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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
[Table view] |
Text
r
. l VIRGINIA ELECTRIC AND Powan Comwwy l RICIIMOND, VIRGINIA 202 61 i
-July 10, 1995 l
i i
U.S. Nuclear Regulatory Commission Serial No.95-230 I Attention: Document Control Desk NL&P/DCH R2 Washington, D.C. 20555 Docket No. 50-338 License No. N PF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM RELIEF REQUEST North Anna Unit 1 is currently in the second period of its second ten-year inservice ,
inspection interval. North Anna Unit 1 examinations have been conducted to the l requirements of the 1983 Edition, through Summer 1983 Addenda, of ASME Section XI.
Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from certain requirements of ;
the ASME Section XI Code associated with partial examinations conducted for North ;
Anna Unit 1. Relief Requests NDE-20, Rev. 2, and NDE 26 for North Anna Unit 1 l (attached) provide the basis for the requested relief. Relief Request NDE-20, Rev. 2, . '
supersedes Relief Request NDE-20 submitted by our letter dated August 5,1993 (Serial No.93-435).
These relief requests have been approved by the North Anna Station Nuclear Safety '
and Operating Committee.
1 If you have any questions conceming these requests, please contact us. l 1
Very truly yours, 1
James P O'Hanlon
. Senior Vice President - Nuclear i
Enclosures i
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ny 9507130045 950710 PDR ADOCK 0500o338 Q PDR
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cc: .U.S. Nuclear Regulatory Commission
- Region ll '
101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter ;
NRC Senior Resident inspector North Anna Power Station Mr. N. Economos U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 1
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North Anna Power Station Unit 1 ASME Section XI Relief Request NDE-20 R 1
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NARTH ANNA UNIT 1 RELIEF REQUEST NDE-20 REVISION 2 l
- 1. IDENTIFICATION OF COMPONENTS Mark / Weld # Linn # Drawing # Class 1 RC-R-1 11715-WMKS-RC-R-1.2 1 1 SI-TK-2 11715-WMKS-SI-TK-2 2 1
10 6"-RC-39-1502-Q1 11715-WMKS-RC-E-2 1 11 6"-RC-38-1502-Q1 11715-WMKS-RC-E-2 1 12 6"-RC-37-1502-01 11715-WMKS-RC-E-2 1 37 27 %"-RC-3 2501-01 11715-WMKS-0109E-1 1 SW-39 12"-RC-22-1502-01 11715-WMKS-0109E-2 1 l
l SW-19 6"-RC-18-1502-01 11715-WMKS-0109F-2 1 SW-41 12"-RC-23-1502-01 11715-WMKS-0109F-2 1 SW-42 6"-RC-19-1502-01 11715 WMKS-0109F-2 1 i !
l l 11. IMPRACTICABLE CODE REQUIREMENTS The 1983 edition, Summer 1983 Addenda (inclusive) of ASME Section XI in Tables IWB-2500-1 and IWC-2500-1 does not allow any limitations to the required volumetric and surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%
]
Ill. BASIS FOR RELIEF l The components listed above have been examined to the extent practical as l required by the Code. Due to interferences of other components or weld joint '
geometry, the reduction in coverage for the listed components was greater than 10E Tables NDE-20-1, 2, 3, and 4 are provided detailing the limitations experienced. Amplifying sketches are also provided. Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code.
