Similar Documents at Surry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 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 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 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 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) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution 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 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) 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 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 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 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) 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 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) 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) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required 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) 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 ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 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 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 ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI 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 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 ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20059C4011990-08-24024 August 1990 Forwards Insp Repts 50-280/90-23 & 50-281/90-23 on 900723-27.Violations Noted 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 ML20059M8771990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20245C3141989-06-0808 June 1989 Advises That Parts of 890324 Rev 23 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan.Changes Inconsistent W/Provisions Listed in Encl.Encl Withheld (Ref 10CFR73.21) ML20247D1731989-05-18018 May 1989 Forwards Amends 127 to Licenses DPR-32 & DPR-37 & Safety Evaluation.Amends Change Tech Spec 6.5.B.7, Station Operating Records by Clarifying Requirement to Retain Photographs of Scope Traces of Welds ML20236B7391989-03-0101 March 1989 Advises That 890104 Rev 2 to Security Contingency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20235U1831989-02-24024 February 1989 Confirms Mgt Meeting at Util on 890228,per 890217 Telcon. Proposed Meeting Agenda Encl ML20245E8621989-01-13013 January 1989 Forwards Insp Repts 50-280/88-50 & 50-281/88-50 on 881212-16.No Violations or Deviations Noted ML20196C5261988-11-23023 November 1988 Forwards Insp Repts 50-280/88-40,50-281/88-40,50-338/88-28 & 50-339/88-28 on 880926-30.No Violations or Deviations Noted ML20155J1801988-10-14014 October 1988 Advises That 880914 Rev 13 to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20153E7671988-08-23023 August 1988 Informs That Safety Sys Functional Insp Will Be Conducted by Region II Insp Team at Facilities on 880912-16 & 26-30.Insp Effort Will Be Focused on Svc Water Sys & Associated Sys Served by Svc Water ML20207H9161988-08-19019 August 1988 Advises That 880616 Rev to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20151Q5111988-08-0404 August 1988 Ack Receipt of Payment of Civil Penalty in Amount of $100,000,per Util .Violation B Re Maint Procedure for Replacing in-core Flux Mapping Detector Remains as Stated ML20151K7321988-07-22022 July 1988 Advises That 880218 Rev to Plant Emergency Plan Meets Planning Stds of 10CFR50.47(b) & Requirements of App E & Acceptable ML20151V7121988-04-27027 April 1988 Advises That Portion 880318 Rev 21 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Other Portions Are Not Consistent W/Provisions of 10CFR50.54(p) as Delineated in Encl.Encl Withheld (Ref 10CFR73.21) ML20148J0841988-03-10010 March 1988 Ack Receipt of 880222 Response to 880125 Notice of Violation for Insp Repts 50-280/87-35 & 50-281/87-35 ML20234F2961987-12-31031 December 1987 Advises That 871116 Rev 19 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Encl Withheld (Ref 10CFR73.21) ML20237A5171987-12-0707 December 1987 Advises That Operator Licensing Exams Scheduled for Wk of 880314,including Written,Simulator/Operating & Plant Oral Exams.Encl List of Approved Ref Matl Requested by 880114 to Avoid Delay in Administering Exams ML20234A9741987-09-0808 