Letter Sequence RAI |
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MONTHYEARML20195C9421988-06-0909 June 1988 Forwards Request for Addl Info Re Pump & Valve Inservice Testing Program.Response Requested within 120 Days of Ltr Date Project stage: RAI 1988-06-09
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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) 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 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 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 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 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 ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 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 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 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:NRC TO UTILITY
MONTHYEARML20062D7631990-11-0606 November 1990 Forwards FEMA Re Plant Emergency Exercises on 900808.Two Deficiences in Offsite Performance Noted ML20058H0211990-10-29029 October 1990 Forwards Insp Repts 50-338/90-26 & 50-339/90-26 on 900908-24 & 1009-12.No Violations or Deviations Noted ML20058D7431990-10-26026 October 1990 Grants 901004 Request for Waiver from Tech Spec 6.9.1.7 Re Submittal of Core Surveillance Rept IR 05000338/19900181990-10-25025 October 1990 Ack Receipt of Re Violations Noted in Insp Repts 50-338/90-18 & 50-339/90-18 ML20058D7291990-10-25025 October 1990 Ack Receipt of Re Violations Noted in Insp Repts 50-338/90-18 & 50-339/90-18 ML20058B4151990-10-24024 October 1990 Ack Receipt of 880808 & 900613 Responses to NRC Bulletin 88-004 Re Potential safety-related Pump Loss ML20058E9271990-10-23023 October 1990 Forwards SALP Repts 50-338/90-22 & 50-339/90-22 for June 1989 - Aug 1990 ML20058E5771990-10-23023 October 1990 Forwards Requalification Exam Rept 50-338/OL-90-01 for Units 1 & 2 Administered During Wks of 900820 & 27 ML20062C4311990-10-18018 October 1990 Forwards SE & TER Concluding That Util Actions Do Not Conform to Requirements of Station Blackout Rule.Plant Emergency Diesel Generators Do Not Have Excess Capacity Available to Qualify Generators as Aac Source ML20062B2531990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20062B6471990-10-11011 October 1990 Advises That Rev 15 to Guard Training & Qualification Plan Consistent w/10CFR50.54(p) & Acceptable ML20058B4241990-10-10010 October 1990 Confirms Region II Insp of fitness-for-duty Program on 901023-25.Tentative Itinerary Encl ML20058B3871990-10-10010 October 1990 Forwards Details Re Allegation Rept Rii 90-A-0152,per 901001 Telcon.Encl Withheld (Ref 10CFR2.790) ML20058A8481990-10-0909 October 1990 Forwards Insp Repts 50-338/90-23 & 50-339/90-23 on 900819- 0915.Violation Noted But Not Cited ML20059N1011990-09-19019 September 1990 Forwards Insp Repts 50-338/90-19 & 50-339/90-19 on 900820-24.Violations Noted But Not Cited ML20059K7941990-09-11011 September 1990 Forwards Insp Repts 50-338/90-18 & 50-339/90-18 on 900708- 0818 & Notice of Violation ML20059K7301990-09-0707 September 1990 Ack Receipt of in Response to Violations Noted in Insp Repts 50-338/90-11 & 50-399/90-11.Expresses Appreciation Re Issues Concerning EOPs & Abnormal Procedures ML20059K6811990-09-0606 September 1990 Forwards Insp Repts 50-338/90-20 & 50-339/90-20 on 900806- 10.No Violations or Deviations Noted ML20058P8841990-08-0606 August 1990 Forwards Insp Repts 50-338/90-16 & 50-339/90-16 on 900709-13.No Violations or Deviations Noted ML20056A0491990-07-30030 July 1990 Forwards Insp Repts 50-338/90-17 & 50-339/90-17 on 900709-13.No Violations or Deviations Noted ML20055H3831990-07-25025 July 1990 Confirms 900720 Verbally Granted Temporary Waiver of Compliance from Tech Spec 3.3.1.1,Table 3.3-2 Re Response Time Testing of Pressurizer High Level Reactor Trip Function ML20056A5331990-07-20020 July 1990 Forwards Summary of 900718 Mgt Meeting at Plant Re self-assessment of Facility ML20055H4401990-07-0505 July 1990 Ack Receipt of Providing Scenario for Plume & Injection Pathway Exercise Scheduled on 900807 & 08 ML20055H4491990-07-0303 July 1990 Forwards Summary of 900625 Meeting W/Util in Region II Ofc Re Emergency Preparedness Upgrade Program.List of Attendees Also Encl ML20055H6151990-06-28028 June 1990 Forwards Insp Repts 50-338/90-13 & 50-339/90-13 on 900514-18 & 29.Noncited Violations Noted ML20055H6271990-06-26026 June 1990 Forwards Insp Repts 50-338/90-14 & 50-339/90-14 