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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 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 ML20059N6721990-10-0909 October 1990 Responds to Util 900702 Request for Authorization to Use ASME Boiler & Pressure Vessel Code Case N-395.Request Acceptable 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 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 ML20059H0921990-08-23023 August 1990 Forwards Insp Repts 50-348/90-20 & 50-364/90-20 on 900711-0810.No Violations or Deviations Noted 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 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 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 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) 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 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 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 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 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 ML20245G3171989-06-13013 June 1989 Requests Completion of Radiochemical Analyses of Liquid Samples Spiked W/Radionuclide within 60 Days of Receipt of Samples 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 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 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
[Table view] |
See also: IR 05000348/1987011
Text
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NUCLEAR REGULATORY COMMISSION
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VVASHINGTON, D. C. 205S5
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July 27, 1987 )
Docket Nos.: 50-348 and 50-364
Alabama Power Company '
ATTN: Mr. R. P. Mcdonald
Senior Vice President !
Post Office Box 2641
Birmingham, Alabama _35291-0400
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Gentlemen:
'
This letter transmits the report of the inspection conducted at the Joseph M.
Farley Nuclear Plant (FNP), Units 1 & 2, by Messrs. R. P. McIntyre, J. B. Jacobson,
P. J. Prescott, J. J. Petrosino, of the Vendor Inspection Branch and D. R. i
Lasher of the Instrumentation and Controls System Branch on May 11-22 and
June 1-5, 1987. The inspection was related to activities authorized by NRC.
License Nos. NPF-2 and NPF-8. Our findings were discussed with Mr. J. D.
Woodafd and other members of your staff at the conclusion of the inspection.
The purpose of-this inspection was to review the implementation of your procure-
ment and vendor interface programs at FNP by examining the respcnse of Alabama 1
Power Company.to specific vendor-related technical issues of safety significance.
The results of the inspection show considerable weakness in the areas of
procurement and vendor interface. The Alabama Power Company vendor interface
program appears to lack the rigor and formality necessary to achieve its
int 9nt. Several examples are cited in this report where, although Alabama
Power Company had been made aware of a problem by a vendor, complete, effective'
and timely corrective action was not taken. In addition, significant deficiencies ,
I
were found in the procurement of both safety-related and comercial grade
components, resulting in hardware being installed in safety-related ap)11 cations i
which may not have been capable of aerforming its intended function. T1ese
findings, when considered along wit 1 the improper installation of the service
f water battery rack and the failure to report to the NRC the inoperability of 2
control room fire dampers and 15 cracked battery cells in both trains of the
auxiliary building batteries indicate a leck of systematic attention to detail. i
While no instances were found where Alabama Power Company failed to receive
information as a result of its lack of a formal arocess to periodically contact
key vendors, a number of cases were identified w1ere the information had not
been obtained from the vendor or VETIP but was obtained fortuitously from other
sources.
The findings discussed above have been classified as four Potential Enforcement
Findings (50-348 and 364/87-11-01 to 04, enclosed) and will be referred to
the hRC Region II office for appropriate action. ;
B707300390 B70727
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Alabama Power Company -2- July 27, 1987
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Should you have any questions concerning this inspection, we will be pleased
to discuss them with you. i
Sincerely,
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Division of Reac rojects - I/II
Office of fluclear Reactor Regulation
Enclosures:
1. Potential Enforcement Findings
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2. Report No. 50-348/87-11 and 50-364/87-11
cc: see page 3
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' Alabama Power Company -3- July 27, 1987
cc:
Mr. W. O. Whitt D. Biard MacGuineas, Esquire
Executive Vice President Volpe, Boskey and Lyons
Alabama Power Company 918 16th Street, N.W.
Post Office Box 2641 Washington, D.C. 20006 ;
Birmingham, Alabama 35291-0400 '
Charles R. Lowman
~Mr. Louis B. Long, General Manager Alabama Electric Corporation
Southern Company Services, Inc. Post Office Box 550
Post Office Box 2625 Andalusia, Alabama 36420
Birmingham, Alabama 35202
. Chairman Regional Administrator, Region II ,
. Houston County Commission U.S. Nuclear Regulatory Commission l
Dothan, Alabama 36301 101 Marietta Street, Suite 2900
4
Atlanta, Georgia 30303
Ernest L. Blake, Jr., Esquire
Shaw, Pittman, Potts and Trowbridge Claude Earl Fox, M.D.
2300 N Street, N.W. State Health Officer
Washington, D.C. 20037 State Department of Public Health
State Office Building
. Montgomery, Alabama 36130
Robert A. Duettner, Esquire
Balch, Bingham, Baker, Hawthorne,
.
Mr. J. D. Woodard
Williams and Ward General Manager - Nuclear Plant
Post Office Box 306 Post Office Box 470
Birmingham, Alabama 35201 Ashford, Alabama 36312
s
Resident Inspector
U.S. Nuclear Regulatory Commission l
Post Office Box 24 - Route 2
Columbia, Alabama 36319
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Alabama Power Company -
4- July 27, 1987-
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DISTRIBUTION:
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PJPrescott
JBJacobson
JJPetrosino
DRLasher i
PFarron, Consultant !
