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| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 5 | | | page count = 5 |
| | | project = TAC:L22113 |
| | | stage = RAI |
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| REQUEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING THE APPLICATION FOR THE NORTH ANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION (TAC NO. L22113) | | REQUEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING THE APPLICATION FOR THE NORTH ANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION (TAC NO. L22113) |
| I Deat Mr. O'Hanlon: | | I Deat Mr. O'Hanlon: |
| By letter dated May 9,1995, you submitted an application to the Nuclear Regulatory I Commission in accordance with 10 CFR Part 72 for the review and approval of a site-specific j license for an independent spent fuel storage installation (ISFSI) at the North Anna Nuclear Power Station site. | | By {{letter dated|date=May 9, 1995|text=letter dated May 9,1995}}, you submitted an application to the Nuclear Regulatory I Commission in accordance with 10 CFR Part 72 for the review and approval of a site-specific j license for an independent spent fuel storage installation (ISFSI) at the North Anna Nuclear Power Station site. |
| The staff has determined that additional information is required to determine compliance with 10 CFR Part 72. The attached RAI addresses the thermal design criteria of the fuel assemblies to be stored in the North Anna ISFSI and the concrete pad static analysis. You should note that I | | The staff has determined that additional information is required to determine compliance with 10 CFR Part 72. The attached RAI addresses the thermal design criteria of the fuel assemblies to be stored in the North Anna ISFSI and the concrete pad static analysis. You should note that I |
| as the staff review continues, it is likely that additional information will be needed to complete the review. | | as the staff review continues, it is likely that additional information will be needed to complete the review. |
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| Section 2.3.2.1 and Table 3.41 of the North Anna ISFSI SAR state that 800 g cal /cm' will be used as the design criterion for the storage casks. The North Anna ISFSI SAR uses the TN 32 as its design basis storage cask. However, the maximum solar heat load used in the TN 32 TSAR is 2950 BTU /ft' (800 g-cal /cm') for flat surfaces and 1474 BTU /ft2 (400 g cal /cm') for curved surfaces. The TN 32 cask was not analyzed for 800 g-cal /cm' on the curved surfaces, as might be inferred from Section 2.3.2.1 and Table 3.41. Therefore, it does not appear to meet the design criterion specified in the North Anna ISFSI SAR. | | Section 2.3.2.1 and Table 3.41 of the North Anna ISFSI SAR state that 800 g cal /cm' will be used as the design criterion for the storage casks. The North Anna ISFSI SAR uses the TN 32 as its design basis storage cask. However, the maximum solar heat load used in the TN 32 TSAR is 2950 BTU /ft' (800 g-cal /cm') for flat surfaces and 1474 BTU /ft2 (400 g cal /cm') for curved surfaces. The TN 32 cask was not analyzed for 800 g-cal /cm' on the curved surfaces, as might be inferred from Section 2.3.2.1 and Table 3.41. Therefore, it does not appear to meet the design criterion specified in the North Anna ISFSI SAR. |
| 1.2 Request Clarify the insolation design criterion used for the North Anna Spent Fuel Storage Cask and justify any deviation from the TN 32 TSAR design criterion. If the North Anna design criterion are different from the TN 32 TSAR design criterion, demonstrate that the TN 32 meets the North Ann design criterion. | | 1.2 Request Clarify the insolation design criterion used for the North Anna Spent Fuel Storage Cask and justify any deviation from the TN 32 TSAR design criterion. If the North Anna design criterion are different from the TN 32 TSAR design criterion, demonstrate that the TN 32 meets the North Ann design criterion. |
| 2.0 Maximum Decay Heat Design Criteria 2.1 Background Table 3/41 of the North Anna Technical Specifications lists a decay heat of 0.843 kw/ assembly whereas Table 3.1 1 of the North Anna ISFSI SAR, states that the maximum decay heat is specified in the storage cask TSAR. Virginia Power proposes to use the TN 32 as its storage cask at the North Anna ISFSI. | | 2.0 Maximum Decay Heat Design Criteria |
