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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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Wenq p k UMTED STATES s*
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001
<Q***** February 12, 1997 Mr. James P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center Jo43P/U7 5000 Dominion Boulevard Glen Allen, VA 23060 SU6 JECT: REQUEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING THE APPLICATION FOR THE NORTH ANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION (TAC NO. L22113)
Dear Mr. O'Hanlon:
By letter dated May 9, 1995, you submitted an application to the Nuclear Regulatory Commission in accordance with 10 CFR Part 72 for the review and approval of a site-specific 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. You should be aware that the enclosed request for additionel information (RAI) may be the first in a series of information solicitations to which you will have to respond. You should prepare and submit your response to this request within 60 calendar days from the date of this letter.
Although the staff determined that sufficient information was submitted to initiate its review, the staff is concerned that some information was either l lacking or insufficiently presented. In particular, the staff has concerns !
regarding the proposed site's design earthquake as well as analyses presented I in the safety analysis report (SAR) regarding cask sliding and tipping. The staff encourages you to ensure that the responses to these and other aspects of this RAI are given thorough and accurate review prior to submittal to the NRC.
Some topical areas do not have any RAI items. This should not be interpreted that the staff will not have future questions in these areas. Some topical areas (e.g., quality assurance) will be subject to subsequent inspection activity.
It is incumbent upon you to determine if information submitted in response to this RAI is proprietary. If it is necessary to submit proprietary information, you are required to submit the appropriate affidavit in accordance with 10 CFR 2.790. Finally, Office of Management and Budget approvals regarding information collection requirements are delineated in 10 CFR 72.9.
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9702140263 970212 PDR Y
ADOCK 05000338 PDR NRC FILE CENTER COPY
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J.P. O'Hanfon ; ,
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As before, please r'eference the-TAC number noted above in future correspondence related to this licensing action. If you have any comment or )
question concerning this r.equest, please contact me at 301-415-8549. '
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[ t, Sincerely, l Original signed by /s/
Margaret E. Lusardi, Project Manager Spent Fuel Licensing Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket No. 72-16 (50-338/339)
Enclosure:
Request for Additional Information cc: Service List Distribution: (Control No. 010S) !
Dockets 72-16, 50-338/-339 NRC File Center. PUBLIC NHSS r/f l SFP0 r/f CHaughney SShankman WKane WReamer, 0GC l EKeegan KCleu S0' Conner VTharpe GEdison, NRR BWood, NRR WGloersen, RII l OFC SFP0 E SFPQ C SFP0 M-NAME MLusa M yt:dd FJhh EJLeeds d u '
l DATE 2/// /97 2)f /97 2/ /I /97 ;
C = COVER E = COVER & ENCLOSURE N = NO COPY 1 0FFICIAL RECORD COPY G:\ NORTH _AN\RAI.ONE !
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Mr. William C. Porter, Jr. Regional Administrator, Region II County Administrator U.S. Nuclear Regulatory Commission ;
Louisa County 101 Marietta Street, N.W., !
P.O. Box 160 Suite 2900 '
Louisa, Virginia 23093 Atlana, Georgia 30323 Michael W. Maupin, Esquire Mr. J. A. Stall, Manager !
Hunton and Williams North Anna Power Station !
Riverfront Plaza, East Tower P. O. Box 402 i 951 E. Byrd Street Mineral, Virginia 23117 )
Richmond, Virginia 23219 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation l P. O. Box 1197 Richmond, Virginia 23209 Old Dominion Electric Cooperativs 4201 Dominion Blvd. l Glen Allen, Virginia 23060 4
Mr. M. L. Bowling, Manager Nuclear Licensing & Programs Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
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 Route 2 Box 78 i
Mineral, Virginia 23117 Robert B. Strobe, M.D. , M.P.H.
l State Health Commissioner l Office of the Commissioner
- Virginia Department of Health P.O. Box 2448
- Richmond, Virginia 23218 i
. i l REQUEST FOR ADDITIONAL INFORMATION This document, titled Request for Additional Information (RAI), 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 as the applicant's SAR.
