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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: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 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 ML20058E5771990-10-23023 October 1990 Forwards Requalification Exam Rept 50-338/OL-90-01 for Units 1 & 2 Administered During Wks of 900820 & 27 ML20058E9271990-10-23023 October 1990 Forwards SALP Repts 50-338/90-22 & 50-339/90-22 for June 1989 - Aug 1990 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 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 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 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 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 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 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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September 21, 1988
/ Virginia Electric and Power Company ATTN: Mr. W. R. Cartwright Vice President Nuclear Operations P. O. Box 26666 Richmond, VA 23261 Gentlemen:
SUBJECT: NRC INSPECTION REPORT NOS. 50-338/87-39 AND 50-339/87-39 l
Thank you for your responses of February 26, March IS, and August 22, 1988, to l our Notices of Violation and Deviation issued on January 27, 1988, concerning 1 activities conducted at your North Anna facility. We have evaluated your responses and found that they meet the requirements of 10 CFR 2.20 In your response, you admitted the violation but denied a portion of the deviation. After careful consideration of the bases for your denial of one part of the deviation, the current NRC position regarding the documentation requirements for Emergency Operating Procedures, and comitments made in your letter of August 22, 1988, we have decided to withdraw the portion of the deviation in dispute. We will examine the implementation of your actions to i correct the violation and deviation during future inspection The responses directed by this letter and its enclosure are not subject to the clearance procedare! of the Office of Management and Budget as required by the paperwork reduction act of 1980 Pub L. No. 96-51 We appreciate your cooperation in this matte Sincerel Original signed by Al Gibson Albert F. Gibson, Director Division of Reactor Safety Enclosure: Evaluation and Conclusion cc w/ encl:
vG. Kane, Station Manager vN. E. Hardwick, Manager - Nuclear Programs and Licensing l
l hec w/ encl:
I vliRC Resident Inspector ORS Technical Assistant Document Control Desk State of Virginia k
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ENCLOSURE
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EVALUATIONS AND CONCLUSIONS ;
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1 On January 27, 1988, a Notice of Violation and a Notice of Deviation were issued for findings identified during an NRC inspection. VEPC0 responded to these Notices on February 26, 1988. The licensee admitted the Violation as [
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stated, but denied an item contained within the Notice of Deviation. The NRC's evaluation and conclusion for the area of the Deviation which was Jenied by VEPC0 is as follows:
Restatement of Deviation
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On July 1,1983, the licensee submitted a Procedure Generation Package (PGP)
I for Emergency Operating Procedures (EOPs) to the NRC. In that submittal, the -
j licensee committed to implement the Westinghouse Owners Group (WOG) Emergency
- Response Guidelines (ERGS), Rev. 1, as approved by the NRC. In addition, the
- licensees PGP required that justification of any significant deviation from an i ERG step and justification of all E0P setpoints be documented. The licensee us> a Step Deviation Document (SDD) for this documentation. The licentae's
- PGP also required that controls and displays referenced in E0Ps be identified to assist the operator in accurate and quick identificatio The licensee's SDD for procedure ES-0.28, Natural Circulation Cooldown Without
Shroud Cooling Fans, Rev.1, failed to document justification of a significant i departure from the ER Step 20 of procedure ES-0.2B directed the operators a
to perform an isothermal depressurization following an 8-hour soak perio '
This represented a significant departure from the WOG ERGS wherein the l operators are directed to continue cooling down, following the soak period, .
, while maintaining 200*F subcoolin The RCS depressurization method used in l l step 20 of ES-0.2B resulted in significantly less upper head subcooling than I a in the ERG procedure from which it was derived. This step deviation was not j identified or justified in the licensee's SD !
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Also, the licensee's SDD failed to identify the use of different setpoint ;
j The minimum temperature / pressure cooldown curve shown in Attachment 1 i Pressure / Temperature Limits for Cooldown, to ES-0.2B was less conservative l
than the cooldown curve defined by Technical Specifications, Figure 3. <
- Other setpoints contained in ES-0.2B were different from those used in the ERG !
- (including cooldown rate; subcooling margin; and holdpoint pressur l 1 temperature, end time). These setpoint differences were not mentioned in the 1 licensee's 50 j
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Finally, the licensee's E0Ps for natural circulation cooldown ES-0.2A, Natural f Circulation Cooldown With Shroud Cooling fans, Rev. 1; ES-0.2B, Natural ;
Circulation Cooldown Without Shroud Cooling Fans, Rev.1; and ES-0.2, Natural ,
I Circulation Cooldown With Steam Void in Vessel (with RVLIS), Rev. 1 failed to !
I identify controls and displays to be used in maintaining cooldown pressure and I temperature limits in that Attachment 1. Pressure / Temperature Limits for
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Cooldown, did not indicate which temperature instruments are to be used.
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.. l Enclosure 2 Summary of Licensee's Response i
The licensee denied that there was a deviation for failure to document a significant deviation from the WOG ERG by performing an isothermal depressurization. The basis for this statement was derived from a comparison
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made between the generic methodology and the process used in the North Anna
! procedur The WOG ERG Background document defines operating limits for a generic plant design which are designed to maintain subcooling in the reactor vessel upper head during a plant cooldown on natural circulatio ,
The response also explained the methodology used to determine the plant ;
specific setpoint values for North Anna. The licensea concluded that: i The North Anna natural circulation cooldown procedure (ES-0.28)
confo*ms to the corresponding generic guideline with no significant l
deviation in strategy, execution. or intent.