| | |
| | ===2.1 Background=== |
| | Table 3/41 of the North Anna Technical Specifications lists a decay heat of 0.843 kw/ assembly whereas Table 3.1 1 of the North Anna ISFSI SAR, states that the maximum decay heat is specified in the storage cask TSAR. Virginia Power proposes to use the TN 32 as its storage cask at the North Anna ISFSI. |
| The maximum decay heat listed in the TN 32 TSAR is 0.847 kw/ assembly, therefore, there is a discrepancy between these two tables. | | The maximum decay heat listed in the TN 32 TSAR is 0.847 kw/ assembly, therefore, there is a discrepancy between these two tables. |
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| 2.2 Request Change the North Anna ISFSI SAR and/or the Technical Specifications so that both give the same decay heat value. | | 2.2 Request Change the North Anna ISFSI SAR and/or the Technical Specifications so that both give the same decay heat value. |
| 3.0 Concrete Pad Static Analysis 3.1 Background T | | 3.0 Concrete Pad Static Analysis |
| Section 4.2.1.1 (static analysis) of the North Anna ISFSI SAR discusses the concrete storage pad design. | | |
| | ===3.1 Background=== |
| | T Section 4.2.1.1 (static analysis) of the North Anna ISFSI SAR discusses the concrete storage pad design. |
| 3.2 Request Provide the calculation packages of the static analysis to demonstrate that the cask i storage pad and areas have been designed to adequately support the static load of the i stored casks. | | 3.2 Request Provide the calculation packages of the static analysis to demonstrate that the cask i storage pad and areas have been designed to adequately support the static load of the i stored casks. |
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Letter Sequence RAI |
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MONTHYEARML20138K1271997-02-12012 February 1997 Requests Addl Info for Review of 950509 Application for Approval of site-specific License for ISFSI at North Anna Nuclear Power Station Site.Response Requested within 60 Days from Date of Ltr Project stage: Approval ML20217H5721997-10-0909 October 1997 Forwards Info Which Supports Use of NUREG/CR-0098,dtd May 1978,as Part of ISFSI Liquefaction Analysis,In Response to NRC Question Raised at 970505 Meeting Project stage: Meeting ML20202B0011997-11-24024 November 1997 Forwards Response to NRC 971105 RAI Re Util 970509 Application for Review & Approval of site-specific License ISFSI at Plant.Response to Item 5 Will Be Forwarded to NRC in Separate Correspondence within 30 Days Project stage: Request ML20203A8411997-12-0404 December 1997 Forwards Draft Reformatted Proposed North Anna ISFSI TS, According to Improved Std TS Format,For Review.Comments & Addl Proposed Changes Requested by 980130 Project stage: Draft Other ML20203J9981997-12-16016 December 1997 Forwards Response to Item 5 to NRC RAI Dtd 971104,re North Anna ISFSI License Application Project stage: Other ML20198H7391997-12-29029 December 1997 Forwards RAI Re Application for North Anna ISFSI for Fuel Assemblies to Be Stored in Plant ISFSI Project stage: RAI ML20199A4921998-01-16016 January 1998 Forwards RAI Which Addresses Thermal Design Criteria of Fuel Assemblies to Be Stored in North Anna ISFSI & Concrete Pad Static Analysis Project stage: RAI ML20199D9331998-01-23023 January 1998 Forwards Rev 21 to North Anna Power Station Emergency Plan & Rev 6 to Corporate Emergency Response Plan. Revs Reflect Addition of Isfsi.Rev 30 to EPIP-1.01, Emergency Manager Controlling Procedure, Encl Project stage: Other ML20203H9691998-02-13013 February 1998 Forwards RAI Re 950509 Application for Review & Approval of site-specific License for Isfsi.Rai Addresses Concrete Pad Design,Transporter Design,Cask Loading Operations & Record Keeping Requirements Project stage: RAI ML20203B4071998-02-17017 February 1998 Forwards Response to 980116 RAI Re Application for Review & Approval of site-specific License for ISFSI Project stage: Request ML20216F7781998-04-13013 April 1998 Forwards Summary of Required Changes to Plant UFSAR Associated W/Isfsi Operation.Identified Changes Have Been Approved by Plant Nuclear Safety & Operating Committee & Do Not Constitute