September 1987 Forwards Request for Addl Info Re 861211 Proposed Amend to Physical Security Plan,Including Rev to Existing Schedule for Safeguards Requirements to Indicate Implementation within 180 Days.Response Requested within 30 Days IR 05000280/19870121987-07-0808 July 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-280/87-12 & 50-281/87-12.Corrective Actions Will Be Examined During Future Insps ML20234F2591987-06-25025 June 1987 Ack Receipt of Transmitting Rev 11 to Surry ISFSI Security Personnel Training & Qualification Plan. Changes Consistent W/Provisions of 10CFR72.84 & Acceptable ML20234C8301987-06-25025 June 1987 Advises That 870529 Rev 11 to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20214V9731987-05-21021 May 1987 Forwards Insp Repts 50-280/87-09 & 50-281/87-09 on 870405-0502.Vo Violatios or Deviations Noted.Attention Directed to Unresolved Item Identified in Rept.Matter Will Be Pursued During Future Insp ML20215J3941987-05-0505 May 1987 Forwards NRC Granting Extension to 871201 for Providing Schedule of plant-specific Implementation Re USI A-46, Equipment Seismic Adequacy Verification Requirements ML20206C0271987-04-0909 April 1987 Advises That 1987 Financial Info Submitted by Satisfies Requirements of 10CFR140.21 ML20209E1641987-04-0303 April 1987 Forwards Exam Rept 50-280/OL-87-01 Administered on 870209-11.Written Exam Questions & Answer Key & Util Comments Re Written Exam Also Encl ML20206C4421987-03-27027 March 1987 Ack Receipt of 861113 Response to 861014 Notice of Violation Re Insp Repts 50-280/86-20 & 50-281/86-20.Violation Re Inadequate Procedures for Work Performed on Recirculation Spray HXs Classified as Severity Level V Violation ML20205N3731987-03-25025 March 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-280/86-42 & 50-281/86-42 ML20205Q1121987-03-24024 March 1987 Forwards Insp Repts 50-280/87-03 & 50-281/87-03 on 870209-13 & Notice of Violation.Concern Expressed That Implementation of Radioactive Matls Transportation Program Permitted Situation to Develop ML20207T6681987-03-12012 March 1987 Confirms 870325 Meeting in Richmond,Va to Discuss NRC PRA Application Program for Conducting Insps at Nuclear Power Stations,Per 870305 Telcon.Meeting Will Include Technical Discussion of How PRA Will Develop Insp Techniques ML20207T6211987-03-0606 March 1987 Forwards Insp Repts 50-280/87-04 & 50-281/87-04 on 870201- 28.No Violations or Deviations Noted ML20212K8871987-03-0303 March 1987 Forwards Notice of Denial of Amends to Licenses DPR-32 & DPR-37 & Opportunity for Hearing Based on Review of Util 801028,830921 & 850412 Requests to Delete Tech Spec 4.15 Re High Energy Pipe Break Insp Program ML20212H9611987-03-0303 March 1987 Ack Receipt of Transmitting 861121 Rev to Security Contingency Plans.Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion in Plan ML20207T5791987-03-0202 March 1987 Forwards Safety Insp Rept 50-281/86-36 on 861113-20 & 870209 & Notice of Violation.Type a Test Shall Be Performed During Each Refueling Outage Until Two Consecutive Tests Meet Acceptable Criteria of 10CFR50,App J ML20212J2161987-03-0202 March 1987 Forwards Safety Evaluation & Technical Evaluation Rept Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys On-Line Functional Testing. Response Acceptable ML20212E6971987-02-27027 February 1987 Urges Industry Response to Check Valve Issues Initially Highlighed by San Onofre Unit 1 Event in Nov 1985.Concerns Noted Re Potential Implications for All Nuclear Power Plants in Light of Surry 2 Event.Evaluation of Programs Requested ML20207T6781987-02-23023 February 1987 Forwards Insp Repts 50-280/87-02 & 50-281/87-02 on 870202-06.No Violations or Deviations Noted ML20211M7801987-02-19019 February 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-280/86-34 & 50-281/86-34.Response Meets Requirements of 10CFR2.201 ML20211M9261987-02-17017 February 1987 Forwards NRC Re Policy for Managing Emergency Notification Sys & Health Physics Network.Licensee Should Assign Knowledgeable Individual to Maintain Open,Continuous Communication Channel ML20211M7841987-02-17017 February 1987 Confirms 870420-24 Insp at Facility,Per 870205 Telcon. Compliance W/Sections Iii.G,Iii.J,Iii.L & Iii.O of App R to 10CFR50 Will Be Evaluated