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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 ML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed 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 ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method 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 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 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 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 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 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 ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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 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 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 ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year 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 ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During 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 ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal 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 ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) 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 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 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 ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 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 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 ML20058G8921990-11-0707 November 1990 Forwards Insp Repts 50-155/90-20 & 50-255/90-20 on 900925-28 & 1015-19.Violations Noted 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 ML20058G2461990-11-0202 November 1990 Forwards Safety Insp Rept 50-155/90-17 on 900904-1015 & Notice of Violation ML20058F7331990-10-31031 October 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058A7671990-10-22022 October 1990 Advises That Review of 900816 Response to NRC Bulletin 90-001 Re Loss of Fill Oil in Rosemount Transmitter Ongoing 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 ML20062C6601990-10-0909 October 1990 Ack Receipt of 900913 Response to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19 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 ML20059N0081990-09-28028 September 1990 Forwards Insp Rept 50-155/90-10 on 900723-27 & 0806-10 & Notice of Violation ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059N3481990-09-24024 September 1990 Forwards Insp Repts 50-348/90-24 & 50-364/90-24 on 900827-31.No Violations or Deviations Noted ML20059L4771990-09-18018 September 1990 Forwards Safety Insp Rept 50-155/90-13 on 900724-0903. Noncited Violation Noted ML20059J3091990-09-10010 September 1990 Forwards Exemption from 10CFR55.45(b)(2)(ii) Re Use of Simulation Facility,Per 900404 Request.Util Request to Delay Submittal of Description of Performance Tests & Results Until 910526 Granted ML20059F2531990-08-31031 August 1990 Forwards Safety Evaluation Supporting Util 891229 Request to Dispose of Dredged Discharge Canal Sediment from Facility ML20059K1311990-08-28028 August 1990 Confirms Mgt Meeting on 900913 to Discuss Timeliness of Activation of Emergency Response Facilities ML20059C6111990-08-27027 August 1990 Forwards Safety Insp Rept 50-155/90-15 on 900814-16.No Violations Noted 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 ML20059B7771990-08-22022 August 1990 Advises That Util Commitment to Install Two New Recorders That Provide Containment Temp Indication on Front Panel During 1990 Refueling Outage,Acceptable 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 ML20056B5191990-08-17017 August 1990 Forwards Final SALP Rept 50-155/90-01 & Revised Pages to SALP Rept.Overall Performance Did Not Decline,Per 900716 Meeting.Nrc Overstated Concern W/Radiological Controls Functional Area in Initial Rept & Cover Ltr ML20059A7571990-08-16016 August 1990 Advises That Response to Bulletin 90-001, Transmitters Mfg by Rosemount, Complete,Per ML20059A1741990-08-16016 August 1990 Informs That NRC NDE Mobile Lab Will Conduct Independent NDE Exams at Plant on 900924-1005.Selected Sys for Exam Listed on Encl ML20059A1661990-08-16016 August 1990 Forwards Safety Insp Rept 50-155/90-14 on 900730-0803.No Violations Noted ML20059A3721990-08-14014 August 1990 Ack Receipt of Informing NRC of Change in Completion Date Re on-the-job Training Procedure,Per LER 90-002 ML20058N2211990-08-0707 August 1990 Forwards Safety Insp Rept 50-155/90-12 on 900612-0723.No Violations Noted ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date 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) ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20058P8661990-07-31031 July 1990 Forwards Insp Repts 50-348/90-21 & 50-364/90-21 on 900709-13.No Violations or Deviations Noted ML20055G7301990-07-20020 July 1990 Requests Util Provide Ref Matls Listed in Encl for Requalification Program Evaluation on 901018 & Wk of 901105 ML20055G2881990-07-16016 July 1990 Advises of fitness-for-duty Insp Scheduled for Wk of 900925- 28 at Plant.Written Policies & Procedures Will Be Reviewed as Part of Insp Process 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 ML20055G5051990-07-11011 July 1990 Advises That 900511 Rev 95 to Chapters 2,5,6,7,8 & Apps D, M & P for Plant Emergency Plan Consistent w/10CFR50.54(q) & Acceptable.Position of on-call Technical Adviser Should Be Inserted in Table 1 of Chapter 5 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 ML20055F1661990-07-0606 July 1990 Forwards Initial SALP Rept 50-155/90-01 for Jan 1989 - Apr 1990,prior to 900716 Scheduled Meeting.Two Areas of Improvement & No Areas of Decline Identified Since Last SALP Rept 1990-09-28
[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 ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use 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 ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted 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 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 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 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 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 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 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 ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp 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 ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) 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 ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr 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 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 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 ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created 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 ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld 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 ML20206E3721999-04-29029 April 1999 Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML20206R2031999-04-29029 April 1999 Forwards Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted ML20206B7381999-04-26026 April 1999 Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined 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 ML20205E3471999-03-29029 March 1999 Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to ML20204F4611999-03-19019 March 1999 Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] |
See also: IR 05000155/1986013
Text
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September 22, 1988 ;
Docket No. 50-155
License No. DPR-06
EA 87-80
Consumers Power Company
ATTN: David P. Hoffman
Vice President
Nuclear Operations
212 West Michigan Avenue
Jackson, Michigan 49201
Gentlemen:
SUBJECT: NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY
(NRC INSPECTION REPORT N0. 50-165/86013(DRS))
This r:;fers to the NRC inspection conducted on September 15-19, 1986, at the
Big Rock Point Nuclear Plant of activities authorized by NRC License No. DPR-06.