Unreviewed Safety Question Project stage: Other ML20217F0461998-04-23023 April 1998 Forwards Response to RAI Re North Anna ISFSI for Concrete Pad Design,Transporter Design,Cask Loading Operations & Record Keeping Requirements Project stage: Response to RAI ML20236H5081998-05-29029 May 1998 Responds to 980518 RAI Re Application for Review & Approval of site-specific License for ISFSI at Naps.Listed Commitments Made to Ltr Project stage: Request ML20248K9121998-06-0808 June 1998 Forwards Preliminary SER for North Anna Nuclear Power Station Isfsi,Per Util 950509 Submittal of Application for ISFSI Project stage: Other ML20236H4471998-06-30030 June 1998 Informs That Attachments to 980529 Response to NRC 980518 RAI Re Application for Review & Approval of site-specific License for ISFSI at NAPS May Be Placed in PDR Project stage: Request ML20236M6571998-07-0707 July 1998 Submits Preoperational Test Acceptance Criteria & Test Results for North Anna ISFSI Construction.Preoperational Test Results Acceptable Project stage: Other 1998-01-23
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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:OUTGOING CORRESPONDENCE
MONTHYEARML20212J9101999-10-0101 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 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 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 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 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 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 ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity 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 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 ML20206P6401999-05-0505 May 1999 Refers to Public Meeting Conducted at North Anna Power Station on 990413 to Discuss Results of North Anna Plant Performance Review.List of Attendees Encl ML20205S0321999-04-21021 April 1999 Forwards SER Accepting Util 980804 Requests for Relief from Certain Requirements of Subsections IWE & Iwl of 1992 Addenda of ASME Section Xi.Alternatives for IWE2,IWE4,IWE6 & IWL2,authorized Pursuant to 10CFR50.55a(a)(3)(ii) ML20205Q2451999-04-12012 April 1999 Forwards Insp Repts 50-338/99-01 & 50-339/99-01 on 990131- 0313.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20205T1411999-04-0909 April 1999 Informs That on 990407,A Royal & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Dates Scheduled for Wks of 000925 & 1002 for Approx 11 Candidates ML20196K9891999-03-29029 March 1999 Confirms Plans to Hold Meeting on 990413 at North Anna Nuclear Information Center to Discuss North Anna Plant Performance Review ML20205B5641999-03-24024 March 1999 Forwards Audit Rept of North Anna Power Station,Units 1 & 2 Conducted on 990126-28 in Glen Allen,Va.Audit Team Assessment of Y2K Project Plan Identified Plan as well-structured,well Organized & Well Implemented ML20196L0021999-03-24024 March 1999 Discusses Plant Performance Review of North Anna Power Station Completed by NRC on 990205.Found Overall Performance at North Anna to Be Acceptable.Several Examples of Inadequate or Untimely Problem Resolution Were Noted ML20207E1331999-03-0101 March 1999 Forwards Insp Repts 50-338/98-11 & 50-339/98-11 on 981220- 990130.No Violations Noted.Util Conduct of Activities at North Anna Power Station Generally Characterized by Safety Conscious Plant Operations & Good Maintenance ML20203F8681999-02-16016 February 1999 Forwards Request for Addl Info Re Util 970527 plant-specific Summary Rept in Response to USI A-46 Program at North Anna Power Station,Units 1 & 2 ML20196K3681999-01-21021 January 1999 Discusses Closure of Tasks Re Generic Implication of part- Length Control Rod Drive Mechanism Housing Leak at Prairie Island,Unit 2 & Anna Power Station,Units 1 & 2 ML20199K3221999-01-14014 January 1999 Forwards Insp Repts 50-338/98-10 & 50-339/98-10 on 981108- 1219.No Violations Identified.Conduct of Activities at North Anna Power Station Generally Characterized by safety-conscious Plant Operations ML20198S3921999-01-0606 January 1999 Forwards Request for Addl Info on Resolution of USI A-46 for North Anna Power Station,Units 1 & 2 IR 05000338/19980051999-01-0606 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/98-05 & 50-339/98-05 on 981105 ML20198H8951998-12-22022 December 1998 Forwards Corrected Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval & Se.Authorization Ltr Erroneously Dtd as 981103 & End Dates of Second 10-yr Insp Intervals Incorrect ML20198P0401998-12-14014 December 1998 Refers to 981210 Open Meeting at Licensee Request at Region II Re Weld Discrepancies Identified on Various Auxiliary Feedwater Sys Pipe Supports During Safety Sys Engineering Insp.List of Attendees & Util Presentation Handouts Encl ML20196J5591998-12-0808 December 1998 Submits Correction to Transmittal Ltr ,which Forwarded SE Authorizing Licensee Relief Request Re Rev to NDE-32, Svc Water Sys Leaks, Per 10CFR50.55a(a)(3)(ii). Corrected Date Should Be 981203 ML20198A7491998-12-0404 December 1998 Confirms 981203 Telcon Between L Hart of Licensee Staff & V Mccree of NRC Re Meeting Scheduled for 981210 in Atlanta, Ga Concerning Pipe Support Potential Construction Errors or Drawing Errors ML20198H9341998-12-0303 December 1998 Forwards SE Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant,Per Util 970224 Relief Request ML20196G9431998-12-0202 December 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting,Completed on 981102.Details of Insp Plan for Next 4 Months Encl ML20196A6581998-11-25025 November 1998 Forwards Notice of Withdrawal of 960321 Application for Amends to Licenses NPF-4 & NPF-7 for Plant.Changes Would Have Clarified Requirements for Testing Charcoal Absorbent in Waste Gas Charcoal Filter Sys ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20196H3951998-11-0505 November 1998 Forwards Insp Repts 50-338/98-05 & 50-339/98-05 on 980713- 17,27-31 & 0921-25 & Notice of Violation & Re Failure to Implement Adequate Corrective Actions to Resolve Corrosion of AFW Tunnel Pipe Supports Identified in Sept 1996 ML20196G1161998-11-0303 November 1998 Forwards Safety Evaluation Authorizing Rev to ISI Program Relief Reuest NDE-32 Re SWS Leaks,Submitted on 980224,for Remainder of Second 10-yr Insp Interval for Each Unit ML20155H8061998-10-29029 October 1998 Responds to Discussing NRC Initiatives & Efforts. Plans for Another Stakeholders Meeting Underway for 981113. Staff Will Continue to Solicit Feedback & Comments from Public on Initiatives ML20154Q8331998-10-21021 October 1998 Informs That Info Submitted in 980911 Application & Affidavit Re WCAP-15063-P, W In-Reactor Creep Model, Marked Proprietary,Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20154G3611998-10-0707 October 1998 Informs That Util 951018,960722 Responses to Anomalies Identified in SER Dtd 950924,acceptable & Subject to NRC Inspection.Request for Relief from Valve Quarterly Tests & Proposal to Extend Test Interval,Not Acceptable ML20155B0531998-10-0202 October 1998 Forwards Exam Repts 50-338/98-301 & 50-339/98-301 on 980817- 21 & 31-0903.Fourteen Candidates Passed & One Failed Exam ML20155B3741998-09-25025 September 1998 Cancels Meeting Which Was Scheduled for 981109.Purpose of Meeting Was to Discuss SALP for North Anna Power Station. Informs That NRC Has Suspended SALP Program Until Staff Completes Review of NPP Performance Assessment Process ML20239A3801998-09-0202 September 1998 Confirms 980819 Telephone Conversation Between D Summers & L Garner Re Meeting at NRC Request Which Has Been Scheduled for 981109.Purpose of Meeting Will Be to Discuss SALP for North Anna Power Station ML20151T9351998-08-27027 August 1998 Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Novs. Licensee NOV Responses Which Accept Violations & Require No Addl Communication to Be Ack in Cover Ltr of Next Insp Rept ML20237E0111998-08-25025 August 1998 Discusses Completion of Licensing Action for GL 97-05, Steam Generator Tube Insp Techniques, ML20151T5531998-08-18018 August 1998 Forwards Insp Repts 50-338/98-07 & 50-339/98-07 on 980720-23.No Violations Noted.Insp Observed Selected Portions of Emergency Organization Response in Key Facilities During EP Plume Exposure Exercise IR 05000338/19980011998-08-0404 August 1998 Discusses Re Insp Rept Review & Three Clarifications Re Insp Repts 50-339/98-01 & 50-338/98-01 Discussions of Security at ISFSI ML20237B0001998-07-30030 July 1998 Confirms 980728 Telcon Between D Sommers & R Haag Re Meeting Scheduled for 980810 in Atlanta,Ga to Discuss Recent Mgt Changes & Items of Interest ML20236M0291998-07-0808 July 1998 Forwards Request for Addl Info Re ASME Section XI Relief Requests NDE-37,through NDE-41 for North Anna Power Station, Unit 1 ML20236K5451998-07-0707 July 1998 Forwards SER Accepting Proposed Change in Commitment on Inservice Insp Program for Protection Against Dynamic Effects Associated W/Postulated Rupture of High Energy Main Steam & Feedwater Piping,In Mechanical Equipment Room ML20236F7311998-06-29029 June 1998 Forwards Request for Addl Info Related to Fire,Seismic & High Wind,Flood & Other External Events Areas of IPEEE Submittal IR 05000338/19980021998-06-25025 June 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/98-02, 50-339/98-02 & 72-0016/98-02 ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20248M0381998-06-0909 June 1998 Forwards Request for Addl Info Re Revised Loop Stop Valve Operation.Changes Will Modify Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves 1999-09-08
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January 16, 1998
, NIr. James P. O'Hanlon Senior Vice President Nucleer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING THE APPLICATION FOR THE NORTH ANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION (TAC NO. L22113)
I Deat Mr. O'Hanlon:
By letter dated May 9,1995, you submitted an application to the Nuclear Regulatory I Commission in accordance with 10 CFR Part 72 for the review and approval of a site-specific j license for an independent spent fuel storage installation (ISFSI) at the North Anna Nuclear Power Station site.
The staff has determined that additional information is required to determine compliance with 10 CFR Part 72. The attached RAI addresses the thermal design criteria of the fuel assemblies to be stored in the North Anna ISFSI and the concrete pad static analysis. You should note that I
as the staff review continues, it is likely that additional information will be needed to complete the review.
You are requested to respond in a time frame that is consistent with your proposed licensing l and loading schedule and yet which allows the staff ample time to complete its review. Please l reference the Docket No. and the abc' e TAC No. In future correspondence related to this request.
If you have any comment or question concerning this request, please contact me at 301 415 1428.
T I
Sincerely, '
l
[ original signed by /s/]
Joseph W. Shea, Project Manager '
Spent Fuel Licensing Section (I ;
9801270230 990116 Spent Fuol Project Office !
PDR ADOCK 05000338 Office of Nuclear Mawrial Safety y PDR and Safeguards Dockets 7216 (50 338/339) h{ g
Enclosure:
Request for AdditionalInformation cc: Service List ll l l ll ll ll ll Distribution: (Control No. 010S)
Dockets NRC File Center PUBLIC NMSS r/f SFPO r/f SFLS r/l CHaughney SShankman SWhaley WReamer, OGC ii NKalyanam, NRR WGloersen, Ril EMcAlpine, Ril --
OFC SFPOh E SFPO E SFPO .
E SFPO /E s NAME IS h VTharpe FSturz b uh ems &
DATE Oil /98 01/ 198 01//4 /9 0 11 / [
C = COVER E = COVER & ENCLOSURE N = NO COPY 01/16/98 :dd OFFICIAL RECORD COPY G:\ NORTH _AN\l22113.RA5
REQUEST FOR ADDITIONAL INFORMATION This document, titled Request for Additional information (RAl), contains a compilation of additional information requirements, identified to-date by the U.S. Nuclear Regulatory Commission staff, during its review of the applicant's application and Safety Analysis Report
- (SAR). This RAI follows the same format of tne applicant's SAR.
Each individual RAI describes information needed by the staff for it to complete its review of the application and/or the SAR and to determine whether the applicant has demonstrated compliance with the regulatory requirements. Where an individual RAI relates to the applicant's apparent failure to meet one or more regulatory requirements, or where an RAI specifically focuses on compliance issues associated with one or more specific regulatory requirements (e g., specific design criteria or accident conditions), such requirements will be specified in the individual RAl.
) ,
I ENCLOSURE l l A
RE: Fuel Assemblies to Be Stored in the North Anna Independent Spent Fuel Storage Installation (ISFSI)
The following regulatory requirements are applicable: 10 CFR 72.26,72.44, and 72.212. It should be noted that other regulatory requirements may be applicable to this section.