I 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 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 are specified in the individual RAI. '
This RAI is organized as follows:
Chapter 1.0 Introduction and General Description of Installation Chapter 2.0 Site Characteristics Chapter 3.0 Principal SSSC Design Criteria Chapter 4.0 Storage System l Chapter 5.0 Storage System Operations i
Chapter 6.0 Waste Management Chapter 7.0 Radiation Protection
! Chapter 8.0 Accident Analysis Chapter 9.0 Conduct of Operations Chapter 10.0 Operating Controls and Limits Chapter 11.0 Quality Assurance TS Technical Specifications FAD Financial Assurance and Decommissioning l
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ENCLOSURE
Chapter 1.0 Introduction and General Description of Installation The following regulatory requirements are applicable to the RAIs in this chapter: 10 CFR 72.2(a)(1), 72.11, 72.24(b), 72.24(c)(3), 72.24(j), 72.28(a),
l 72.230(b), and 72.236(a). It should be noted that other regulatory
- requirements may be applicable to this section.
1-1 Update the SAR to reflect the revision of the TN-32 Topical Safety Analysis Report (TSAR) approved by the Nuclear Regulatory Commission.
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Chapter 2 Site Characteristics i The following regulatory requirements are applicable to the RAls in this chapter: 10 CFR 72.2(a)(1), 72.11, 72.24, 72.90, 72.92, 72.94, 72.98, 72.102, 72.104, 72.106, 72.120, and 72.122. It should be noted that other regulatory i l requirements may be applicable to this section. i 2-1 Revise the safety analysis report (SAR) sections and associated I i
analyses pertaining to the independent spent fuel storage installation (ISFSI) design earthquake to clearly comply with the l requirements of 10 CFR 72.102(a)(1), (a)(2), (f)(1), and (f)(2). 1 SAR Section 2.5.2.3 states that the North Anna Power Station Units 1 I and 2 Preliminary Safety Analysis Report and design were completed prior to the promulgation of Appendix A to 10 CFR Part 100, and the term " design-basis earthquake" as used in the ISFSI SAR has the meaning it had prior to the promulgation of these regulations. The '
SAR also references American National Standards Institute /American Nuclear Society (ANSI /ANS) 2.19 and states that "The North Anna Power Station operating-basis earthquake in Section 2.5.2.6 of the UFSAR exceeds the 500-year earthquake and was used as the Design i Earthquake" (page 4.2-3). NRC has not endorsed ANSI /ANS 2.19 as acceptable for meeting the requirements of 10 CFR 72.102. In any case, the design earthquake must comply with 10 CFR Part 72 requirements.
l 2-2 Provide calculations and documentation to demonstrate compliance with 10 CFR 72.102(c) and support the statement in the SAR that ". . .
! liquefaction would not occur under the Design Basis Earthquake of 0.18g."
l While the ISFSI concrete storage pads may not be classified as a structure system or component important to safety, the SAR must demonstrate that the pad will continue to support the casks without causing a tip-over as a result of the ISFSI design earthquake. The calculations should provide the maximum pad settlement (s) and identify the location (s). If reinforcing bars are stressed beyond l yield, identify the locations and evaluate the effect on the casks.
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Chapter 3.0 Principal SSSC Design Criteria l The following regulatory requirements are applicable to the RAls in this l chapter: 10 CFR 72.2(a)(1), 72.11, 72.24(c), 72.24(d), 72.24(e), 72.24(f),
72.24(g), 72.24(m), 72.24(1)(2), 72.30(a), 72.44(d), 72.102, 72.104, 72.106, 72.120(a), 72.122, 72.124, 72.126, 72.128, and 72.130. It should be noted that other regulatory requirements may be applicable to this section.
3-1 Revise SAR Table 3.1-1 to provide the manufacturer and reactor type l for the spent fuel assemblies.
l The information was noted elsewhere in the SAR but should be provided here for completeness. ,
3-2 Revise SAR Section 3.2.3 to comply with the requirements of 10 CFR 72.102 (see also RAI 2-1).
The design earthquake defined in this section is not in compliance with the requirements of 10 CFR 72.102 nor is it consistent with the 0.18g design basis earthquaks stated in SAR Sections 2.5.2.3, 2.5.2.4, and 2.5.4.
3-3 Clarify your statement in SAR Section 3.3.5 that no occupational dose l 1s expected from decommissioning.