on 900604-08.No Violations or Deviations Noted ML20059M8771990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248B4731989-09-21021 September 1989 Forwards Insp Repts 50-338/89-26 & 50-339/89-26 on 890716- 0822 & Notice of Violation ML20247P4281989-09-18018 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/89-12 & 50-339/89-12 ML20247C2011989-09-0707 September 1989 Forwards Safety Evaluation Accepting Util 890512 Response to IE Bulletin 80-11, Masonry Wall Design IR 05000338/19890181989-09-0101 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/89-18 & 50-339/89-18.Implementation of Corrective Actions Will Be Examined During Future Insps ML20246M7141989-08-23023 August 1989 Forwards Insp Repts 50-338/89-22 & 50-339/89-22 on 890601-0714.No Violations or Deviations Noted ML20246M5381989-08-22022 August 1989 Forwards Insp Repts 50-338/89-27 & 50-339/89-27 on 890731-0804.No Violations or Deviations Noted ML20246M4781989-08-21021 August 1989 Confirms 890627 Telcon Between Rf Saunders & PE Fredrickson Re 890824 Mgt Meeting.Meeting Requested to Review Results of SALP Program for Facility IR 05000338/19890141989-08-21021 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/89-14 & 50-339/89-14 ML20246H2371989-08-21021 August 1989 Forwards Safety Sys Outage Mods & Maint Team Insp Repts 50-338/89-200 & 50-339/89-201 During Wks of 890508 & 22.No Violations Noted.Identified Weaknesses Re Performance of Vendor Surveillance Activities ML20246L2331989-08-15015 August 1989 Forwards SALP Repts 50-338/89-16 & 50-339/89-16 for May 1988 - May 1989.Overall Performance Satisfactory During Assessment Period ML20245L3381989-08-0707 August 1989 Forwards Insp Repts 50-338/89-24 & 50-339/89-24 on 890710-14.No Violations or Deviations Noted IR 05000338/19890111989-08-0303 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/89-11 & 50-339/89-11 ML20248D9791989-08-0303 August 1989 Forwards Request for Addl Info Re Pipe Stresses Due to Differential Settlement Between Svc Bldg & Main Steam Valve House.Responses Should Be Provided in Forthcoming License Amend Request ML20248D9011989-08-0303 August 1989 Advises That NRC Approval Neither Granted Nor Required in Case of Certification Since Util Assumes Responsibility for Regulatory Compliance w/10CFR55.45(b)(2) ML20248D2571989-07-31031 July 1989 Forwards Corrected Pages 1 & 2 to Insp Repts 50-338/89-12 & 50-339/89-12 Due to Pages Not Being Photocopied Correctly ML20246A3941989-07-28028 July 1989 Forwards Insp Repts 50-338/89-21 & 50-339/89-21 on 890613-14.No Violations or Deviations Noted IR 05000338/19890151989-07-25025 July 1989 Ack Receipt of Re Violations Noted in Insp Repts 50-338/89-15 & 50-339/89-15 ML20247D5211989-07-17017 July 1989 Forwards Insp Repts 50-338/89-12 & 50-339/89-12 on 890412-14 & 20-26 & Notice of Violation ML20247D5161989-07-12012 July 1989 Forwards Summary of Mgt Meeting Held on 890619 at Region II Ofc Re self-assessment of Facility.List of Attendees & Handout Encl ML20246K3031989-07-0707 July 1989 Forwards Insp Repts 50-338/89-19 & 50-339/89-19 on 890605-09.No Violations or Deviations Noted ML20246G1361989-07-0505 July 1989 Discusses Insp Repts 50-338/89-08,50-339/89-08,50-338/89-14 & 50-339/89-14 & Forwards Notice of Violation.Violations Noted:Inadequate Svc Water Supply to safety-related Spray Sys During Accident Conditions.W/O Notice of Violation ML20246D4191989-06-30030 June 1989 Advises That 890329 Rev 22 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20246E7221989-06-30030 June 1989 Forwards Insp Repts 50-338/89-20 & 50-339/89-20 on 890605-09 & 12-13.No Violations or Deviations Noted 1990-09-07
[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 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 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 ML20248K9121998-06-0808 June 1998 Forwards Preliminary SER for North Anna Nuclear Power Station Isfsi,Per Util 950509 Submittal of Application for ISFSI ML20249A4741998-06-0505 June 1998 Advises of Planned Insp Effort Resulting from Plant Ppr. Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl 1999-09-08
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June 9, 1988 i
Docket flo. 50-338 DISTRIBUTION
@ Docket;fA]ep OGC-WF IIRC PDR E.-Jordan fir. D. S. Cruden Local PDR J. Partlow Vice President - Nuclear PD22 Reading ACRS(10)
Virginia Electric and Power Company S. Varga Gray File P.O. Box 26666-G. Lainas Richmond, Virginia 23261 H. Berkow -
-D.
