|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20210E0501999-07-22022 July 1999 Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20209H5171999-07-15015 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129 ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted ML20209F6931999-07-13013 July 1999 Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J4711999-06-30030 June 1999 Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request 1999-09-08
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20246F1311989-06-26026 June 1989 FOIA Request for Minutes of Meeting Ref in 820210 Memo from NRR Re Design & Const Assurance for Upcoming OL Cases ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML20236M6681987-06-16016 June 1987 FOIA Request for Documents Re PRA of Plant Being Prepared for NUREG-1150 & Under Auspices of Rmiep Research Program ML20215L9141987-05-0101 May 1987 Forwards Final EGG-NTA-7598, Conformance to Generic Ltr 83-28,Item 2.2.2--Vendor Interface Programs for All Other Safety-Related Components,La Salle Units 1 & 2, Informal Rept.Licensee Conforms to Generic Ltr on Subj Item ML20214K0231986-10-15015 October 1986 FOIA Request for All Documentation Re Accident Sequence Evaluation Program Repts Re Listed Facilities in Preparation for NUREG-1150 ML20214J9761986-10-15015 October 1986 FOIA Request for Containment Event Trees for Listed Facilities,Technical Repts & Memoranda Re Interpretation & Quantification & Identification of FIN Numbers,Contractors & Investigators Involved in Creation/Analysis of Event Trees ML20137A6851985-09-27027 September 1985 FOIA Request for Summaries & Evaluations of LERs from Fuel Loading to Declaration of Commercial Operation for Listed Nuclear Power Plants ML20132F5751985-08-13013 August 1985 FOIA Request for Power Plant Exam Results Summary Sheets for Listed Plants ML20134L5011985-06-19019 June 1985 FOIA Request for Operator Exam Results Summary Sheets for Listed Nuclear Plants ML20133C5961985-05-23023 May 1985 FOIA Request for Section 55.25 Exam Summary Sheets Prepared by Operator Licensing Branch for Operator Candidates & Monthly & Quarterly Repts on Senior Operator Performance on Exams ML20126E1901984-12-28028 December 1984 FOIA Request for Info Re Initial Operator Written Exam Results on Number of post-TMI-2 Plants.Info Provided in Did Pertain to Initial Exam Results.Table Listing Dates of Initial Licensing Encl ML20107K8831984-11-16016 November 1984 FOIA Request for Six Categories of Documents to Be Available in Pdr,Including Control of Heavy Loads at Indian Point Unit 2 & VEPCO Re IE Bulletin 80-11 ML20107K6231984-11-0101 November 1984 FOIA Request for Four Categories of Documents Re Results of Written Operator Exams at Listed Facilities,Including Dates of Exams & Number of Candidates Taking Exams ML20126F9821984-10-29029 October 1984 FOIA Request for Seven Specified Documents & Encls ML20125A8761984-10-25025 October 1984 FOIA Request for 1983 Annual Rept for Safety Relief Valve Challenges of Listed Plants & Annual Plant Mod,Tests & Experiments Rept for 1983 Per 10CFR50.59 ML20112H8101984-04-0505 April 1984 FOIA Request for Repts Resulting from Listed Environ Qualification of Equipment Site Audits to Be Placed in Pdr. Access to Any Repts Resulting from Audits Held Since Oct 1982 Also Requested ML20084R6521984-02-24024 February 1984 FOIA Request for Computer Printout from Sept 1980 to Present of Civil Penalty Info on 27 Listed Nuclear Facilities.Sample Format Encl ML20083N2371984-02-17017 February 1984 FOIA Request for Four Categories of Documents Re Facility ML20079M8961984-01-20020 January 1984 Forwards Personnel Resumes Inadvertently Omitted from Re Independent Auditor for Plan to Verify Const ML20079G1841984-01-13013 January 1984 Forwards Resumes for Principal Positions Noted on Organization Chart in Section IV of Ebasco 831205 Proposal Re Independent Auditor for Plan to Verify Const ML20114A3581983-12-30030 December 1983 Forwards Author to Gf Cole Re Independent Audit of Program to Verify Quality of Const & Continuation of Const Plan.Portions Deleted ML20102A1951983-11-16016 November 1983 Responds to 831101 Request for Comments Re Util Course of Action Presented at 831101 Meeting.Util Responded to All Detailed Recommendations.Many Responses Broad in Scope & Detailed Intent Cannot Be Judged ML20102A1641983-09-22022 September 1983 Forwards 830928 Presentation to Commissioners on Independent Review