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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E0451990-11-13013 November 1990 Discusses 901106 Meeting Re Alternative Tube Plugging Criteria for Facility Steam Generators ML20062D6911990-11-0909 November 1990 Forwards SER Re Response to Generic Ltr 88-11 Concerning NRC Position on Radiation Embrittlement of Reactor Vessel. Compliance w/10CFR50,Appendix G,For Min Upper Shelf Energy Could Not Be Verified.Operation for 16 EFPY Acceptable ML20058F7931990-11-0606 November 1990 Forwards Summary of NRC Understanding of Current Status of Unimplemented Generic Safety Issues for Plant,Per Util 900627 Response to Generic Ltr 90-04 ML20058B4021990-10-19019 October 1990 Forwards Summary of 900913 Mgt Meeting Re Emergency Preparedness Program & Onsite Technical Support Ctr ML20058B1391990-10-16016 October 1990 Forwards Insp Repts 50-348/90-28 & 50-364/90-28 on 900911-1012.No Violations or Deviations Noted ML20062B7031990-10-12012 October 1990 Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20058B2581990-10-12012 October 1990 Ack Receipt of 900807 & 0904 Ltrs Transmitting Objectives & Scenario Package for Exercise Scheduled on 901024 ML20059N6721990-10-0909 October 1990 Responds to Util 900702 Request for Authorization to Use ASME Boiler & Pressure Vessel Code Case N-395.Request Acceptable IR 05000348/19900181990-10-0909 October 1990 Ack Receipt of 900926 Response Re Violations Noted in Insp Repts 50-348/90-18 & 50-364/90-18 ML20062C6601990-10-0909 October 1990 Ack Receipt of 900913 Response to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19 ML20059N3481990-09-24024 September 1990 Forwards Insp Repts 50-348/90-24 & 50-364/90-24 on 900827-31.No Violations or Deviations Noted ML20059K1311990-08-28028 August 1990 Confirms Mgt Meeting on 900913 to Discuss Timeliness of Activation of Emergency Response Facilities ML20059H0921990-08-23023 August 1990 Forwards Insp Repts 50-348/90-20 & 50-364/90-20 on 900711-0810.No Violations or Deviations Noted ML20059B3421990-08-23023 August 1990 Advises That Util 900131 Response to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations,Satisfactory ML20056B3721990-08-21021 August 1990 Forwards Order Imposing Civil Monetary Penalty in Amount of $450,000 Re Violations,Per 870914-18,1102-06 & 16-21 Insps. Violations Include Failure to Demonstrate Splice Qualification & Failure to Maintain Environ Qualification ML20058M9441990-08-0303 August 1990 Forwards Insp Repts 50-348/90-19 & 50-364/90-19 on 900711-13 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21) ML20058P8661990-07-31031 July 1990 Forwards Insp Repts 50-348/90-21 & 50-364/90-21 on 900709-13.No Violations or Deviations Noted ML20055H4251990-07-13013 July 1990 Forwards Insp Repts 50-348/90-16 & 50-364/90-16 on 900611-0710.Violations Noted,But Not Cited ML20055H6501990-07-13013 July 1990 Forwards Insp Repts 50-348/90-17 & 50-364/90-17 on 900618-22.No Violations or Deviations Noted IR 05000348/19900121990-07-10010 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12.Part (a) of Violation Agreed with Denial & Withdrew This Portion & Revised Records Accordingly ML20059M8061990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3961990-02-23023 February 1990 Forwards Insp Repts 50-348/90-04 & 50-364/90-04 on 900129-0202.No Violations or Deviations Noted ML20248B0201989-09-18018 September 1989 Forwards Summary of 890912 Mgt Meeting in Region II Ofc Re Configuration Mgt Program & Findings of self-initiated Safety Sys Assessment of Svc Water Sys.List of Attendees & Meeting Agenda Also Encl ML20247K0821989-09-15015 September 1989 Forwards Amend 8 to Indemnity Agreement B-81,reflecting Revs to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Increasing Liability Insurance ML20248C2061989-09-15015 September 1989 Advises of Special Emergency Operating Procedure Insp Program Being Performed at Plant on 891127-1208 to Verify That Procedures Technically Accurate & That Actions Can Be Accomplished W/Equipment,Controls & Instrumentation ML20247G5401989-09-12012 September 1989 Forwards Insp Repts 50-348/89-19 & 50-364/89-19 on 