Itiller
Dear Mr. Cruden:
L. Engle
SUBJECT:
INTERIM EVALUATION FOR PUMP AllD VALVE lilSERVICE TESTING PROGRAM, NORTil AllNA NUCLEAR POWER STATION, UNIT 1 (NA-1) (TAC NO. 52414)
By letter dated March 3, 1988, Virginia Electric and Power Company submitted a request for an exemption from 10 CFR 50.55a(g)(4)(ii) which would alica a common IST start date for both NA-1&2. That common start date would be achieved by erending the termination date of the NA-1 IST program to coincide with the termi;;ation of the NA-2 IST program. The ilA-1 IST program would be extended to terminate on December 14,(g)90,(rather than on June 6,1988.
19 The exemption for NA-1 from 10 CFR 50.55a (4) ii) was granted on April 26, 1988.
IlA-1 is currcntly in the first 120-month interval and has not yet received an
-IIRC IST SER. Since the interval, as discussed above, is only being extended by 30 months, the staff has performed a review which concentrated on the acceptability of relief requests and other problems in order to identify any major deficiencies in the NA-1 IST program. A list of questions and comments resulting from the staff's review is provided in the enclosure to this letter.
We request that your response to the staf f's comments and requests for infor-mation be provided to us within 120 days of the date of this letter.
The reporting and/or r ;ordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, 1
Leon B. Engle, Project Manager Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enciesure:
See next page D:kh L 'P @ 2 Pt llBer low DI Plbr LET 6 g /88 6/C /86 6f/88 8806220333 880609 PDR ADOCK 05000338 PDR'
)
Mr. D. S. Cruden North Anna Power Station Virginia Electric & Power Company Units 1 and 2 cc:
Mr. William C. Porter, Jr.
James B. Kenley, M.D., Ccmmissioner County Administrator Department of Health Louisa County 109 Governor Street P.O. Box 160 Richmond, Virginia 23219 Louisa, Virginia 23093 Regional Administrator, Region II Michael W. Maupin, Esq.
U.S. Nuclear Regulatory Commission Hunton and Williams 101 Marietta Street N.W., Suite 2900 P. O. Box 1535 Atlanta, Georgia 30323 Richmond, Virginia 23212 Mr. W. T. Lough Virginia Corporation Commission Mr. G. E. Kane Division of Energy Regulation P. O. Box 402 P. O. Box 1197 Mineral, Virginia 23117 Richmond, Virginia 23209 Old Dominion Electric Cooperative Ellyn R. Weiss, Esq.
c/o Executive Vice President Harmon, Weiss and Jordan Innsbrook Corporate Center 2001 S Street NW 4222 Cox Road, Suite 102 Washington, DC 20009 Glen Allen, Virginia 23060 Mr. W. L. Stewart Senior Vice President - Power Virginia Electric and Power Co.
