NRC Approved Amend 103 Changes for Use by NRC in Issuing SER ML20202F7821999-01-27027 January 1999 Forwards 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(vi).Ltr Contains No New Commitments or Modifies Any Prior Commitments ML20206S0331999-01-20020 January 1999 Submits Annual Rept of Safety & Relief Valves Failure & Challenges ML20206P1221998-12-31031 December 1998 Forwards LAR for License DPR-22,revising TS pressure-temp Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4, Deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR ML20198M3271998-12-28028 December 1998 Submits Change to Commitment for Submittal of ITS Application.Util Plans to Provide ITS Conversion Package Submittal to NRC in Dec of 2000 ML20198J7511998-12-22022 December 1998 Informs of Completion of Listed Commitment Made in Re Severe Accident Mgt. Severe Accident Mgt Guidelines Have Been Assessed,Plant Procedures Have Been Modified & Training of Affected Plant Staff Has Been Completed ML20198J4311998-12-21021 December 1998 Forwards Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv. Under Separate Cover,Licensee Is Providing LAR to Revise Curves ML20198J7711998-12-14014 December 1998 Documents 981214 Discussion with NRC Staff Re Deviation from Emergency Procedure Guidelines ML20195C8781998-11-11011 November 1998 Forwards Supplement to 971125 License Amend Request Re Condensate Storage Tank Low Level Suction Transfer Setpoints for HPCI Sys & Reactor Core Isolation Cooling Sys ML20195C9631998-11-11011 November 1998 Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment ML20195E2261998-11-10010 November 1998 Submits Suppl 1 to Util Response to NRC Request for Addl Info Re 981118 Request for Deviation from Emergency Procedure Guidelines ML20155H6591998-11-0404 November 1998 Forwards Response to 980910 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20155F9091998-10-27027 October 1998 Forwards Master Table of Contents to Rev 16 of Usar.Info Was Inadvertantly Omitted at Time of 981023 Submittal 05000263/LER-1998-005, Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed1998-10-21021 October 1998 Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed ML20154L9321998-10-12012 October 1998 Forwards Suppl 2 to LAR & Suppl 980319,which Proposed Changes to Ts,App a of Operating License DPR-22 for Mngp.Number of Addl Typos & One Title Change on Pages Associated with Amend Request Have Been Identified 05000263/LER-1998-004, Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment1998-10-0909 October 1998 Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment ML20154L8671998-10-0909 October 1998 Forwards Suppl 1 to LAR for License DPR-22, Replacing Exhibits B & C of Original Submittal to Reflect Item 2 & Subsequent Changes.Request for APRM Flow Converter Calibr Interval Extension,Withdrawn ML20154J6201998-10-0505 October 1998 Forwards Rev 49 to Monticello Security Plan.Encl Withheld, Per 10CFR73.21 ML20153F5351998-09-25025 September 1998 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Improved TS ML20153F0051998-09-25025 September 1998 Forwards Suppl 1 to 971031 Application for Amend to License DPR-22,replacing Exhibit C Which Contains TS Pages Incorporating Proposed Changes Described in Original 971031 Request ML20153D8561998-09-17017 September 1998 Forwards Rev 17 to EPIP A.2-414, Large Vol Liquid Sample &/ or Dissolved Gas Sample Obtained at Post Accident Sampling Sys. Superseded Procedures Should Be Destroyed.Ltr Contains No New NRC Commitments,Nor Does It Modify Prior Commitments ML20153D1441998-09-17017 September 1998 Informs NRC That Listed Commitments 1 & 3 Were Completed by End of 1998 Refueling Outage.Commitments Involved Final Disposition of Remaining Outlier Components Re All Known Outstanding Work Associated with GL 87-02,Suppl 1,USI A-46 ML20153E0331998-09-17017 September 1998 Forwards Response to NRC 980629 RAI Re RPV Weld Chemistry Values Previously Submitted as Part of Plant Licensing Basis.Next Monticello RPV Sample Capsule Scheduled to Be Removed During 1999/2000 Refueling Outage ML20153E9011998-09-0909 September 1998 Forwards Rev 1 to MNGP Colr,Cycle 19, Incorporating Changes to power-flow Maps in Figures 6 & 7.Changes Made to Correct Errors in Stability Exclusion Region & Stability Buffer Region Shown on Rev 0 ML20151S7401998-08-28028 August 1998 Responds to NRC Re Violations Noted in Insp Rept 50-263/98-09.Corrective Actions:Procedure 4 AWI-04.04.03 Will Be Revised to Eliminate Term Urgent from Section 4.3.1.D ML20238E8201998-08-26026 August 1998 Forwards Effluent & Waste Disposal Semi-Annual Rept for Jan-June 1998 & Revised Effluent & Waste Disposal Semi- Annual for Jul-Dec 1997. Ltr Contains No New NRC Commitments,Nor Does It Modify Any Prior Commitments ML20237E9741998-08-26026 August 1998 Forwards Rev 4 to EWI-09.04.01, Inservice Testing Program. Rev of Inservice Testing Program Reflects Valves Added as Result of Component Mods Recently Performed ML20237E6821998-08-25025 August 1998 Forwards fitness-for-duty Program Performance Data for Six Months Period Ending 980630 1999-09-09
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' I Northem States Power Company I Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 l
l l
l March 14,1996 10 CFR Part 50 Section 50.55a US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Reauest for Relief for the 3rd 10-Year Interval inservice Inspection Proaram On August 5,1994 we submitted for review our latest revision of our third 10-year incervice Inspection Examination Plan for Monticello. The purpose of this letter is to request review and l approval of ISI Relief Request No. 8 to the third 10-year plan. i Attached is Monticello's Relief Request No. 8 which addresses documentation requirements l for calibration blocks. The new code requirements for calibration block material documentation were discovered when we were preparing to purchase material for some new calibration blocks. The documentation that we have for our existing calibration blocks does not meet all of the revised requirements. We thus are requesting relief for documentation of our existing calibration blocks.