The inspection was conducted by a special environmental qualification (EQ)
inspection team to assess the program implemented at the Big Rock Point Nuclear
Plant to meet the EQ requirements of 10 CFR 50.49. As a r7sult of the
September 15-19, 1986 inspection, a violation of NRC regulatory requirements
was identified. NRC concerns relative to this violation were discussed
during Enforcement Conferences that were held on July 7, 1987 and July 21,
1988.
The violation described in the ent.losed Notice of Violation and Proposed
Imposition of Civil Penalty (Notice) involved examples of failures to comply
with the requirements of 10 CFR 50.49. The first example involved a Limitorque
Motor Actuator that was removed from service after 13 years of operation and
was then subjected to a loss of coolant accident (LOCA) test on April 23, 1975.
The actuator was reinstalled and returned to service. It continued to be used
following the November 30, 1985 deadline for environmental qualification of
equipment important to safety without being qual 1fied by testing and/or analysis
to evaluate aging as well as potential degradation due to the LOCA test. The
second example involved the use of environmentally unqualified butyl rubber
and polyethylene insulated cables in Class 1E systems including the Main
Steam Isolation Valve, the Core Spray System, the Containment Spray System,
and the Reactor Depressurization System.
The NRC staff believes that Consumers Power Company (CPCo) clearly should have
known about the EQ deficiencies described above. For Limitorque Actuator
MO-7068, it should have been clear that the actuator was unqualified because
the maintenance documentation provided by Limitorque following the 1975 LOCA
testing of the valve actuator did not provide evidence that any refurbishment
of the degradable materials had been accomplished or any evidence that such
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- Consumers Power Comany 2 September 22, 1988
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- refurbishment had been considered and found unnecessary. At the Enforcement l
Conferences, CPCo took the position that analysis showed qualification of the -
! actuator for 40 years but the NRC staff has concluded that the data used to
}
support that conclusion did not consider the case in which an actuator had
already undergone a once-in-a-lifetime LOCA test and CPCo should have
recognized that fact.
. With regard to the unqualified cables inside the containment, CPCo was informed
l in an NRC Inspection Report dated August 8, 1984 that the NRC staff had concerns
l about the qualification of the cables and that report stated that those concerns !
could be addressed by testing the installed cable or by showing qualification
'
through testing already completed. CPCo decided to show qualification of the j
cables by demonstrating similarity of the installed cables to cables already i
i tested. It is the NRC staff's position that CPCo clearly should have known that ;
the similarity analysis that was performed by CPCo for the polyethylene !
) insulated cable as well as the one it performed for the butyl rubber insulated
I cable were deficient. In the case of the polyethylene insulated cable, the !
insulation formulation (which includes material, manufacturing process and i
j
fabrication) was not shown to be similar to that of the tested cable. In the i
i case of the butyl rubber insulated cable, the insulation formulation differed !
1
from that of the cable cited in the test report relied on by CPCo and the test !