Post Office Box 26666 Richmond, Virginia 23261 Mr. Patrick A. O' Hare Office of the Attorney General Supreme Court Building 101 North 8th Street i
Richmond, Virginia 23219 Resident Inspector / North Anna c/o U.S. NRC Senior Resident Inspector Route 2, Box 78 Mineral, Virginia 23117 k
I, b
ENCLOSURE REQUEST FOR INFORf1ATION PUMP AND VALVE INSERVICE TESTING PROGRAM NORTH ANNA POWER STATION, UNIT N0. 1 DOCKET N0. 50-338 By letter dcted March 3,1988, Virginia Electric and Power Company submitted a request for an exemption from 10 CFR 50.55a(g)(4)(ii) which would allow a common start date for North Anna Units 1 and 2 Inservice Testing (IST) programs.
The Unit 1 IST program would be extended to terminate on December 14, 1990, rather than the current date of June 6,1988.
In order to focilitate extending the termination date for the Unit 1 IST program, a preliminary review of the October 5.1983 program was perforrred utilizing the acceptance criteria and guidance contained in the following documents: ASME Code Section XI, Code interpretations when applicable, the Code of Federal Regu-lotions 10 CFR Part 50, the Standard Review Plan, Section 3.9.6, and the Draf t Regulatory Guide and Value/ Impact Statement titled, "Identification of Valves for Inclusion in Inservice Testing Programs."
This partial review focused on the relief requests submitted.
Each relief re-quest was evaluated to determine 1) if testing the affected ccmponents in accordance with the Code requirements would be impractical, ?) whether the licensee's proposed testing would provide a reasonable alternative to the Code requirements, and 3) whether it would place an unreasonable burden on the licensee if the Code requirements were inposed.
l The following are program deficiencies found in the review which must be changed to ensure program conformance with the above standards and the NRC staff positions.
1.
VALVE PROGRAM General 1.
The Code permits valves to be exercised during cold shutdowns where it is not practical to exercise them during plant operation.
10 CFR Part 50 allows valves that cannot be exercised quarterly or at cold shutdown to be exercised during refueling intervals if specific relief is granted.
These valves are specifically identified by the licensee and are full-stroke exercised during cold shutdowns or, when relief is granted, at refueling cutages.
The NRC staff requires that the licensee provide a technical justification for each valve that cannot be exercised quarterly t
I 2
during power operations that clearly explains the technical difficulties or hazards encountered during that testing.
Relief requests and cold shutdown justification bases should indicate the negative consequences that make testing at the Code-reouired frequency impractical, such as endangering personnel, equipment damage, or resulting in a plant shutdown.
T. sting at an increased frequency because.of logistics problems or for the sake of convenience to the licensee is not considered an adequate justification.
Based on the technical trerit of the justification, the NRC 5taff will then evaluate the impracticability of exercising those valves quarterly and either allow testing during cold shutdowns cr grant relief to perform the testing at refueling outages.
The relief justifi-cations in the North Anna IST program need to include more detailed tech-nical justification.
2.
Valves which are full-stroked at a cold shutdown or refuelir,g frequency can often be partial-stroke exercised quarterly during power operation.
The licensee has identified the valves which are full-stroke exercised on a cold shutdown or refueling frequency but has rot identified any partial-stroke exercising done on a quarterly basis.
3.
When a measured flowrate through a check valve is used as the positive means to verify a full-stroke exercise of the valve disk, the NRC staff's position is that the measured flowrate through the valve must be at least equal to the maximum flow rate identified in any of the plant's safety analyses.
This criteria is required for the test to be considered an adequate demonstration of the full-stroke requirement. Any flow rate less than this will be considered partial-stroke exercising unless it can be shown (by some means such 6s measurement of the differential pressure ecross the valve), that the check valve's disk position at the lower flow rate would permit maximum required flow through the valve.
In many cases, especially in the safety injection systems, the licensee does not meet this requirement for full-stroke exercising of check valves.
Some specific cases will be addressed in this evaluation, but the licensee should evaluate the testing of all the check valves in the IST program to ensure that each check valve is truly meeting the requirements of a full-stroke.
4.
Where check valves cannot be full-stroked exercised with flow or an exter-nal exerciser at any frequency, a relief request must be submitted re-questing to disassemble the valve to ensure freedom of disk movement.
The sample disassembly and inspection program involves grouping similar valves and testing one valve in each group during each refueling outage. The sampling technique requires that each valve in the group be the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions.
Additionally, at each disassembly the licensee must verify that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound (no loose or cor-roded parts). Also, if the disassembly is to verify the full-stroke capa-bility of the valve, the disk should be manually exercised.