WBradford, Resident Inspector
HDance, RII
LReyes, RII
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' Alabama Power Company -4- July 27, 1987
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DISTRIBUTION:
Docket Files (50-348/364)
NRC PDR
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VIB Reading.
DRIS Reading :
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JGPartlow
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PFarron, Consultant ;
WBradford, Resident Inspector ;
HDance, RII ;
LReyes, RII '
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POTENTIAL ENFORCEMENT FINDINGS
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Alabama Power Company Docket Nos. 50-348, 50-364 l
Joseph M. Farley Nuclear
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License Nos. NPF-2, NPF-8 !
Plant Units 1 and 2
As a result of the inspection conducted on May 11-22 and June 1-5, 1987, the
following Potential Enforcement-Findings were identified.
1.- The NRC inspectors observed-that both train B 125-v Service Water (SW)
battery racks were improperly installed and mounted, therefore creating
an unanalyzed condition concerning seismic qualification. Specifically,
the concrete anchor bolt nuts on all train B battery rack anchors were
backed off and used as leveling nuts for the rack thus providing no preload
on the concrete anchors. The battery racks were improperly installed in
the SW train B battery room approximately 1 year prior to the time of this
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inspection and remained in this unanalyzed condition until it was identi-
fied by the NRC inspector. Further, the inspectors identified six instances
where the licensee had failed to take adequate corrective action: (1) a
Henry Pratt, May 1985, 10 CFR 21 notification detailing problems with
Pratt valves using Limitorque operators was not correctly or completely
dispositioned; (2) an Anchor Darling, August 1r , 10 CFR Part 21 notifica-
tion concerning failures with tilting disc cher valve hinge pin bushings
was not completely dispositioned in that only u.eck valves in the auxiliary
feedwater system were inspected, (3) conditions noted in NRC Information
Notice 84-83, which concerned cracks on GNB battery cells caused by the
use of hydrocarbon based solvents for cleaning purposes were not completely
corrected, since only two of three electrical maintenance procedures were
revised to address the problem, (4) the review of a November 1984 Ruskin
10 CFR 21 letter concerning the failure of fire dampers to completely
close during flow conditions showed that the licensee identified this
problem in three areas, corrected it in two areas but did not correct two
dampers in the control room area, and (5) a Colt Service Information
Letter (SIL) A-2 dated February 1985 was evaluated by the licensee, but
' not all the corrective actions determined to be appropriate by Alabama .
Power's engineering review were implemented. (50-348,364/87-11-01) -
2. The licensee installed nine circuit breakers with questionable seismic !
qualification and voltage ratings into safety-related motor control centers
at both FNP Units 1 and 2. The circuit breakers, that were affixed with
an Underwriters Laboratories, Incorporated, rating of 480 V by the original
manufacturer, were sold by Satin American Corporation as seismically
qualified safety-related circuit breakers acceptable for installation
into FNP's 600-V motor control centers. The vendor provided no basis for
seismic or 600-V qualification. No testing or analysis that would qualify
the use of these breakers as installed has ocen done either by the licensee
or the vendor. (50-348, 364/87-11-02)
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3. The licensee installed numerous commercial grade parts at FNP Units 1 and 2
~without adequately evaluating their suitability for use in safety-related
applications. Specifically- ~
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'(1}}: Commercial.gradecircuitbreakers'were._installedtinto' safety-related
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' motor contro1~ centers 1U.and 2U..
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. (2)! A'c6mmercial grade Hamco. limit switch was installed"as a replacement
W for safety-related switch for the accumulator: tank isolation valve.-
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'(3) A' commercial grade; torque switch was installed into a safety-related
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a Limitorque motor. actuator.' Limitorque has _ stated that although the -
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isafety-related and commercial grado' torque switches for outside
.
o Containment are the same, the switches'that were ordered'as safety
related receive additional-QA checks at Limitorque not performed on
the' commercial-grade switches. No additional QA checks were made at
FNP:on this switch.
,
(4)- Commercial grade hinge pin bushings were installed'in safety-related
, ' Anchor / Darling tilting disc check valves in the auxiliary feedwater
g system.-
" '
(5) A commercial grade'Agastat timing relay-(ATR).was installed'as a
replacement in safety-related panel #Q2R16B007_-B, 600 volt. load
-distribution panel. Additionally, commercial grade:ATRs were'found
'
in'other safety-related_ electrical _ enclosures including two ATRstin
diesel generator load. sequencer panel #Q2R43E5018-B. and two ATRs'in
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diesel generator relay terminal box ll0lR43E506-B.-
-(50-348, 364/87-11-03) _
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4. - The. licensee neither restored two non-functional safety-related control
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' room fire ventilation dampers within the 7 day Technical Specification
req'irement
u nor. submitted its special report to the NRC, as required.
.within 30. days. and:the licensee failed to report to the NRC a degraded
safety-related.125-V auxiliary building battery condition in both. trains
A and B of Unit 2 that was discovered in April of 1986 by FNP personnel.
,
T 'The battery degradation involved 15 cracked battery cell cases, 3 ini l
, battery room'2B and 12 in battery room 2A. Corrective. action was performed.
4
(50-348,364/87-11-04) '
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