, The dose rate on the bottom of the Transnuclear Inc., Dry Storage Cask (TN-32) is significant (133 gamma /368 neutron), and potential activation of the concrete should be addressed.
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Chapter 4.0 Storage System The following regulatory requirements are applicable to the RAls in this chapter: 10 CFR 72.11, 72.24(c)(3), 72.24(d), 72.26, 72.44(c), 72.102(f),
72.106,72.120,72.122(h)(1),72.122(1),72.124,72.128(a)(4),72.182(b),and 72.182(c). It should be noted that other regulatory requirements may be applicable to this section.
4-1 Clarify the design compressive strength for the concrete ISFSI pad.
SAR Section 4.2.1 states that the minimum compressive strength shall be 3000 psi.
4-2 Clarify the "E" load identified for the structural design of the concrete storage pad with respect to the design earthquake used for the ISFSI to assure compliance with 10 CFR 71.102 (see also RAI ltem 2-1).
4-3 Revise the analyses in SAR Sections 4.2.1.4 and 4.2.1.5 to demonstrate that the casks will not slide or tip-over, as a result of the ISFSI design earthquake, based on the method of ANSI /ANS 57.9, Section 6.17.4.1 (see also RAI Item 2-1). Justify that the North
, Anna site conditions are bounded by the TN-32 Topical Safety Analysis j Report (TSAR) Section 2.2.3 analysis.
. The analyses provided show that the casks will tip and slide under
. North Anna Power Station's operating basis earthquake and design i earthquake. The calculated accelerations exceed those evaluated in i
- the TN-32 TSAR that are needed to cause tip-over. NRC endorses the l ANSI /ANS 57.9 method which defines a factor of safety of 1.1 against l
, sliding and overturning. I 4-4 Describe, in more detail, and provide drawings for the impact limiter
- and lift beam, that are identified as equipment important to safety. I 4-5 Describe the location of the flashing light described in SAR Section
- ' 4.4.5.3 that will energize as a result of the sealed surface storage casks' (SSSCs) pressure monitoring system alarm.
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e Chapter 5.0 Storage System Operations The following regulatory requirements are applicable to the RAls in this chapter: 10 CFR Parts 20 and 50 and Sections 72.11,72.24(e),72.24(f),
72.24(1)(2), 72.40(a)(5), 72.104, 72.106, 72.122, 72.128(a)(5), and 72.150.
It should be noted that other regulatory requirements may be applicable to this section.
5-1 Add a statement that lifting within the spent fuel and decontamination buildings is governed by the regulatory requirements of 10 CFR Part 50.
l 5-2 Describe the steps that will be taken to monitor and control cask internal pressure and potential fuel damage during cask reflood for unloading operations.
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Chapter 6.0 Waste Management Wo questions at this time.
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Chapter 7.0 Radiation Protection The following regulatory requirements are applicable to the RAls in this chapter: 10 CFR 20.1101, 20.1201, 20.1207, 20.1208, and Subpart F and 10 CFR 72.11, 72.24(e), 72.102(b), 72.104, 72.106, and 72.126(a). It should be noted that other regulatory requirements may be applicable to this section.
7-1 Clarify and revise, as necessary, SAR Section 7.3 to consider higher neutron surface dose rates for the TN-32 based on Chapter 5 of NRC's Safety Evaluation Report (SER) for the TN-32.
Chapter 5 of the SER notes that the neutron source term could double for spent fuel enriched to less than 3.85%, thereby, increasing the neutron dose for the cask. Increases in neutron doses were also possible for burnups greater than 35,000 mwd /MTU.
. 7-2 Explain how the time estimates for the various tasks were determined for estimating the occupational exposures to ISFSI personnel in SAR Tables 7.4-1 through 7.4-6.
7-3 Define what the letters A through H indicate on Figure 7.3-1.
7-4 Provide the calculations that demonstrate compliance with 10 CFR 72.104(4).