of Project Mgt ML20080J5571983-09-12012 September 1983 Responds to Re Independent Review of Zimmer Project Mgt,Forwarding List of Refs Utilized in Reaching Conclusions on Case Studies & Documents on Welder Performance,Attachments 1 & 2,respectively.W/o Attachment 2 ML20078B9461983-09-12012 September 1983 Submits Response to NRC 830901 Request Re Independent Review of Project Mgt Rept GA-C17173.List of Refs Utilized by Vendor for Case Studies Encl ML20073Q4361983-04-22022 April 1983 Informs That in Addition to Mgt Review of Facility,Contract Negotiations Have Been Conducted W/American Electric Power for Control Room Design Review on Donald C Cook Plant. Contract Will Not Influence Judgment on Mgt Review ML20082P2821983-03-0101 March 1983 Forwards Ad from 831017 & 24 Cincinnati Enquirer.W/O Encl ML20023D0381982-07-26026 July 1982 Repts Investigation Re Possible Flawed Equipment at Facilities,Per Eyewitness News Broadcast ML20023D0311982-07-24024 July 1982 Repts Allegation Re Zack Co Falsified Documents Concerning HVAC Activities at Facilities Per Nbc Nightly News Broadcast ML20058C7821982-06-26026 June 1982 Comments on 820625 Meeting at Site Re Motor Operator/Yoke Connection Tightness Check,Expansion Anchor Installation & Insp Values & Torque Wrench Calibr ML20072D1811982-06-26026 June 1982 Comments on Agenda Items for 820625 Site Meeting Re Technical Aspects of Torque Wrench Calibr.Motor Operator/ Yoke Connection Tightness Check,Torque Wrench Calibr Accuracy & Expansion Anchor Installation Discussed ML20063N6031982-05-11011 May 1982 Forwards Four Affidavits Re Safety Problems at Facility. Proprietary Info Deleted from Two Affidavits ML19350B8401981-03-10010 March 1981 Forwards 810305 Ltr to Emphasize Importance of Matter of Irregularities at Facility,Per 801223 Ltr.Shareholders Resolution Encl.Response Requested ML20074A0781981-02-18018 February 1981 Forwards Electrical Drafting Std EDSB-126 Revised on 791005, Pages 2-43 Through 2-48 of Electrical Installation Spec H-2173 & Pages 8.3-29,8.3-30 & 8.3-65 of Fsar,Per Request Re Tray Loading Criteria.Related Info Encl ML19273E1691980-04-23023 April 1980 Concurs W/Nrc Findings Re Fire Protection Safety Evaluation. Implementation of Program Acceptable ML19260D7071980-02-0404 February 1980 Responds to Telcon Re IE Info Notice 79-36 Concerning Use of Nupipe Computer Program in Piping Sys Analysis.Problem Discussed in Notice Does Not Apply.Supporting Documentation Encl ML20126A8131980-01-30030 January 1980 Requests Facility Exemption from Examination of Reactor Coolant Makeup Sys Components Under LOCA Conditions,As Described in GE Document 22A2756,Revision 2 ML19254F9641979-06-12012 June 1979 Forwards June 1979 Fire Protective Cable Tray Fire Test by Ms Abrams,Witnessed by Nb Cohn on 790606 ML20235E6691971-09-0707 September 1971 Forwards Adequacy of Structural Criteria for Wh Zimmer Nuclear Power Station, Final Rept ML20235D0791971-09-0707 September 1971 Forwards Adequacy of Structural Criteria for Wh Zimmer Nuclear Power Station, Final Rept ML20235E6231971-08-24024 August 1971 Forwards Revised Draft, Adequacy of Structural Criteria for Wh Zimmer Nuclear Power Station ML20235E5791971-08-12012 August 1971 Confirms That Questions Described in 710716 Special Rept Have Been Resolved Satisfactorily & Resolution of Problems Described in Detail in Final Rept on Facility ML20235E5211971-08-12012 August 1971 Forwards Revised Draft Adequacy of Structural Criteria for Plant. Two Topics Found in Rept Which Need follow-on Attention ML20235E4511971-07-16016 July 1971 Forwards Suppl to 710504 Draft Rept & Requests Listed Addl Info Re Plant.Suppl Presents More Detailed Assessment of Factors Relating to Evaluation of Adequacy of Foundations ML20235B6791971-05-0404 May 1971 Forwards Draft Adequacy of Structural Criteria for Wh Zimmer Power Station. Rept Calls Attention to Matters Which Must Be Clarified Before Finalizing Rept ML20235B6231970-06-29029 June 1970 Requests Listed Addl Info Re PSAR for Plant,Including Description of Structure Supported,Dimensions of Foundation Element,Including Length of Pile or Caissons & Depth Driven or Drilled 1989-06-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206R4561999-05-12012 May 1999 Provides Notification That Ws Jakielski,License SOP-30168-3, Is Being Reassigned & No Longer Requires Use of NRC License, IAW 10CFR50.74 ML20206K7081999-05-0707 May 1999 Forwards 10CFR50.46(a)(3) Rept Re