890821-25.No Violations or Deviations Noted.Licensed Operator Performance During Simulator Training Did Not Meet Expectations ML20247G9511989-09-12012 September 1989 Forwards Insp Repts 50-348/89-18 & 50-364/89-18 on 890731-0804 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21) ML20247G6611989-09-0707 September 1989 Confirms 890906 Telcon W/J Garlington & D Verrelli Re Mgt Meeting Scheduled for 890912 in Region II Ofc to Discuss Results of Licensee self-initiated Safety Assessment ML20247F4881989-09-0606 September 1989 Ack Receipt of Responding to Violations Noted in Insp Repts 50-348/89-13 & 50-364/89-13.Implementation of Corrective Actions Will Be Examined During Future Insps ML20246N7041989-08-25025 August 1989 Forwards Insp Repts 50-348/89-17 & 50-364/89-17 on 890724-28.No Violations or Deviations Noted ML20246P3561989-08-17017 August 1989 Forwards Insp Repts 50-348/89-16 & 50-364/89-16 on 890711-31.No Violations or Deviations Noted ML20246G3921989-08-11011 August 1989 Confirms Util Participation in NRC Regulatory Impact Survey on 890911,per 890808 Telcon.Agenda Encl ML20245K5571989-08-0909 August 1989 Advises That 890601 Rev 16 to Emergency Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20245H9851989-08-0303 August 1989 Requests Responses to Encl Questions Re Requests for Relief from ASME Code Requirements of Second 10-yr Inservice Insp within 45 Days of Ltr Receipt ML20245H1201989-08-0202 August 1989 Requests That Encl Ref Matls Be Furnished to NRC by 890825 for Requalification Program Exam Scheduled for Wk of 891023 ML20248C8061989-08-0101 August 1989 Forwards Insp Repts 50-348/89-10 & 50-364/89-10 on 890424-27 & 0508-12 & Notice of Violation.Unresolved Item Identified ML20247R9781989-07-28028 July 1989 Forwards Final FEMA Rept on 881102 Emergency Response Exercise.Identified Deficiency Promptly Corrected.Resolution of Weaknesses,Identified by Fema,Should Be Corrected Prior to Next full-scale Emergency Preparedness Exercise ML20245F1971989-07-26026 July 1989 Forwards Insp Repts 50-348/89-14 & 50-364/89-14 on 890611-0710.No Violations or Deviations Noted.Matter Re Apparent Excessive Work Hours for Licensed Operators Will Be Discussed W/Util at 890731 Meeting in Region II Ofc ML20247R5141989-07-26026 July 1989 Forwards Insp Repts 50-348/89-13 & 50-364/89-13 on 890509-10 & Notice of Violation.Fact That Two Independent Actions Involving Unauthorized Use of Radioactive Matls Occurred within Short Time Indicates Disrespect for Radioactivity ML20247E2691989-07-20020 July 1989 Forwards Exam Rept 50-348/OL-89-01 Administered During Wks of 890619 & 26.Concerns Noted Re Operator Performance & Exam Admin.Concerns Will Be Discussed at 890731 Mgt Meeting at Region II Ofc IR 05000348/19890111989-07-18018 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-11 & 50-364/89-11 ML20246L8101989-07-13013 July 1989 Forwards Antitrust Settlement Notice Submitted for Fr Publication ML20246B2391989-06-27027 June 1989 Forwards Insp Repts 50-348/89-12 & 50-364/89-12 on 890511-0610.No Violations or Deviations Noted ML20246B0051989-06-16016 June 1989 Forwards Insp Repts 50-348/89-11 & 50-364/89-11 on 890411- 0510 & Notice of Violation ML20245A8551989-06-13013 June 1989 Forwards SER Supporting Util 831104 & 850422 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20245F5031989-06-13013 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-07 & 50-364/89-07 ML20245G3171989-06-13013 June 1989 Requests Completion of Radiochemical Analyses of Liquid Samples Spiked W/Radionuclide within 60 Days of Receipt of Samples ML20248A1751989-06-0202 June 1989 Ack Receipt of 890407 Response to Violations Noted in Insp Repts 50-348/89-03 & 50-364/89-03.Violation Occurred as Stated in Notice of Violation.Written Statement Describing Corrective Actions Requested.Encl Withheld (Ref 10CFR2.790) ML20247L4481989-05-25025 May 1989 Comments on Licensee 881229 Response to Generic Ltr 88-17 W/Respect to Expeditious Actions for Loss of Dhr.Response Appears to Meet Intent of Ltr But Lacks Details for Listed Items ML20247L6451989-05-25025 May 1989 Requests That Licensee Follow Instructions of 890328 Order & Either Request Hearing or Submit Payment of Civil Penalty Re Operation of Safety Injection Pump W/Gas from Crossover Piping.Hydrogen Accumulation Discovered on 880226 Not 06 1990-09-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20206R4741999-05-13013 May 1999 Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC ML20206M2321999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created ML20206G7341999-05-0404 May 1999 Forwards Safety Evaluation Re Completion of GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206G2411999-04-30030 April 1999 Forwards Revised RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Farley.Requests to Be Notified of Rev to Original Target Date of 990521 ML20206R2031999-04-29029 April 1999 Forwards Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted ML20205T1931999-04-0909 April 1999 Informs That on 990316,J Deavers & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Farley NPP for Y2K.Initial Exam Dates Are Wks of 000508 & 22 for Approx 12 Candidates.Chief Examiner Will Be C Ernstes ML20205Q1541999-04-0606 April 1999 Forwards Insp Repts 50-348/99-09 & 50-364/99-09 on 990308-10.One non-cited Violation Identified ML20205M2831999-04-0202 April 1999 Forwards Errata Ltr for Farley Nuclear Power Plant FEMA Exercise Rept.Page 19 of Original Rept Should Be Replaced with Encl Corrected Page 19 ML20196K4881999-03-19019 March 1999 Forwards Insp Repts 50-348/99-01 & 50-364/99-01 on 990110- 0220.One Violation of NRC Requirements Occurred.Violation Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20205A2611999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Farley Plant Performance Review on 980202.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20204C9561999-03-17017 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Plant,Units 1 & 2.Response Requested by 990521 ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207M2181999-03-11011 March 1999 Advises That Info Contained in 990125 Application CAW-99-1318 & Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20207M1991999-03-0808 March 1999 Partially Withheld Info Re Meeting Held on 990129 at Region II Ofc in Atlanta,Ga to Discuss Physical Protection Measure for Svc Water Intake Structure Located at Facility (Ref 10CFR73.21).List of Attendees Encl ML20206U1831999-02-0909 February 1999 Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed ML20203G5541999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 940407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203G3921999-02-0202 February 1999 Forwards Insp Repts 50-348/98-08 & 50-364/98-08 on 981129- 990109 ML20199L4451999-01-25025 January 1999 Forwards for Review & Comment Revised Draft Info Notice Re Inservice Testing of A-4 Multimatic Deluge Valve for Farley NPP Units 1 & 2.Informs That Comments Submitted on 981120 Were Reviewed & Incorporated Where Appropriate ML20199K7351999-01-21021 January 1999 Responds to 981123 Request by Providing Copy of Latest Draft of Info Notice Being Prepared Which Discusses Failure of Several Preaction Sprinker Sys Deluge Valves.Requests Submittal of Comments by 981120 ML20199K7231999-01-20020 January 1999 Confirms 990119 Telcon Re Informational Meeting Scheduled for 990129 to Be Held in Atlanta,Ga to Discuss Security Related Issues at Plant.Meeting Will Be Closed to Public,Due to Sensitive Nature of Issues ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20199D8541999-01-12012 January 1999 Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199C9361999-01-0808 January 1999 Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted 1999-09-09
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g 36 March 20, 1987 t Alabama Power Company i ATTN: Mr. R. P. Mcdonald Senior Vice President i P. O. Box 2641 l Birmingham, AL 35291-0400 Gentlemen:
SUBJECT:
REQUALIFICATION PROGRAM EVALUATION - FARLEY NUCLEAR PLANT In a telephone conversation between Mr. Lee Williams, Training Manager, and Mr. Jim Moorman, Operator Licensing Section, arrangements were made for an evaluation of the requalification program at the Farley Nuclear Plant.
The evaluation visit is scheduled for the week of June 22, 1987.