During Insp.Listed Addl Info Requested by 870330 ML20207T3681987-02-13013 February 1987 Confirms 870204 Telcon Re Rescheduling 870123 Mgt Meeting to 870312,to Review Results of NRC SALP Program for Mar 1985 - Aug 1986 ML20211M0511987-02-13013 February 1987 Forwards Insp Repts 50-280/86-41 & 50-281/86-41 on 861207- 870131.No Violations or Deviations Noted.Attention to Unresolved Items Requested ML20211C4351987-02-10010 February 1987 Forwards Augmented Insp Repts 50-280/86-42 & 50-281/86-42 on 861209-870114 & Notice of Violation.Rept on 861209 Reactor Trip & Feedwater Pipe Failure Event Reviewed. Staff Concurs W/Planned Actions ML20210V1761987-02-0606 February 1987 Forwards Insp Repts 50-280/87-01 & 50-281/87-01 on 870112-15.No Violations or Deviations Noted ML20210A3691987-01-23023 January 1987 Forwards Summary of 870112 Mgt Meeting W/Util at Plant to Discuss Findings & Plans Re 861209 Pipe Rupture.Util Understands Enough of Failure Mechanism Involved to Take Corrective Actions & Restart Units.Attendees List Encl ML20213A1551987-01-16016 January 1987 Extends Invitation to Participate in 870218 Incident Investigation Program Workshop in Atlanta,Ga.Workshop Will Provide Understanding of Process by Which NRC Investigates Potential Significant Incidents.Agenda Encl.W/O Procedures IR 05000280/19850291987-01-14014 January 1987 Forwards NRC Confirmatory Measurement Results of Util Radiochemical Analyses Submitted in 860711 & Oct 1986 Ltrs, Per Insp Repts 50-280/85-29 & 50-281/85-29.Comparative Results in Disagreement for Fe-55 Analysis.W/O Encls ML20215H6981987-01-12012 January 1987 Forwards Info Re PRA-based Interactive Sys Called Plant Risk Status Info Mgt Sys (Prisim) to Assist NRC Inspectors in Planning Insp Activity.Extends Invitation to Discuss Prisim W/Util Personnel.W/O Encl ML20207P4761987-01-0909 January 1987 Confirms 870123 Mgt Meeting to Review Results of SALP Program.Program Involves Appraisal of Regulatory Performance by Selected NRC Managers.Regulatory Performance Evaluated for Mar 1985 - Aug 1986 ML20207P2161987-01-0808 January 1987 Requests Submittal of Emergency Exercise Info to Chief of Emergency Preparedness Section,Region Ii,To Protect Scenario & Objectives (Ref ) 1990-08-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20216F1381999-09-0808 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 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 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 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 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 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 ML20249A7951998-06-12012 June 1998 Responds to from R Saunders & L Liberatori Requesting Waiver of Fee to Review 971031 Plant,Unit 1 Risk-Informed Inservice Insp Submittal ML20217P4601998-05-0101 May 1998 Forwards ERDS Implementation Documents Including Data Point Library Updates for Robinson (Number 248),Peach Bottom (Number 249),Surry (Number 250),Crystal River (Number 251), McGuire (Numbers 252 & 254) & Salem (Number 253).W/o Encl ML20199G0741998-01-23023 January 1998 Discusses 980116 Meeting W/Utility in Atlanta,Ga to Provide VEPCO Opportunity to Discuss Performance at Surry Facility. List of Attendees,Plant Self Assessment ,safety Culture Memo & Suppl Handout Encl ML20198Q6451997-11-10010 November 1997 Ack Receipt of & Check for $55,000 in Payment for Civil Penalty Proposed by NRC in .Corrective Actions Will Be Examined During Future Insps ML20211N2701997-10-0707 October 1997 Forwards Insp Repts 50-280/97-11 & 50-281/97-11 on 970924. No Violations or Deviations Noted.Insp Determined Whether Activities Authorized by Licensee Were Conducted Safely & IAW NRC Requirements IR 05000280/19970011997-08-29029 August 1997 Discusses Insp Repts 50-280/97-01 & 50-281/97-01 on 970113 & 17 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000 ML20141D5001997-06-25025 June 1997 Responds to 960408 Submittal Re NRC Bulletin 96-001, Control Rod Insertion Problems. Staff Determined That Required Actions Completed for North Anna Power Stations Units 1 & 2 & for Surry Power Stations,Units 1 & 2 ML20141B2731997-05-0505 May 1997 Ltr Contract:Task Order 44, Initial Exam for Surry NPP, Under Contract NRC-03-94-035,awarded