IV. ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.
Tebla NDE-20-1,. Rr,vi2 inn 2 .= -
North Anna Unit 1 Examination Coverage Estimates (Reactor Vessel)- ,
Category B-A, item B1.40 -
Mark / Weld # Beam Anale Exam Area Scan Direction %_Eram Reason For Partial Sketch!! -
1 (120- 240 ) 0 Weld & Base -
72 Joint Configuration 1 A & 18 l 45 Weld 2 13 And Lifting Lug 45 Weld 5 97 Interference 45 Weld 7 99 45 W eld 8 99 60 Weld 2 7 60 - W eld 5 98 60 W eld 7 99 60 Weld 8 99 45 & 60 Base 2 36 45 & 60 Base 5 91 45 & 60 Base '7 68 45 & 60 Base 8 68 Surface coverage 98%
UT Scan Direction Definitions 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circumferential scan, clockwise (looking down on head) 8 - Circumferential scan, counterclockwise (looking down on head)
Revision 2 March 23, 1995
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North Anna Unit 1 Examination Coverage Estimates (Vessels) ,
Category B-D, item B3.110 Mark / Weld # Beam Angle Exam Area Scan Direction % Exam Beason For Partial Sketch #
10,11,12 0 Weld & Base -
80 Nozzle Geometry, 2 45 Weld 2 85 Cladding Prevents 45 W eld 5 25 Extended V-path 45 Weld 7 100 45 W eld 8 100 60 Weld 2 90 60 W eld 5 15 60 W eld 7 100 60 We!d 8 100 45 & 60 Base 2 80 45 & 60 Base 5 35 45 & 60 Base 7 65 45 & 60 Base 8 65 UT Scan Direction Definitioits 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circumferential scan, clockwise (looking down on head) 8 - Circumferential scan, counterclockwise (looking down on head)
Revision 2, March 23, 1995
Tcblo NDE-20-3, R vici:n 2 -
North Anna Unit 1 Examination Coverage Estimates (Piping & Integral Attachments) ,
UT Scan Coverace % Surface Mark / Weld # Cateoorv Item # 2 5 Z H Coveraae % Reason For Partial Sketch #
37 B-J B9.11 75 0 90 90 100 Nozzle and Weld Geometry, Material Attenuation Prevent SW-39 B-J B9.31 90 0 27 27 100 Branch Connect Configuration 4 SW-19 B-J B9.31 90 0 27 27 100 Branch Connect Configuration 4 SW-41 B-J B9.31 90 0 27 27 100 Branch Connect Configuration 4 SW-42 B-J B9.31 90 0 27 27 100 Branch Connect Configuration 4 UT Scan Direction Definitions 2 - Axial scan,180 degrees from isometric flow direction (weld count).
5 - Axial scan, the same direction as the isometric flow (weld count).
7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.
Revision 2, March 23, 1995
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FLOV 6 -RC-19-1502-01
[SV-42)
V TYPICAL SV-19, SV-39 S V-41 AND SV-42 5 SIDE o N0ZZLE 180 29 -RC-4-2501 R-01 (SV-19) 2 SIDE 27 1/2"-RC-3-2501 R-01 FL0V . (SV;39 g, , -RC-6-2501 R-01
[SV-41 AND SV-42) i ( [/[/M SKETCH 4 1 1715-W M K S-109E-2 WELD SW-39 l l 715-WMKS-109F-2 WELDS SW-19, SW-41, & SW-42
Tcbl3 NDE-20-4, Rsvizien 2 .'
North Anna Unit 1 Examination Coverage Estimates (Boron injection Tank) ,
Category C-A, Item C1.20 -
Mark / Weld # Beam Anate Exam Area Scan Direction *f Exam Reason For Partial Sketch # -
1 (58"-116") 0 Wald & Base -
91 Support Legs 3 and 4 5 l 45 Weld 2 95 .g 45 W eld 5 82 45 W eld 7 100 45 W eld 8 100 60 W eld 2 99 60 Weld 5 78 60 W e!d 7 100 60 W eld 8 100 45 & 60 Base 2 98 45 & 60 Base 5 80 45 & 60 Base 7 (2 side) 100 45 & 60 Base 8 (2 side) 100 45 & 60 Base 7 (5 side) 87 45 & 60 Base 8 (5 side) 87 1
I UT Scan Direction Definitions 2 - Axial scan head side of weld 5 - Axial scan shell side of weld 7 - Circumferential scan, clockwise (lookirg down on tank) $
1 8 - Circumferential scan, counterclockwise (looking down on tank)
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l Revision 2, March 23, 1995
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ATTACHMENT 2 e North Anna Power Station Unit 1.
ASME Section XI Relief Request NDE-26 l
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NORTH ANNA UNIT 1 ;
RELIEF REQUEST NDE-26 l )
- 1. IDENTIFICATION OF COMPONENTS Mark / Weld # Line # Drawina # Class 4A 29"-RC-1 -2501 -01 11715-WMKS-0109E-1 1 N-SE29 IN 29"-RC-1-2501-01 11715-WMKS-RC-E-1 A.2P 1 5A 31"-RC-2-2501-01 11715-WMKS-0109E-1 1 N-SE31 IN 31"-RC-2-2501 -01 11715-WMKS-RC-E-1 A.2P 1 16A 29"-RC-4-2501-01 11715-WMKS-0109F-1 1 N-SE29 IN 29"-RC-4-2501-01 11715-WMKS-RC-E-18.2P 1 17A 31"-RC-5-2501 -01 11715-WMKS-0109F-1 1 N-SE31 IN 31 "-RC-5-2501 -Q1 11715-WMKS-RC-E-18.2P 1 28A 29"-RC-7-2501 -01 11715-WMKS-0109G-1 1 .