{ conditions used in the cited test report were unstated and therefore could not !
j be shown to be equivalent to the conditions that the installed cable would be
subjected to in a LOCA. [
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To emphasize the importance of (1) management attention to, and control of, the l
3 EQ program, and (2) aggressive management action to ensure that problems are !
I promptly identified and corrected, I have been authorized, after consultation 1
l with the Director, Office of Enforcement and the Deputy Executive Director for
Regional Operations, tc issue the Notice of Violation and Proposed Imposition {
,
, of Civil Penalty (Enclosure 1) in the amount of One Hundred and Eighty-Seven l
J Thousand Five Hundred Dollars ($187,500) for the violation described in the [
]
enclosed Notice. In accordance with the "Modified Enforcement Policy Relating t
i to 10 CFR 50.49," contained in Generic Letter 88-07 (Enclosure 2), the violation !
i described in the enclosed Notice has been determined to be moderate and to l
have affected some systems and components, and therefore is considered to be !
an EQ Category B violation. The base value of a Civil Penalty for an EQ :
Category B violation is $150,000.
!
l
j In determining the civil penalty amount, the NRC considered the four factors j
set forth in the "Modified Enforcement Policy Relating to 10 CFR 50.49," for ;
! escalation and mitigation of the base civil penalty amount. These factors
i consist of (1) identification and prompt reporting of the EQ deficiencies l
3 (150%); (2) best efforts to complete EQ within the deadline (150%); j
! (3) corrective actions to result in full compliance (150%), and (4) duration l
l of a violation which is significantly below 100 days (-50%), i
l
With rr N ' to the first factor, no escalation or mitigation is warranted f
since a. g W ral issues regarding qualification of cable were clearly !
recogi i by 'he NRC staff and CPCo well prior to the November 30, 1985
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Consumers Power Company 3 September 22, 1988
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deadline and a violation occurred in this case because CPCo failed to take !
adaquate corrective action. With respect to the second factor, 25 percent !
y
mitigation is warranted because best efforts were applied by the licensee to i
- complete EQ within the deadline. However, full mitigation for those efforts is
l not appropriate because, notwithstanding the NRC staff's continued concerns ;
j with an issue as fundamental as cable qualification, CPCo did not satisfactorily l
j resolve the issue prior to the deadline. With respect to the third factor, j
! 50 percent escalation is war.' anted since the licensee's efforts to make an !
operability or qualification determination were not timely and the quality of i
i the supporting analyses were unacceptable. With respect to the fourth factor, (
j mitigation is inappropriate since the EQ violation existed in excess of 100 days. ;
After reviewing these factors, the base civil penalty has been increased by ,
' 25 percent. ;
You are required to respond to this letter and should follow the instructions L
'
. specified in the enclosed Notice when preparing your response. In your
i response, you should document the specific actions taken and any additional
l actions you plan to prevent recurrence. After reviewing your response to this
<
Notice, including your proposed corrective actions and the results of future !
inspections, the NRC will determine whether further NRC enforcement action is >
- necessary to ensure compliance with NRC regulatory requirements.
1
j In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, '
i Title 10, Code of Federal Regulations, a copy of this letter and its enclosures l
) will be placed in the NRC Public Document Room. l
The responses directed by this letter and the enclosed Notice are not subject
j to the clearance procedures of the Office of Management and Budget as required
j by the Paper.<ork Reduction Act of 1980, PL 96-511. I
I
Sincerely, g
OricinM ei- .d t'/ !
A Bert Davis !
! A. Bert Davis '
j Regional Administrator
J
"
Enclosures: !
1. Notice of Violation and Proposed i
1 Imposition of Civil Penalty I
l 2. Generic Letter 88-07 l
I 3. Inspection Report
l
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No. 50-155/86013(DRS) -
1 l
! See Attached Distribution !
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' Consumers Power Company 4 September 22, 1988
Distribution
cc w/ enclosures:
Mr. Kenneth W. Berry, Director
Nuclear Licensing
Thomas W. E1 ward, Plant
Manager '
Licensing Fee Management Branch
Resident Inspector, RIII
Ronald Callen, Michigan
Public Service Commission
Michigan Department of
Public Health
PDR
LPOR
SECY
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CA
OGPA
g 0CO/DCB (RIOS) .
J. M. Taylor, OEDRO l
J. Lieberman, OE
L. Chandler, OGC
T. Murley, NRR
J. Luehman, OE
RAO: RIII
PAO:RIII
SLO:RIII
M. Stahulak, RIII
Enforcement Coordinators,
RI, RII, RIV, and RV
E. Jordan AE00
B. Hayes 01
S. Connelly, OIA
OE File
EA File
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