to Sonalyst,Inc ML20137R2791997-03-27027 March 1997 Twentieth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App FF ML20136C4211997-03-0606 March 1997 Fifteenth Partial Response to FOIA Request for Records. App Y Records Encl & Available in PDR ML20134P3181997-02-20020 February 1997 Notifies Nuclear Power Reactor Licensees of Potential Problem Involving Protected Area Access Control at Nuclear Reactor Sites.Encl Being Withheld Due to Sensitive Info Contained within ML20133F5081996-12-31031 December 1996 Forwards Recent Revision to NRC Enforcement Policy Re All Predecisional Enforcement Conferences Scheduled After 961210.All Open to Public Observation W/Some Exceptions.Copy of Change Noted in 61FR65088 Encl ML20132E3431996-12-19019 December 1996 Fowards Emergency Response Data System Implementation Documents.W/O Encl ML20149M5511996-12-0606 December 1996 Discusses 961118 Meeting Re SALP for Surry Facility.List of Attendees & SALP Slides Encl IR 05000280/19960101996-10-28028 October 1996 Forwards Insp Repts 50-280/96-10 & 50-281/96-10 on 960908-28 & Notice of Violation ML20129H0411996-10-23023 October 1996 Extends Invitation to 961118 SALP Meeting at Plant as Observer.Subsequent to Meeting,Time Scheduled to Discuss Matters of Mutual Interest W/Regard to Regulation & Performance at Plant ML20129B8121996-10-10010 October 1996 Informs That Region II Will Host Annual Training Conference in Atlanta,Ga on 961120-21 to Inform Regional Operations & Training Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators.Map Encl ML20128G9071996-10-0303 October 1996 Forwards ERDS Implementation Documents & Data Point Library Updates for Listed Plant.W/O Encl ML20134C5451996-09-19019 September 1996 Discusses 960916 Meeting W/Util in Atlanta,Ga Re Licensee Proposal for Reviewing & Revising UFSAR ML20134C5401996-09-11011 September 1996 Confirms Predecisional Enforcement Conference to Be Held on 960909 & 10 in Atlanta,Ga to Discuss Apparent Violation Re Licensee Failure to Follow Procedures for Pressurizer Relief Tank Venting.Subj Meeting to Be Closed IR 05000280/19950201996-08-16016 August 1996 Informs That NRC Has Recently Completed Investigation of Apparent Willful Violation of Operational Procedure at Plant as Followup to Insp Repts 50-280/95-20 & 50-281/95-20 ML20059M8071993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide Re Proposed Rule for Protection Against Manevolent Use of Vehicles at Nuclear Power Plants.Encl Withheld (Ref 10CFR73) ML20059C3471993-10-21021 October 1993 Forwards Exam Repts 50-280/93-300 & 50-281/93-300 Administered During Wk of 930920 ML20128A4951993-01-22022 January 1993 Forwards Amends 173 & 172 to Licenses DPR-32 & DPR-37 & Se. Amends Revise TS to Modify Acceptance Criteria for Functional Testing of Anchor Darling Mechanical Snubbers ML20127D2741993-01-0707 January 1993 Advises That 921222 Rev 16 to Surry,Units 1 & 2 Nuclear Security Personnel Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20128Q3741991-08-26026 August 1991 Forwards Insp Repts 50-280/91-22,50-281/91-22,50-338/91-18 & 50-339/91-18 on 910731 & 0801-02.No Violations Observed ML20128Q3441991-07-11011 July 1991 Forwards Insp Repts 50-280/91-15 & 50-281/91-15 on 910520-22 & 0619.No Violations Observed ML20128Q4651991-04-17017 April 1991 Forwards Insp Repts 50-280/91-09 & 50-281/91-09 on 910326- 29.No Violations Noted ML20128Q5101991-04-12012 April 1991 Forwards Insp Repts 50-280/91-06 & 50-281/91-06 on 910224-0330 & Notice of Violations ML20059C4011990-08-24024 August 1990 Forwards Insp Repts 50-280/90-23 & 50-281/90-23 on 900723-27.Violations Noted 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 ML20059M8771990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20245C3141989-06-0808 June 1989 Advises That Parts of 890324 Rev 23 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan.Changes Inconsistent W/Provisions Listed in Encl.Encl Withheld (Ref 10CFR73.21) ML20247D1731989-05-18018 May 1989 Forwards Amends 127 to Licenses DPR-32 & DPR-37 & Safety Evaluation.Amends Change Tech Spec 6.5.B.7, Station Operating Records by Clarifying Requirement to Retain Photographs of Scope Traces of Welds ML20236B7391989-03-0101 March 1989 Advises That 890104 Rev 2 to Security