In addition to complying with the requirements in 10 CFR Part 20, the dose limit requirements in 10 CFR 72.104(a) for normal and anticipated occurrences must also be met. j i
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Chapter 8.0 Accident Analysis The following regulatory requirements are applicable to the RAls in this chapter: 10 CFR 72.2(a)(1), 72.11, 72.24(b), 72.24(d), 72.24(m), 72.104(a), '
72.106(b),72.122(d),72.122(g),72.122(h)(1),72.122(1),72.122(1),72.124, 72.126(a), 72.128(a)(4), 72.182(b), and 72.182(c). It should be noted that '
other regulatory requirements may be applicable to this section.
8-1 Reference the SAR section that describes the procedures for verifying proper loading of the spent fuel assemblies in SAR Section 8.2.6.2.
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Chapter 9.0 Conduct of Operations The following regulatory requirements are applicable to the RAIs in this
!. chapter: 10 CFR 72.24(h), 72.28, 72.32, 72.40(a)(9), 72.190, 72.192, and
! 72.194 and Subpart I, " Training and Certification of Personnel." It should be
, noted that other regulatory requirements may be applicable to this section.
i 9-1 Verify that the results of the pre-operational testing will be evaluated for lessons learned and potential changes to equipment and j procedures.
i 9-2 Clearly define the acceptance criteria, margins, and acceptance j criteria for the pre-operational tests and SSSC seal testing.
i SAR Section 9.2.3 refers to other sections for this information, but i the information is not clearly stated in those referenced sections.
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- 9-3 Describe the process by which procedures will be generated for the 10 CFR Part 72 licensed activities.
! 9-4 Describe the process / program for the preparation and review of safety
, and environmental evaluations allowed under 10 CFR 72.48, " Changes, i tests, and experiments" (e.g., procedure, preparer / reviewer training j and qualifications, unreviewed safety question guidance and j determination,etc.).
I 9-5 Provide a description of North Anna's systematic approach to ISFSI
- training.
4 A systematic approach to training should include, but not be limited
- to, identification of tasks to be trained in, identification of l skills and knowledge required to perform the identified tasks, design
! of the training program and performance measures, development of i lesson plans, implementation of the training, and mechanisms for evaluating the program and personnel being trained.
9-6 Provide a copy of the revised North Anna Emergency Plan, noting the !
- sections that were revised due to the addition of the ISFSI. l i
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l Chapter 10.0 Operating Controls and Limits No questions at this time. i l
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E Claptut 11.0 Quality Assurance int following regulatory requirements are applicable to the RAls in this section: 10 CFR Part 72, Subpart G, " Quality Assurance," specifically, Sections 72.140 through 176. It should be noted that other regulatory requirements may be applicable to this section.
10-1 Clarify the most recent revision and list of amendments for the Quality Assurance Program document VEP-1-5A.
The revision reviewed by staff, as provided by the licensee, was VEP-1-Sa, Amendment 5. The cover sheet shows that the document was updated in February 1994, but the " List of Amendments" on page 17.2-iv shows the last update of the document as June 16, 1992.
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Technical Specifications No questions at this time.
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Financial Assurance and Decommissioning The following regulatory requirements are applicable to the RAIs in this section: 10 CFR 72.11, 72.30, 72.54, 72.130, 72.236(i), and 10 CFR 61.55. It should be noted that other regulatory requirements may be applicable to this section.
4 FAD-1 Provide the annual schedule of construction and operation expenses that Virginia Electric and Power Company (Virginia Power) and Old Dominion expect to incur for the ISFSI over its scheduled operating i
- life. I FAD-2 Explain whether or not Virginia Power and Old Dominion intend to seek i recovery of all or part of the construction, operation, and decommissioning expenses of the ISFSI through ratepayers. If so, j state when such rate recovery will be sought.
FAD-3 Verify that the ISFSI decomissioning cost will be fully assured by trust fund or other assurance mechanism provided in 10 CFR J
50.75(e)(1) or (3) (as referenced in 10 CFR 72.30(c)(5)).
. Although Section 10.2 of the license application briefly discusses decomissioning trust funds, it is not clear that the ISFSI decomissioning costs have been provided for separately, over and above other decomissioning costs associated with the North Anna facility. At a minimum, the North Anna decommissioning trust should either have a separate sub-account for ISFSI decomissioning costs or some clear method to identify separately the various components of decomissioning costs, including the NRC-required radiological decommissioning costs, non-radiological costs not required by the NRC, and ISFSI costs. 1 l
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