Significant Change in Calculated Pct.Loca Analyses for Both GE Fuel & Siemens Power Corp Fuel Demonstrates Results within All of Acceptance Criteria Set Forth in 10CFR50.46 05000373/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal1999-05-0707 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal ML20206R0751999-04-30030 April 1999 Forwards License Renewal Applications & Certification of Medical Examinations for LaSalle County Station Personnel Whose Licenses Expire in Nov.Personnel Listed.Without Encls ML20206F0931999-04-30030 April 1999 Forwards LaSalle County Nuclear Power Station,Units 1 & 2 Effluent & Waste Disposal Semi-Annual Rept for 1998. LaSalle County Station Tech Specs Recently Revised to Reduce Periodicity of 10CFR50.36a ML20206K1861999-04-30030 April 1999 Informs That in Comed Submitted Annual Exposure Rept for Personnel Receiving Greater than 0 Mrem/Yr Rather than 100 Mrem/Yr.Updated Rept Limiting Data to Personnel Receiving Greater than 100 Mrem/Yr,Attached ML20206D5921999-04-28028 April 1999 Forwards Annual Environ Operating Rept for 1998 for Environ Protection Plan, for LaSalle County Station,Units 1 & 2. Rept Includes Info Required by Listed Subsections of App B to Licenses NPF-11 & NPF-18 ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205L8161999-04-0808 April 1999 Advises NRC of Util Review & Approval of Cycle 8 Reload Under Provisions of 10CFR50.59 & Transmit COLR for Upcoming Cycle Consistent with GL 88-16.Reload Licensing Analyses Performed for Cycle 8 Utilize NRC-approved Methodologies ML20205J9451999-04-0505 April 1999 Submits Petition Per 10CFR2.206 Requesting That LaSalle County Nuclear Plant Be Immediately Shut Down & OL Suspended or Modified Until Such Time That Facility Design & Licensing Bases Are Properly Updated ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207J9841999-03-0505 March 1999 Informs That Effective 990212,KC Dorwick Has Resigned & No Longer Requires Use of NRC License for LaSalle County Station ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207C7251999-03-0101 March 1999 Forwards Annual Rept for LaSalle County Station, for Period of 980101-981231.App E to Rept Provides Info on All Personnel Receiving Exposures of More than 0 Mrem/Yr Rather than 100 Mrem/Yr Requirement of TS 6.6.A.2 ML20207F9581999-03-0101 March 1999 Requests That Initial License Examination Currently Scheduled for Weeks of May 15 & 22,2000 Be Changed to Weeks of Nov 13 & 20,2000.Class Size Is Projected to Be Twelve RO & SRO Candidates ML20207C8401999-02-25025 February 1999 Forwards Rev 60 of Comed LSCS Security Plan,Iaw 10CFR50.4(b) (4).Rev Eliminates Requirement for Annual change-out of Vital & PA Keys & Locks & re-configuration of PA Fence Around North Access Facility.Rev Withheld ML20207A9361999-02-24024 February 1999 Forwards Rev 4 to Restart Plan,To Reflect Review,Oversight & Approval Process Necessary to Restart Unit 2.Review & Affirmation Process Will Focus on Station Capability to Support Safe Dual Unit Operations 1999-09-30
[Table view] |
Text
SAItoux r & LrNny ENGINEERS rou%ota av ratOta'cn sanotsv sesi 55 EAST MONROE ST AEET CHICAGO,f LLINOIS 60603 paarwan ?tLEawcNE -
r2-269-2 COO U2-269 J75a OA SLE ACORES S - S A ALU N -C H4 C A G O February 4, 1980 The Cincinnati Gas & Electric Company Wm. H. Zimmer Station - Unit 1 Commonwealth Edison Company La Salle County Station - Units 1 and 2 NUPIPE Mr. Mark Hartzman 3 f 1,0 '2 Seism 1'. Review Group l q 'g-Division of Operating Reactors Nuclear Regulatory Commission (NRC)
Washington, D. C. 20555
Dear Mr. Hart:
man:
It is my understanding that you recently contacted our Mr. C. F. Beck by telephone, and asked whether Sargent &
Lundy has used the NUPIPE Computer Program in the analysis of any piping systems on our projects. It is my understanding that Mr. Beck explained to you that we had hired Nuclear Services Corporation to perform some pipe analysis work on both the Zimmer - Unit 1 and La Salle - Units 1 and 2 generating stations. It is also my understanding that we explained to you that to the best of our understanding, all of the work on Zimmer and La Salle was on non-safety-related systems.
The reason for your asking the question was, to the best of my understanding, related to the recent problems brought forth in the NRC IE Information Notice No. 79-36, which was distributed on January 2, 1980.
I am enclosing a copy of a letter dated January 28, 1980 from Mr. R. H. