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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
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e VIRGINIA ELECTRIC AND POWEH COMPANY HICliMOND,YIHOINIA 20061 Febr.tary 6, 1997 1
l Document Control Desk Serial No.97-027 U. S. Nuclear Regulatory Commission NLOS/ETS: R1 Washington, D. C. 20005 Docket No. 50-339 License No NPF-7
Dear Sir:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2
, SECOND INTERVAL INSERVICE INSPECTION PROGRA_lf ADDITIONAL INFORMATION ASME RELIEF REQUEST By letter dated December 7,1995 (Serial No.95-602), Virginia Electric and Power Company requested the use of Code Cases N-522 and N-535. In a subsequent letter dated June 10,1996 (Serial No. 95-602A), the request to use Code Case N-535 was withdrawn and the request for use of Code Case N-522 was revised and submitted as Relief Request SPT-16 for Unit 2 only. The NRC Staff requested additionalinformation to complete the review of the relief request. Relief Request SPT-16 has been revised to include the additional conditions and is provided in the Attachment to this letter.
This letter is not intended to establish any additional commitments. Should you have any questions or require additional information, please contact us. l 4
4 Very truly yours, 24d&
R. F. Saunders, Vice President [
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Nuclear Engineering and Services p , ; if, r
- Attachment ,
i 970210049G 970206 PDR ADOCK 05000339 G PDR
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- cc: United States Nuclear Regulatory Commission !
- Regional Administrator !
l Region ll l 101 Marietta Street, N. W Suite 2900 l
Atlanta, Georgia 30323 s
1 l Mr. R. D. McWhorter l NRC Senior Resident inspector j
! North Anna Power Station :
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1 ATTACHMENT 1 l REVISED RELIEF REQUEST SPT-16 NORTH ANNA POWER STATION UNIT 2 l
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Virginia Electric & Power Company North Anna Unit 2 Second 10-Year Interval Request for Relief No. SPT-16, Revision 2 I. IDENTIFICATION OF COMPONENTS Class 2 piping that penetrates the containment vessel where the piping and isolation valves are part of the containment system but the balance of the piping is outside of the scope of Section XI.
Drawing Test boundary Penetration Number 120!,0-SPM-096A 2 SH. 3 1"-SI-450-1502-01, 3"-SI-567-1502-01 7 between 2-SI-MOV-2867D and 3"-SI-568-1502-01, 3"-SI-568-1502-01 between 2-SI- l 2867C and 3"-SI-4171502-01, 3*-SI-417-1502 01 between 3" SI-568-1502 01 and i penetration 7 j 12050-SPM-096B-2 SH. 4 3"-SI-417-1502-01 between 2-SI-93 and 7 penetration 7 )
12050-SPM-079B-2 SH. 3 6"-CC-752-151-02 13 i 12050-SPM-095C-2 SH.1 3"-CH-479-1502-01 between 2-CH MOV- 15 2289A and 2-CH-335 12050-SPM-0958-2 SH.1 3* CH-499-153A-01 between 2-CH-MOV-2381 19 and penetration 19 12050-SPM-095C-2 SH. 2 3"-CH-499-153A-01 between 2-CH-MOV-2380 19 and penetration 19 and %"-CH-799-153A-01 between 2-CH-331 and penetration 19 l l
12050-SPM-096A-2 SH.1 1"-SI-413-602-02 between penetration 20 and 20 l 2-SI-47 12050-SPM-0968-2 SH.1 1" SI-413-602-02 between 2-SI-136 and 20 penetration 20 12050-SPM-096A-2 SH. 3 3"-SI-538-1502-01 between 2-St-MOV-2836 22 and penetration 22 12050-SPM-096B-2 SH. 4 3"-SI-538-1502-01 between 2 SI-85 and 22 penetration 22 12050-SPM-079A-2 SH. 2 8"-CC-678-151-02 25 12050-SPM-079A 2 SH. 4 8"-CC-688-151-02 26 12050-SPM-079A-2 SH. 3 8"-CC-739-151 -02 27 12050-SPM-090A-2 SH 1 2"-DG-435-153A-02 33
Drawing Test boundary Penetration Nurnber 12050-SPB-104B-2. SH.1 4" line between 2-FP-79 and 2-FP-82 34 12050-SPM-082B-2 SH. 2 1"-ARC-401-153A-Q2 between 2-RM-TV-200D 43 and 2-IA-428 12050-SPM-0828-2 SH. 2 1"-ARC-402153A-Q2 between 2-RM-TV-2008 44 and 2-RM-TV-200C 12050-SPM-0938-2 SH. 2 3"-RC-452-153A-Q2 between 2-RC-2519A to 45 2-RC-162 12050-SPM-095C-2 SH.1 2"-CH 666-1502-02 between 2-CH-332 and 2- 46 CH-FCV 2160 12050-SPM-082A-2 SH.1 2"-ACC-421-153A-Q2 between penetration 47 47 and 2-IA-250 12050-SPM-082B-2 SH.1 2"-ACC-421-153A-Q2 between penetration 47 47 and 2-lA-TV-202B 12050-SPM-096B-2 SH.1 1"-SI-498-601-Q2 between 2-SI-HCV-2936 50 and 2-SI TV-201 12050-SPM-096B-2 SH.1 1"-SI-517-1501 02 between 2-SI-132 and 2- 53 SI-TV-200 12050-SPM-089B-2 SH. 2 %"-SS-749-ICN9-Q1 between 2-SS-TV-206A 56B and 2-SS-TV 206B 12050-SPM-089B-2 SH. 2 %"-SS-750 lCN9-01 between 2-SS-TV-202A 56C and 2-SS-TV-202B 12050 SPM-089A-2 SH. 3 %"-SS-622-ICN9-Q2 between 2-SS-TV-212A 56D and 2-SS-TV-2128 12050-SPM-089B 2 SH.1 %"-SS-402-ICN9 02 between 2-SS-TV-201 A 57C and 2-SS-TV-201B 12050-SPM-096A 2 SH. 2 10" SI-415-1502-01 and 6*-SI-416-1502-01 60 12050-SPM-096B-2 SH. 4 6"-SI-416-1502-01 between 2-SI-126 and 60 penetration 60 12050-SPM-096A-2 SH. 2 10"-SI 4641502-01 and 6"-SI-421-1502-01 .61 12050-SPM-096B-2 SH. 4 6*-SI-421-1502-Q1 between 2-SI-128 and 61 penetration 60 12050-SPM-096A-2 SH. 2 6*-SI-531-1502-Q1,10*-SI-418-1502-01, and 62 10"-SI-624-1502-01 12050-SPM-096B-2 SH. 4 6"-SI531-1502-01, 6"-S1-532-1502-01 62 be. tween 6*-SI-531-1502-01 and 2-SI-105, and 6"-SI-533-1502-01 between 6"-S1-531-1502-Q1 and 2 SI 99
Drawing Test boundary Penetration Number 12050-SPM-096B-2 SH. 2 8"-OS-439-153A-02 between 2-OS MOV-2018 63 I
and 2-OS-22 12050-SPM-096B-2 SH. 2 8"-OS-437-153A-02 between 2-OS-MOV- 64 !
201 A and 2-OS-11 f
12050-SPM-091 A-2 SH. 4 12"-RS-407-153A-Q2 and 8"-RS-J73-153A-02 66 12050-SPM-091 B-2 SH.1 8"-RS-J73-153 A-02, 4"-RS-4 57-153 A-02, 8"- 66 RS-456-153A-02, and 6"-RS-J82-153A-02 12050-SPM-091 A-2 SH. 4 12"-RS-408-153A-02 and 8"-RS-J74-153A-Q2 67 12050-SPM-091B-2 SH.1 8"-RS-J74-153 A-02, 4"-RS-461-153 A-02, 8"- 67 RS-460-153A-Q2, and 6"-RS-J83153A-Q2 12050-SPM-091 A-2 SH. 4 10"-RS-410-153A-Q2 between 2-RS-MOV- 70 256B and 2-RS-30 ;
12050-SPM-091 A-2 SH. 4 10"-RS-409-153A-02 between 2-RS-MOV- 71 l 256A and 2-RS-20 l 11715 SPM-0788-2 SH. 3 16" WS-627151-02 between 2-SW-MOV- 79 ,
203D and 2-SW-104 I 11715-SPM-0788-2 SH. 3 16"-WS-625-151-02 between 2-SW-MOV- 80 203C and 2-SW 94 11715-SPM-078B-2 SH. 3 16*-WS-623-151-02 between 2-SW-MOV- 81 203B and 2-SW-84 I 11715-SPM-0788-2 SH. 3 16*-WS-621-151-02 between 2-SW MOV- 82 203A and 2-SW-74 l 11715-SPM-078B-2 SH. 3 16"-WS-622-151-02 83 11715-SPM-0788-2 SH. 3 16"-WS-624-151-02 84 11715-SPM-078B-2 SH. 3 16"-WS-626-151-02 85 '
11715-SPM-0788-2 SH. 3 16"-WS-628-151-02 86 12050-SPM-072A-2 SH. 2 6"-AJA-410-151-02 89 11715-SPM-106A-2 SH. 3 %"-HC-75-lCN9-02 between 2-HC-TV-200A 98A and 2 HC-TV-2008 11715-SPM-088A-2 SH. 3 6"-RP-454-152-02 and 6"-RP-444-153 A-02 103 11715-SPM-088A-2 SH. 3 6"-RP-449-152-02 104 11715-SPM-106A-2 SH. 2 %"-HC-413-lCN6-02 between 2-HC-TV-203B 109 and 2-HC-3-154-02, and 2 %"-HC-440-154-02 between 2"-HC-3-154-02 and 2-HC-TV-207B, and 2-HC-3-154-Q2 12050-SPM-096A-2 SH. 3 3"-SI-457-1502-01 113
Drawing Test boundary Penetration Number 12050-SPM-0968-2 SH. 4 3* SI-457-1502-01 between 2-St-119 and 113 penetration 113 i
12050-SPM-096A-2 SH. 3 3"-SI-539-1502-01 114 1 12050-SPM-096B-2 SH. 4 3"-SI-539-1502-01 between 2-SI-107 and 114 penetration 114 II. IMPRACTICABLE CODE REQUIREMENTS l l
Table IWC-2500-1, Examination Category C-H, Items C7.30 and j C7.70 requires a system pressure test each inspection period and Items C7.40 and C7.60 requires a system hydrostatic test each inspection interval.