1 The plant specific natural circulation limitations maintain .
approximately the same subcooling margin in the reactor vessel upper head region as the generic guidelines through all phases of the cooldow This includes allowance for process instrumentation !
accuracy as directed by the generic guideline i NRC Evaluation of Licensee Response !
t The NRC discussed the E0P Setpoint Document with the licensee and Volian, the !
consulting firm that performed the evaluation The licensee agrees with the ,
section of the deviation that cites the lack of documentation within the SDD ;
for the isothermal depressurization and intends to cross-reference the l
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setpoint document as justificatio During subsequent telecons the licensee and the NRC agreed that procedure ES-0.2B does not place the plant in an i unanalyzed or unsafe ccnditio However, the licensees response indicated that their policy is to not document l deviations that the licensee considers to be consistent with the strategy and '
l intent of the WOG ERG The NRC is concerned that this policy is in conflict with conrnitments made in the PGP submittal which states that justification of i any significant deviation from an ERG step and justification of all E0P ;
setpoints be documented, i Regarding the adequacy of the licensees E0P setpoint document; the inspectors reviewed this document dated 4/15/87, and found it to contain the following basis: "7) Af ter the wait period, the cooldown and depressurization is i
continued be placed while maintaining).at in operator (sic " leastWnst 200'F subcooling disturbed until theabout the inspectors RHR this system was can that it was cited in the E0P setpoint document that was supposed to justify an l isothermal depressurization that would be in direct conflict with the above I noted basis. This alone cast doubt as to the thoroughness of the effort to I
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analyze what the NRC considers to be a safety significant deviation from the WOG ER l i
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Enclosure 3
i The licensee intends to rely upon a revised setpoint document that more clearly relates the step deviation to the WOG ERG. This E0P setpoint
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document, dated 2/23/88, will be cross referenced in the 500 for this ste i The NRC performed a review of this setpoint document and had the following comment:
"The primary concern during a loss of forced flow through the reactor core !
is upper head voiding, which is of particular interest in a plant design
such as North Anna where there is little mixing of the fluid in the upper head during this transient. The most important parameter to be monitored
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is the subcooling margin in the upper head. The licensees E0p setpoint documents, both 4/15/87 and 2/23/88, do not list this parameter in their i cooldown tables. Instead, it must be calculated by the reviewer for each
- time increment in the cooldown to verify that adequate upper head
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subcooling is maintaine It is not a requirement to list this i pirameter, however, it is expected that since upper head subcooling is of 1 primary concern, it would be the focus of the data table '
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Sibsequent communication between the licensee and the NRC resolved all of the perceived technical concerns regarding the E0P setpoint document of 2/23/8 A final request was made by the NRC of the licensee in the telecon of 7/23/88 (
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to fennally submit in a correspondence the licensees t.urrent policy for ;
documenting E0P deviations from the WOG ER The licensee made the following :
commitment in their letter of 8/22/8 '
"The North Anna policy is to document and justify any procedure deviations from the WG ERGS, including the following:
1 Any additions or deletions of Notes, Steps, or Cautions j 2 Any changes to setpoints
- 3 Any step sequence changes l
4 Any changes due to tactical or design differences.
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Cross references between the SDD which documents any step additions, deletiond, and change in sequence, and the Setpoint Document which j documents the basis for the procedure setpoints will be provided whenever ,
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- a setpoint specified in the WO3 ERGS is changed. This policy does not j apply to those setpoints which are normally plant specific and are only ;
documented in the Setpoint Document." j j The NRC requested clarification of the final sentence (underlined) and l 1 received from the licensee the statement that any of the netpoints that are '
j assigned specific values in the WOG ERG will be subject to the policy. Those '
setpoints thet are footnoted within the WOG ERG to reference setpoint studies !
or plant specific values will have specific calculations or references l 1 contained in setpoint documents that will verify the value, however these will ;
not be cross referenced in the 500. The NRC cautioned the licensee that a f l
clear audit path between the E0Ps and all supporting documentation, .< bile not ;
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a regulatory requirement, is a preventative measure that can preclude the i difficulties that may arise when plant modifications or other associated l i
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Enclosure 4
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changes affect equipment, setpoints, and/or mitigative action Furthermore, Standard Review Plan 13.5.2. Appendix A. Section 3.3.2, Deviations and Additions, subsection 1.e. states an example of a deviation as the following:
"Plant-specific setpoints or action levels that are calculated or determined in the manner other than specified in the generic technical
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guidelines."
The NRC expects the licensee to follow this guidance as clarification to the above noted underlined sentence contained in the commit:.*ent taken from the correspondence from the licensee dated August 22, 198 ,
NRC Conclusions l
The NRC would like to remind the licensee of what has been identified in the past as weak supporting documentation for changes made to the WOG ERG' Specifically, a NRC audit report of the E0P PGP implementation audit for the North Anna power station, Units no. I and no. 2, issued August 1986, had ,
similar finding Specifically, section 3.1.2.1, Deletion / Revision of ERG steps, states: "Many ERG steps were not included in the North Anna E0Ps or were revised to the extent that their content was in questio Sufficient justification for these deletions / revisions was rarely documented."
t-Ease; on subsequent evaluations of the licensees procedures for natural circulation cooldown and their associated documentation, the NRC is l withdrawing the contested example of the deviation. The reasoning for this 1 decision is based primarily on the fact that the procedure did not place the plant in an unsafe or unanalyzed conditio i
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