A similar Relief Request was granted for the Prairie Island plant on February 22,1996.
This letter contains no new Nuclear Regulatory Commission commitments.
Please contact Sam Shirey, Sr. Licensing Engineer, at (612) 295-1449 if you require further information.
h$kE+ b William J Hill Plant Manager Monticello Nuclear Generating Plant c: Regional Administrator-Ill, NRC NRR Project Manager, NRC Sr Resident inspector, NRC State of Minnesota Attn: Kris Sanda J Silberg
Attachment:
ISI Relief Request No. 8 9603260115 960314 PDR ADOCK 05000263 P PDR
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Att: chm::nt No.1
, , Monticello ISI Relief Request No. 8 (Rev. 0) j Use of Existing Calibration Blocks l 1
l SYSTEM: Various Class: 1 and 2 l
Category: B-A Item: B 1.21, B 1.22, B 1.30, B 1.40 1 B-D B 3.90, B 3.100 B-F B 5.10, B 5.130 B-J B 9.11, B 9.12, B 9.31 C-A C 1.10, C1.20 C-F-1 C 5.11, C 5.12 l C-F-2 C 5.51, C 5.52 Examination Reauirements:
IWA 2232(a) of ASME Section XI states that:
'1Jitrasonic examination of vessel welds greater than 2 inches thick shall be conducted in accordance with Article 4 of Section V, amended as follows."
1 Section V, Article 4, T-441.1.2 outlines the material specification requirements for calibration blocks. T-441.1.2.1 requires calibration blocks to be fabricated from one of the following: (a) nozzle drop out from the component; (b) a component prolongation, or; (c) material from the same material specification, product form, and heat treatment as one of the materials being joined.
l l IWA-2232(b) states that:
" Ultrasonic examination of piping systems shall be conducted in accordance with ASME Section XI, Appendix Ill."
Appendix 111, lll-3411 which outlines the material specification requirements for calibration blocks requires that: i
"(a) The calibration blocks for similar metal welds shall be fabricated from one of the same ;
materials specified for the piping being joined by the weld. (b) Calibration blocks for dissimilar metal welds to be fabricated from the material specified for the side of the weld from which the examination will be conducted. If the examination will be conducted from both sides, calibration reflectors shall be provided in both materials. (c) Where the examination is to be performed from only one side of the joint, the calibration block material shall be of the same specification as the material on that side of the joint. (d) If material of the same specification is not available, material of similar chemical analysis, tensile properties, and metallurgical structure may be used.
IWA-2232(d) states that:
"If the requirements of (a), (b), or (c) above are not applicable, the ultrasonic examination shall be conducted in accordance with the applicable requirements of Article 5 of Section V, amended as follows."
l i
M4% El3 EUT.AMOO45sN40NTILMN5fCALBK-lulW I
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Attachmint No.1
, , Monticello ISI Relief Request No. 8 (Rev. 0)
Use of Existing Calibration Blocks IWA-2232(d)(4)(a) states that:
! "The material from which the blocks are fabricated shall be: (1) a nozzle dropout from the l component; (2) a component prolongation; or (3) material of the same material specification,
! product form, and heat treatment as one of the materials being joined. (b) For calibration I blocks for dissimilar metal welds, the material selection shall be based on the material on the side of the weld from which the examination will be conducted. If the examination will l
be conducted from both sides, calibration reflectors shall be provided in both materials."
Examination Requirement Not Met Several of the calibration blocks currently being used lack the documentation necessary to demonstrate compliance with the material specification requirements of Article 4 of Section V and Appendix lil.
Several of the calibration blocks currently being used on pipe to fitting, or fitting to fitting joints where examination is performed from both sides of the joint, are fabricated to pipe material specifications.
Basis for Relief:
Documentation requirements existing at the time of fabrication did not require traceability to the material's chemical or physical certifications. Existing calibration blocks certification is verified through appropriate P-number grouping. The P-number grouping provides adequate assurance that the blocks will establish the proper ultrasonic calibration and sensitivity.
Proposed Attemative Existing calibration blocks will be used as is. Any calibration blocks obtained in the future will be obtained with documentation to demonstrate compliance with the material specification requirements of ASME Code Section V Article 4 or Section XI, Appendix 111, as applicable.
Justification for Grantina Relief it would be impractical to fabricate a new set of calibration blocks in order to satisfy the documentation requirements of the current Code. Existing records, indicate the appropriate P-number grouping, thereby providing adequate assurance that the blocks will establish the proper ultrasonic calibration and sensitivity.
Any new calibration block will be obtained with the documentation necessary to demonstrate compliance with the material specification requirements.
Time Period Relief is Reauested For Relief is requested for the Third Ten Year Interval.
Approval Status:
Not yet approved. Submitted Rev 0 March 14,1996.
nm = xm-c.munwmmmm 2
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