III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED 1
Relief is requested from performing the Code-required hydrostatic test at the end of the inspection interval and the !
Code-required system pressure test during each period for the l containment penetrations listed.
IV. BASIS FOR RELIEF The sole safety function of the piping and associated valves listed is to provide containment isolation. The components listed are part of the containment system. Containment penetrations are classified as Class 2 per ANSI 18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants", section 2.3.1.2 (1). For the subject penetrations the connecting piping beyond the containment isolation valves serves no safety function and is classified as nonclass by the classification criteria used by Virginia Electric and Power Company for North Anna Unit 2.
The ASME Section XI pressure testing requirements have verified leak-tight integrity by an over pressure test every ten years and a nominal operating test every inspection period. The 10-year hydrostatic tests were considered inordinately burdensome for the margi nal benefit in safety they assure and have been eliminated by Code Case N-498,
" Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems,Section XI, Division 1", which has been approved by Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability ASME Section XI Division 1. The 10-Year hydrostatic test is now conducted at nominal operating pressure.
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1 The subject penetrations are Type C pressure tested to a peak containment internal pressure of greater than or equal to 44.1 psig. This test is performed to satisfy Technical Specification Surveillance Requirement 4.6.1.2 which requires i all containment penetrations to be leak rate tested as I required by 10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and in accordance with the guideline contained in Regulatory Guide 1.163, dated September 1995.
The testing frequency of 10 CFR 50, Appendix J, Option B is ,
l performance based and can vary from 2 years to 5 years or i three refueling cycles. This frequency will not coincide with the inspection period frequency required in Table IWC-2500-1 for system pressure tests and therefore, the ASME Code in effect at North Anna will require additional leak tightness testing.
The ASME Section XI Code has acknowledged that testing of these components beyond the requirements of Appendix J is not necessary and issued Code Case N-522, " Pressure Testing of Containment Penetration Piping", to define its position.
NUREG-1493, " Performance-Based Containment Leak-Test Program",
concluded that prescriptive leak rate testing could be replaced with performance based requirements with only a marginal and acceptable impact on safety. The total cost of Type B (electrical penetrations) and Type C testing all i containment penetrations (approximately 90 penetrations) was i estimated to be $87,500 per outage for North Anna as reported '
in NUREG-1493. NUREG-1493 estimates that 5% of the total cost of Type B & C testing could be saved if the acceptance criteria were relaxed. Performing ASME Section XI pressure testing beyond the requirements of 10 CFR 50, Appendix J, Option B testing would cause Virginia Electric & Power Company to incur additional cost with a marginal gain in safety.
V. PROPOSED ALTERNATIVE As an alternative to the testing frequency and pressurec required by Table IWC-2500-1, Examination Category C-H, Items C7.30, C7.40, C7.60, and C7.70, the subject penetrations and associated piping and valves, will be pressure tested at peak containment calculated pressures to the requirements of 10 CFR Appendix J, as allowed by Code Case N-522. Testing will be performed in accordance with Technical Specification Surveillance Requirement 4.6.1.2 which requires all containment penetrations to be leak rate tested as required by 10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and in accordance with the guideline contained in Regulatory Guide 1.163, dated September 1995.
Methods for the detection and location of leakage at containment isolation valves and the pipe segments between the containment isolation valves will be identified in procedures.
All subject penetrations will be Type C tested at least once every 60 months.
. 4 VI. IMPLEMENTATION SCHEDULE The Technical Specifications were revised on 2/9/96 to incorporate 10 CFR 50, Appendix J, Option B. The subject containment penetratiors were Type C tested in the second period. The third period starts on 12/14/97. Test intervals for valves having two consecutive periodic As-found Type C tests where the results are within the allowable administrative limits may be increased up to a maximum of 60 months. The subject valves have satisfied this criteria and are not scheduled to be tested during the third period.
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