! For this visit, the NRC examiner will administer NRC prepared written, oral, i
and simulator examinations. When the NRC examiner arrives at the site, he 1 will meet with the appropriate facility personnel to review the schedule for these examinations. For the examiner to adequately prepare for this visit, it will be necessary for the facility to furnish the approved reference material listed in Enclosure 1, " Reference Material Requirements for Requalification Program Evaluations," by April 22, 1987. Mr. Williams has been advised of our April 22, 1987, reference material requirements and where they are to be sent.
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 b directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, DC 20503.
The facility management is responsible for providing adequate space and facilities in order to properly conduct the written examinations. Enclosure 2,
" Administration of Operator Licensing Written Examinations," describes our d
requirements for conducting these examinations. Mr. Williams has also been informed of these requirements, ohkj4g i
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-l Alabama Power Company .2 March 20, 1987 Thank you for your consideration in this matter. If you have any questions on the evaluation process, please contact Mr. John F. Munro at 404/221-5544.
Sincerely, (Original signed by D. M. Verrelli)
David M. Verrelli, Chief Reactor Projects Branch 1 Division of Reactor Projects
Enclosures:
- 1. " Reference Material Requirements"
- 2. " Administration of Operator Licensing Written Examinations" cc w/encls:
L. S. Williams, Corporate Training Manager J. D. Woodard, Plant Manager bcc w/ encl:
{ Senior Resident Inspector, Farley JDocument Control Desk State of Alabama RII RII / RII
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aw:obw J rman JF o CA fan HCDa 03/y/87 03 9 /87 03/h /87 03//5/87 03/;j/87 f i 1
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1
- ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REQUALIFICATION 4 PROGRAM EXAMINATIONS l 1. Existing learning objectives and lesson plans (including training manuals, j plant' orientation manual, system descriptions, reactor theory, thermo-
- dynamics,etc.)
4 l Training materials should include all substantive written material used for
, preparing candidates for initial R0 and SR0 licensing. The written material should be inclusive of learning objectives and the details presented during lecture, rather than outlines. Training materials should be identified by i
plant and unit, bound, and indexed. Failure to provide complete properly bound and indexed plant reference material will result in canceling and rescheduling of the examinations. Training materials which include the following should be provided:
- a. System descriptions including descriptions of all operationally relevant 1
flow paths, components, controls and instrumentation. System training material should draw parallels to the actual procedures used for l operating the applicable system. ,
a b. Complete and operationally useful descriptions of all safety-system
! interactions and, where available, BOP system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
j c. Training material used to clarify and strengthen understanding of
! emergency operated procedures.
i
- 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.
i For example, mechanical theory material on pumps should include pump j theory as well as descriptions of how these principles actually apply j to major plant pumps and the systems in which they are installed (i.e.,
j Reactor Coolant pumps,,all ECCS pumps, Recirculation pumps, Feedwater l
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 (i.e., reactor theory material should contain explanationa of how principles related to the actual curves are used by operators to verify shutdown margin
, or calculate an ECP).
i h
4 Enclosure 1 2
- 2. Procedure Index (alphabetical by subject)
- 3. All administrative procedures (as applicable to reactor operation or safety)
All integrated plant procedures (normal or general operating procedures)
~
4.
- 5. (emergency instructions, abnormal or special Emergency proceaures ) 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, whenappropriate)
- 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
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 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 licensee has prepared (voluntary by licensee)
- 16. The following on the plant reference simulator
- a. List of all readily available initialization points.
- b. List of all preset malfunctions with a clear identification number.
The list 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.
i.
Enclosure 1 3
- d. Where the capability exists, an explanation of the ability to vary the 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 major valve (e.g., drifting shut of a main feedwater control valve).
- e. An indication of modeling conditions / problems that may impact the examination.
- f. Identification of significant differences between the simulator and the control room,
- g. 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 provided (voluntary by licensee).
- h. Simulator instructors manual (voluntary by licensee)
- 1. Description of the scenarios used for the training class (voluntary by licensee)
- 17. 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 material is available and that agreement has been reached with the licensee for limiting changes before the administration of the examination. All procedures and 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 ADMINISTRATION OF OPERATOR LICENSING WRITTEN EXAMINATIONS
- 1. A single room shall be provided for completing the written examination. The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsbility of the licensee.
- 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 refreshments. 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 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.
- 5. The 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 rules into the examination room, and no other equipment of reference material shall be allowed.
- 6. Only black ink or dark pencils should be used for writing answers to questions.
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