A dif#erent valve of each group is required to be disassembled, inspected, and '.anually full-struke exercise at each refueling outage, until the entire group has been tested.
If the disassembled valve's full-stroke
f l
3 capability is in question, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
5.
The NRC staff position is that the some of the emergency diesel generator auxiliary systems perforrn a safety-related function even though thay are rot ASME Code Class 1, 2 or 3.
In start system, from the check valve (particular, the diesel generator air s) between the compressor (s) and the receiver (s) to the engine, including the air start solenoids, has a safety-related function.
From the review of the North Anna IST program, it appears that the volves in the diesel generator air start system have not been included in the IST program.
The appropriate valves in the emergency diesel generator oir start system rnust be included in the IST program and tested in accordance with the Code requirements.
6.
In many relief requests, the proposed alternate testing reference a i
testing frequency not te exceed once per 9 months. ASME identified this testing frequency as a typographical error in the 1974 edition through summer 1975 addenda under testing of check valves.
Check valve testing is required by Section XI to be done at a 3-month interval. All inappro-priate references to the 9-month interval must be removed from the IST program.
7.
For valves that require maintenance which can affect valve ope
- ability, the licensee must perform post-maintenance testing to ensure valve opera-bility prior to return to service.
Based on actual plant data which has j
shown valve performance failure after maintenance, the staff will not grant relief from the exercising requirements of IWV-3200 as requested in North Anna letter dated October 28, 1987, Serial No.87-634 Recirculation Spray 1.
In relief request RS-Note-02, the licensee has not demonstrated the imprac-ticality of performing the valve testing at cold shutdowns.
Inconvenience to the licensee is not suitable justification.
Safety Injection 1.
Industry experience has shown that low Temperature ov % ressure (LT0P) protection systems may be challenged or sufficient expansion volume in the RCS may not be available when performing a full-stroke exercise test of safety injection system check valves using ficw.
These problems arise from the high flow rates necessary to accomplish a full-stroke exercise and be-cause the flow is injected into the RCS.
Relief requests SI-Hote-06
-07, and -12 indicate a full-stroke exercise of safety injection check valves at a cold shutdown frequency. These relief requests should be reevaluated by the licensee to determine if 1) a full stroke for these check valves is being achieved when tested at cold shutdown (see General Corment #3), 2) the LT0P and expansion volume considerations stated above apply to the testing of these check valves, and 3) the exercising of these check valves should be performed at refueling intervals vice cold shutdowns, t
4 l
2.
Industry experience has shown that a full-stroke exercise of the check l
valves in the discharge lines of the accumulators usually does not occur i
even at refueling when flow from the accumulators is used bec;use of the I
very high flow rate needed and the lack of suf ficient expansion vitume i
in the RCS.
The licensee should reevaluate the testing of the valves in relief request SI-flote-10 and indicate how conformance with the tode is l
being met.
3.
Industry experience has shown that LTOP protection systems may be chal-lenged and/or suf ficient expansion volume in the RCS may not be. available when performing a full-stroke exercise test of safety injection system check valves using flow. These problems arise from the high flow rates necessary to accomplish a full-stroke exercise and because the flow is injected into the RCS, Relief request SI-ilote-11 indicated a full-stroke exercise of safety injection check va'ves at a cold shutdown frequency.
This relief request should be reevalu~ 'd by the licensee for check valves 1-SI-79,-90, -185, -201, -206, and -20/ to determine if 1) a full stroke fur these check valves is being achieved when tested at cold shutdown (see General Comment #3), 2) the LTOP and expansion volume considerations stated above apply to the testing of these check valves, and 3) the exer-cising of these check valves should be performed at refueling intervals vice cold shutdowns.
P& ids indicate that the individual flow measurement is not possible f or check valves 1-SI-95, -99, -103, -209, -211, and -213.
Unless the safety flow rate ti rough these valves can be measured for each valve individually, full-stroke exercising cannot be verified using flow.
The licensee should reevaluate the testing of these chcck valves and re-write the relief request as necessary (See General Coments #3 and #4).
4.
P&lDs indicate there is no instrumentation installed which measures ficw through each individual check valve in relief request SI-Note-09. Unless the safety flow rate through these valves can be measured for each valve individually, full-stroke exercising cannot be verified using using flow.
