ML20137E074
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| ML20137E074 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 11/20/1985 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8511270196 | |
| Download: ML20137E074 (2) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999
[Table view]Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217K4391999-10-18018 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 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 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 ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors 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) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls 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 ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) 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 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 ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution 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 ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis 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 ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 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 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) 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 ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed 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 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) 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 1999-09-08 Category:NRC TO UTILITY MONTHYEARML20062D7631990-11-0606 November 1990
[Table view]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 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 ML20059C4011990-08-24024 August 1990 Forwards Insp Repts 50-280/90-23 & 50-281/90-23 on 900723-27.Violations 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 ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248B4731989-09-21021 September 1989 Forwards Insp Repts 50-338/89-26 & 50-339/89-26 on 890716- 0822 & Notice of Violation ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu 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 ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247C2011989-09-0707 September 1989 Forwards Safety Evaluation Accepting Util 890512 Response to IE Bulletin 80-11, Masonry Wall Design ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM 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 ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted 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 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 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 1990-09-07 Category:OUTGOING CORRESPONDENCE MONTHYEARML20212J9101999-10-0101 October 1999
[Table view]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 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam 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 ML20217D6621999-05-14014 May 1999 Forwards NRC Operator Licensing Exams 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15.Nine Candidates Passed (& One Failed) Exam 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 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 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 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 ML20199D2291999-01-12012 January 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core of Over Safety-Related Equipment 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 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 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 ML20236Q6751998-07-13013 July 1998 Forwards Insp Repts 50-280/98-05 & 50-281/98-05 on 980503-0613.No Violations Were Identified.Conduct of Activities at Surry Facilities Was Generally Characterized by safety-conscious Operations,Sound Engineering & Maint 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 1999-09-08 |
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e NOV 2 0 1985 Virginia Electric and Power Company d ATTN: 'Mr. W. L. Stewart, Vice President Nuclear Operations P. O. Box 26666 Richmond, VA 23261 Gentlemen:
SUBJECT:
DOCKET NOS.: 50-280, 50-281, 50-338.AND 50-339-We have just completed our review of the revision dated August 29, 1985, of the Virginia Corporate Emergency Plan. Our review indicates that your emergency plan continues to meet the planning standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.
Please be reminded that 10 CFR 50.54(q) requires NRC approval of any changes to your; plan which may decrease the effectiveness of the plan. However, if your safety review indicates no decrease in emergency preparedness, then changes can be made without NRC approval. In all cases, you should furnish the NRC with copies of each change to the plan in accordance with 10 CFR 50.54(q). Also, any changes to the Emergency Plan Implementing Procedures should be made in accordance with the requirements of 10 CFR 50, Appendix E, Section V
'(Implementing Procedures).
Should you have any questions regarding this letter, please contact Ms. M. Poston-Brown of our staff at (404) 221-4717.
Sincerely, Virgil L. Brownlee, Chief Reactor Projects Branch 2 Division of Reactor Projects cc: d. J. Hardwick, Jr. , Manager -
VI. Nuclear Programs W. Harrell, and Station Licensing Manager North Anna Power Station
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