Contingency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20235U1831989-02-24024 February 1989 Confirms Mgt Meeting at Util on 890228,per 890217 Telcon. Proposed Meeting Agenda Encl ML20245E8621989-01-13013 January 1989 Forwards Insp Repts 50-280/88-50 & 50-281/88-50 on 881212-16.No Violations or Deviations Noted ML20196C5261988-11-23023 November 1988 Forwards Insp Repts 50-280/88-40,50-281/88-40,50-338/88-28 & 50-339/88-28 on 880926-30.No Violations or Deviations Noted ML20155J1801988-10-14014 October 1988 Advises That 880914 Rev 13 to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20155F7911988-09-0707 September 1988 Final FOIA Request for Documents Re Radwaste Facilities at Plants.Forwards App B Document.App a & B Documents Available in PDR IA-88-419, Final FOIA Request for Documents Re Radwaste Facilities at Plants.Forwards App B Document.App a & B Documents Available in PDR1988-09-0707 September 1988 Final FOIA Request for Documents Re Radwaste Facilities at Plants.Forwards App B Document.App a & B Documents Available in PDR ML20153E7671988-08-23023 August 1988 Informs That Safety Sys Functional Insp Will Be Conducted by Region II Insp Team at Facilities on 880912-16 & 26-30.Insp Effort Will Be Focused on Svc Water Sys & Associated Sys Served by Svc Water ML20207H9161988-08-19019 August 1988 Advises That 880616 Rev to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable 1999-09-08
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I December 7, 1987 j 1
i Virginia Electric and Power Company ATTN: Mr. W. L. Stewart Vice President, Nuclear Operations P. O. Box 26666 j Richmond, VA 23261 1 4
Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS i In a telephone conversation between Mr. Harold McCallum, Supervisor - Training, and Mr. Ronald F. Aiello, NRC Region II Operator Licensing Section, arrangements were made for of the administration Reactor Operator and Senior Reactor Operator replacement examinations at the Surry Power Station.
The written examinations are scheduled for the week of March 14, 1988. The simulator / operating examinations are scheduled for March 15-17, 1988 at the Surry simulation facility. The plant oral examinations are scheduled for March 15-17, 1988.
In order for us to meet the above schedule, it will be necessary .for the facility to furnish the approved reference material listed in Enclosure 1,
" Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by Janurary 14, 1988. Any delay in receiving properly bound and indexed reference material will result in a delay in administering the examinations. Our examinations are scheduled far in advance with considerable planning to utilize our present limited examiner marnower and to meet the examination dates requested by the various facilities. Therefore, missing the January 14, 1988 deadline, even by a few days, will likely result in a long delay, because it may not be possible to reschedule examinations at other J
facilities. Mr. McCallum %s man advised of our reference material sets that !
are required, and the examia ' names and addresses where each set is to be !
mailed.
The facility management is responsible for providing adequate space and accom-modations in order to properly conduct the written examinations. Enclosure 2,
" Requirements for Administration of Written Examinations," describes our requirements for conducting these examinations. Mr. McCallum has also been informed of these requirements. -
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Nb 57 871207 V $00CM 05000200 PDR rt it..
i Virginia Electric and Power Company 2 December 7, 1987 In addition, to better document simulator examinations, the chief examiner will have the facility simulator operator record prespecified plant conditions (i.e., plant pressure, temperature, pressurizer level, etc.), for each simulator scenario. The candidate will be responsible for providing this information, along with any appeal of his simulator operating examination. Therefore, the (
facility training staff should retain the simulator examination scenario information until all candidates taking the examination have either passed the operating examination or all appeals filed by the candidates who failed the operating examination have been completed.