N-SE29 lN 29"-RC-7-2501 -01 11715 WMKS-RC-E-1C.2P 1 29A 31"-RC-8-2501 -Q1 11715-WMKS-0109G-1 1 N-SE31 IN 31 "-RC-8-2501 -01 11715-WMKS-RC-E-1C.2P 1
- 11. IMPRACTICABLE CODE REQUIREMENTS The 1983 edition, Summer 1983 Addenda (inclusive) of ASME Section XI in !
Table IWB-2500-1 does not allow any limitations to the required volumetric and '
surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than ,
10 % i Ill. BASIS FOR RELIEF ;
The components listed above have been examined to the extent practical as .
required by the Code. Longitudinal waves were used to perform the !
examination because of the materials involved (cast stainless steel and inconnel). However, the use of longitudinal waves prevents the use of beam :
extension to increase examination volume. Due to interferences of other components or weld joint geometry, the reduction in coverage for the listed ,
components was greater than 10% Table NDE-26-1 is provided detailing the ,
limitations experienced. Amplifying sketches are also provided. Alternative i components could not be substituted for examination due to the mandatory selection requirements of the Code. ;
IV. ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage '
be counted as meeting the Code requirements. t
Tcblo NDE-26-1 .
North Anna Unit 1 Examination Coverage Estimates
- UT Scan Coverage % Surface Mark / Weld # Cateaory item # 2 5 Z B- Coveraae % Reason For Partial Sketch #
N-SE-29 IN (A) B-F B5.70 8 100 100 100 100 Nozzle Geometry, Material Attenuation Prevent Extended V-Path 1 N-SE-31 IN (A) B-F B5.70 100 8 100 100 100 Nozzle Geometry, Material Attenuation Prevent Extended V-Path 1 N-SE-29 IN (B) B-F B5.70 8 100 100 100 100 Nozzle Geometry. Material Attenuation Prevent Extended V-Path 1 N-SE-31 IN (B) B-F B5.70 100 8 100 100 100 Nozzle Geometry, Material Attenuation Prevent Extended V-Path 1 N-SE-29 IN (C) B-F B5.70 8 100 100 100 100 Nozzle Geometry, Material Attenuation Prevent Extended V-Path 1 N-SE-31 IN (C) B-F B5.70 100 8 100 100 100 Nozzle Geometry, Material Attenuation Prevent Extended V-Path 1 4A B-J 89.11 100 70 75 75 100 Nozzle & Weld Crown Geometry, Material Attenuation Prevent Extended V-Path 2 5A B-J 89.11 91 94 80 80 100 Nozzle & Weld Crown Geometry, Material Attenuation Prevent Extended V-Path 2 16A B-J B9.11 100 62 90 90 100 Nozzle & Weld Crown Geometry, Material Attenuation Prevent Extended V-Path 2 17A B-J B9.11 62 100 90 90 100 Nozzle & Weld Crown Geometry, Material Attenuation Prevent Extended V-Path 2 28A B-J 89.11 78 100 90 90 100 Nozzle & Weld Crown Geometry, Material Attenuation Prevent Extended V-Path 2 29A B-J B9.11 83 100 90 90 100 Nozzle & Weld Crown Geometry, Material Attenuation Prevent Extended V-Path 2 i
UT Scan Direction Definitions I
! 2 - Axial scan,180 degrees from isometric flow direction (weld count).
l 5 - Axial scan, the same direction as the isometric flow (weld count).
7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.
Revision 2, March 23, 1995
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.1' Coverage from 62% to 100% Coverage from 78% to 100%
depending on transition of depending on transition of ,
weld buildup, weld buildup. See Table NDE-26-1. '
See Table NDE-26-1. ,f '
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SKETCH 2
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