The licensee should reevaluate the testing of these check valves and re-write the relief as necessary (See General Coments #3 and (4).
Quench Spray 1
1.
IW-3522 requires a pusitive means be used to verify that a check valve disk moves to its full open position.
In the case where a mechanical exerciser is used, the torque, cr force, required to move the valve oisk must be measured and be within the specifications of the Code.
Relief re-quest QS-Note-01 states that the check valves in the relief request will be exercised manually but does not mention torque measurement.
If the torque cannot be measured then the requirements of the Code are not being met and the valves in this relief request will either have to be exercised by flow or by sample disassembly. The licensee should reevaluate this relief request and rewrite it to indicate how conformance with the Code is being met.
2.
PLMP PROGRAtt 1.
The staff recognizes the advantages of measuring pump vibration in units of velucity rather than displacement. liowever, IRD Mechanalysis is unacceptable as a standard of reference for the purrp vibration limits.
l l
e 5
A reasonable alternative to Section 1.1, when velocity vibration monitor-ing is desired, is OM-6.
Relief to measure vibution velocity can be granted if the licensee adopts all vibration monitoring requirements in-ciuding the methods of measuring the vibration +.nat are at least as encompassing and as conservative as those found in OM-6.
2.
Lack of installed instrumentation is not considered sufficient technical justification for granting relief from the requirements of Section XI.
The licensee has several options that the staff will consider.
The staff will consider individual relief requests that are seeking tem-porary relief until permanent instrumentation is installed as long as they clearly state when the instrumentation will be in service.
Another option to the licensee is to request relief, en an individual basis, to perform as complete a quarterly test as possible measuring all of the available instrumented parameters and obligate to perform higher flow tests in which all parameters required by the Code are measured at the earliest possiblF Trequency (cold shutdown or refueling). An example of this is in relief request #2, where no installed flow instrumentation exists. On a quarterly frequency, a test can be performed measuring everything but the flow. Then at refueling outages, the pumps can be run actually injecting into the RCS and all test parameters required by the Code, including flow using a downstream flow instrument in the injection line, can be measured.
A third option available is to use other positive means to measure a parameter not instrumented. An example would be to calculate pump inlet pressure from a tank level or to determine a pump flow rate by measuring a change in a tank level providing that these substituted rethods meet the accuracy requirements of Section XI.
Relief requests #2, #3, and #4 must be rewritten to conform with one of these requirements.
3.
In relief request #3, part 3, the difficulty involved in removing insula-tion from around a pump is not considered acequate technical justification to allow granting relief from vibration measurement.
4.
Relief request #4, part 2 is covered in number 2 above.
In this part, the licensee must assure the staff that measuring a change in tank level meets the accuracy requirements of the Code, in relief request #4, part 3, the licensee must provide more detailed technical justification for not measuring vibration, lube oil level and pressure and bearing temperature of these pumps quarterly. The staff does not consider elimination of a test as a reascnable alternative to the Code requirements.
5.
The staff considers the RHR system to have a safety function. Relief re-quest #5 must be rewritten to include a technical justificatica for testing RHR at cold shutdown.
6.
Section XI requires pump differential pressure to ',e measured and the staff considers differential pressure an important parameter in detecting hydraulic degradation of a pump.
In cases where water level is used to determine the inlet pressure to a pu:q, the inlet pressure must be calcu-lated and a differential pressure established for the pump. Relief re-quests #9 and #10 nost be rewritten to conform to this requirement.
L-
s 6
7.
The staff recognizes that cccasionally a system exists that does not 6110w the licensee to establish repeatable reference conditions. An example of this would be a chill water system that runs constantly under various loou conditions.
In these cases, relief can be granted allowing o
a curve of reference values to be used.
However, it is recognized that this' alternative testing method is not equivalent to the Code requirements.
Trending the data using this testing method does not provide results that are as reliable or conclusive.
In the llorth Anna letter dated October 28, 1987, Serial No.87-634, the licensee has requested relief to develop curves for all pumps in the IST program regardless of system character-istics. The staff Will not grant blanket relief requests of this nature.
The licensee must request relief to develop a pump curve on a system-specific basis providing an individual technical justification for each.
The staff will tr.an review each relief on its own merit and consider granting relief on a system-by-system basis.
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