Enclosure 2 also contains the Rules and Guidelines that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all candidates are aware of these Rules.
All reactor operator and senior reactor operator license application information should normally be submitted at least 60 d- before the first examination dates so that we will be able to review the tra g and experience of the cardidates, l process the medical certifications, and lTepare final examiner assignments after l candidate eligibility has been determined. If the application information is not j received at least 30 days before the examination dates, it is possible that a postponement will be necessary.
This request for information was approved by the Office of Management and Budget under Clearance Number 3150-0101 which expires on May 31, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, i Reports Management, Room 3208, New Executive Office Building, Washington, DC '
20503.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 3, " Requirements for Facility Review of Written Examination." Mr. McCallum has been informed of these requirements.
Thank you for your consideration in this matter. If you have any questions !
regarding the examination procedures and requirements, please contact Mr. John F. Munro, Chief, Operator Licensing Section, at 404/331-5594 or j Mr. Ronald F. Aiello at 404/331-5604.
Sincerely, (ORIGINAL SIGNED EY C. A. JULIAN)
Caudle A. Julian, Chiei Operations Branch Division of Reactor Sa'ety
Enclosures:
- 1. Reference Material Requirements
- 2. Requirements for Administration of Written Exams
- 3. Facility Review Requirements cc: (See page 3)
Virginia Electric and Power Company 3 December 7, 1987 I
i cc w/encis:
Harold McCallum, Training Supervisor P D. L. Benson, Station Manager bec w/encls:
Projects Manager, NRR Section Chief, DRP R. Aiello, OL Examiner Senior Resident Inspector t Document Control Desk l State of Virginia l
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i RJI RII RII RII \ / i r$2 PRShaw:sh j?kuAA RFAiello Munro
( f.
CAJulian 12/4/87 12/ 3 /87 12/3 /87 12/}/87
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'I-a ENCLOSURE 1 j REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS t
- 1. Existing learning objectives and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermo- 1 dynamics,etc.) I Training materials should include all substantive written material used for- ;
l preparing candidates for initial RO and SR0 licensing. The written material j should be inclusive of learning objectives and the details presented during i l lecture, rather than outlines. Training materials should be identified by ,
I plant and unit, bound, and indexed. Failure to provide complete, properly l l bound and indexed plant reference material will result in canceling or l rescheduling of the examinations. Training materials which include the following should be provided: '
- a. System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
- b. Complete and operationally useful descriptions of all safety-system l interactions and, where available, 80P system interactions under I emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure, i c. Training material used to clarify and strengthen understanding of emergency operating procedures.
- d. Comprehensive theory material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat transfer and fluid flow, as well as specific application to actual in-plant components. For example, mechhnical theory material on pumps should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed (i.e. , Reactor Coolant pumps, all ECCS pumps, Recirculation pumps, Feedwater pumps and Emergency feedwater pumps). Reactor theory material should include descriptions that draw explicit ties between the fundamentals and the actual operating limits followed in the plant l (i.e., reactor theory material should contain explanations of how j principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP). l l
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l Enclosure 1 2 !
- 2. Procedure Index (alphabetical by subject)
- 3. All administrative procedures (as applicable to reactor operation or safety)
- 4. All intec sted plant procedures (normal or general operating procedures)
- 5. Emergency procedures (emergency instructions, abnormal or special procedures)
- 6. Standing orders (important orders that are safety-related and may supersede {
the regular procedures)
- 7. Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)
- 8. Annunciator procedures (alarm procedures, including set points)
- 9. Radiation protection manual (radiation control manual or procedures)
- 10. Emergency plan implementing procedures
- 11. Technical Specifications
- 12. System operating procedures 1
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagr6ms
- 14. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility
- 15. Questions and answers that the facility licensee has prepared (voluntary by facility licensee) l
- 16. The following on the plant reference simulation facility I
- a. List of all readily available initialization points
- b. List of all preset malfunctions with a clear identification number.
The lst should include cause and effect information. . Specifically, for each malfunction, a concise description of the expected result, or range of results, that will occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given,
- c. A description of simulator failure capabilities for valves, breakers, indicators and alarms.