1.0 Insolation Design Criteria 1.1 Background i Sectica 2.3.2.1 of the North Anna ISFSI Safety Analysis Report (SAR) states that the insolation data from Regulatory Guide 7.8 is 800 g cal /cm' per day for a horizontally transported cask and that the Regulatory Guide defines the design insolation as 400 g cal /cm' per day for stationary and vertically stored casks. Regulatory Guide 7.8 uses the insolation data given in 10 CFR 71.71(c)(1) which is not as stated in the North Anna ISFSI SAR.
Section 2.3.2.1 and Table 3.41 of the North Anna ISFSI SAR state that 800 g cal /cm' will be used as the design criterion for the storage casks. The North Anna ISFSI SAR uses the TN 32 as its design basis storage cask. However, the maximum solar heat load used in the TN 32 TSAR is 2950 BTU /ft' (800 g-cal /cm') for flat surfaces and 1474 BTU /ft2 (400 g cal /cm') for curved surfaces. The TN 32 cask was not analyzed for 800 g-cal /cm' on the curved surfaces, as might be inferred from Section 2.3.2.1 and Table 3.41. Therefore, it does not appear to meet the design criterion specified in the North Anna ISFSI SAR.
1.2 Request Clarify the insolation design criterion used for the North Anna Spent Fuel Storage Cask and justify any deviation from the TN 32 TSAR design criterion. If the North Anna design criterion are different from the TN 32 TSAR design criterion, demonstrate that the TN 32 meets the North Ann design criterion.
2.0 Maximum Decay Heat Design Criteria
2.1 Background
Table 3/41 of the North Anna Technical Specifications lists a decay heat of 0.843 kw/ assembly whereas Table 3.1 1 of the North Anna ISFSI SAR, states that the maximum decay heat is specified in the storage cask TSAR. Virginia Power proposes to use the TN 32 as its storage cask at the North Anna ISFSI.
The maximum decay heat listed in the TN 32 TSAR is 0.847 kw/ assembly, therefore, there is a discrepancy between these two tables.
2
2.2 Request Change the North Anna ISFSI SAR and/or the Technical Specifications so that both give the same decay heat value.
3.0 Concrete Pad Static Analysis
3.1 Background
T Section 4.2.1.1 (static analysis) of the North Anna ISFSI SAR discusses the concrete storage pad design.
3.2 Request Provide the calculation packages of the static analysis to demonstrate that the cask i storage pad and areas have been designed to adequately support the static load of the i stored casks.
3 l
{
l
,o Mr. J. P. O'Hanlon North Anna Power Station Virginia Electric & Power Company Units 1 and 2 cc:
Mr. William C. Porter, Jr. Robert B. Strobe, M.D., M.P.H.
County Administrator State Health Commissioner Louisa County Office of the Commissioner >
P.O. Box 160 Virginia Department of Health Louisa, Virginia 23093 P.O. Box 2448 Richmond, Virginia 23218 MichaelW. Maupin, Esquire Hunton and Williams Regional Administrator, Region 11 Riverfront Plaza, East Tower U.S. Nuclear Regulatoc, Commission 951 E. Byrd Street Atlanta Federal Center Richmond, Virginia 23219 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 3415 Dr. W. T. Lough Virginia State Corporation Mr. W. R. Matthews, Manager Commission i North Anna Power Station Division of Energy Regulation P. O. Box 402 P. O. Box 1197 Mineral, Virginia 23117 Richmond, Virginia 23209 Mr. Al Belisle Old Dominion Electric Cooperative U.S. Nuclear Regulatory Commission 4201 Dominion Blvd. Atlanta Federal Center Glen Allen, Virginia 23060 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 3415
- Mr. James H. McCarthy, Manager l Nuclear Licensing & Operations Mr. David Christian, Manager Support Surry Power Station Virginia Electric and Power Company Virginia Electric and Power Company Innsbrook Technical Center 5570 Hog Island Road 5000 Domin;on Blvd.
Surry, Virginia 23883 Glen Allen, Virginia 23060 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident inspector North Anna Power Station U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117
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