Enclosure 1 3 ;
- d. Where the capability exists, an explanation of the ability to vary the 3 severity of a particular malfunction should be provided, i.e., ability to vary the size of a given LOCA or steam leak, or the ability to cause a slow failure of a component such as a feed pump, turbine generator or j major valve (e.g., drifting shut of a main feedwater control valve) !
- e. An identification of modeling conditinns/ problems that may impact the examination
- f. Identification of any known Performance Test Failures not yet completed i
- g. Identification of significant differences between the simulator and the reference plant's control room
- h. Copies of facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR), and containment challenges (BWR) may be i provided (voluntary by licensee)
- i. Simulator instructors manual (voluntary by licensee) <
- j. Description of the scenarios used for the training class (voluntary by licensee)
- 17. All material different from that listed in items 1-16 that is specific to the Operator Requalification Training Program
- 18. Additional material required by the examiners to develop examinations that-meet the requirements of these standards and the regulations.
The above reference material should be approved, final issues and should be so marked. If a plant has not finalized some of the material, the chief examiner shall verify with the facility that the most complete, up-to-date mater 1al is available and that agreement has been reached with the licensee for limiting changes before the administration of the examination. All procedures and j reference material should be bound with appropriate indexes or tables of contents so that they can be used efficiently.
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ENCLOSURE 2 l REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shal' be 1 such as to prevent contact with all other facility and/or contract.or personnel during the duration of the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a j local school, motel, or other building. Obtaining this room is the ;
responsibility of the licensee.
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- 2. Minimum spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one candidate per table, with a 3-ft, space between tables. No wall charts, models, and/or other training materials shall be present in the examination room.
- 3. Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshment?. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working t days to provide formal written comments with supporting documentation on the examination and answer key to the chief examiner or to the regional office section chief.
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- 5. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each candidate's use in completing the examination.
The examiner shall distribute these pads to the candidates. All reference material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens, pencils, calculators, or slide l rules into the examination room, and no other equipment or reference I material shall be allowed. j
- 6. Only black ink or dark pencils should be used for writing answers to questions.
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i Enclosure 2 2 i l
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS t During the administration of this examination the following rules apply: I
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions. j
- 4. Print your name in the blank provided on the cover sheet of the examination.
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- 5. Fill in the date on the cover sheet of the examination (if necessary). I
- 6. Use orly the paper provided for answer:>.
- 7. Print your name in the upper right-hand corner of the first page of each j section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as )
appropriate, start each category on a new page, write on only one side of .
the paper, and write "Last Page" on the last answer sheet.
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- 9. Number each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
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- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems, whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
Enclosure 2 3
- 16. If parts of the examination are not clear as to intent, ask questions of.
the examiner only.
- 17. You must sign the statement on the. cover sheet that indicates.that the work is your own and you have not -received or been given assistance in completing the examination. This must be done after the examination has been completed.
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- 18. When you complete your examination, you shall: .I
- d. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
I (3) Answer pages including figures which are a part of the answer.
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- b. Turn in your copy of the examination and all pages used to answer ;
the examination questions. l l c. Turn in all scrap paper and the balance of the paper that you did I
not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after l leaving, you are found in this area while the examination is still I in progress, your license may be denied or revoked, i l
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ENCLOSURE 3 i
REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATION -
- 1. There shall be no review of the written examination by the facility staff before or during the administration of the examination. Following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key.
- 2. The facility will have five (5) working days from the day the written examination is given to provide formal comment submittal. The submittal l will be made to the responsible regional office by the highest level of i coporate management for plant operations,-e.g., Vice President for Nuclear Operations. A copy of the submittal will be forwarded to the chief examiner, as appropriate. Comments not submitted within five (5) working days will be considered for inclusion in the grading process on a case by case basis by the regional office section chief. Should the comment subnittal deadline not be met, a long delay for finalization of the examination results may occur.
- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC question, answer and reference .)
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- b. Facility comment
- c. Supporting documentation NOTES: 1. No change to the examination will be made without submittal of complete, current, and approved reference material. l
- 2. Comments made without' a concise facility recommendation will not be addressed.
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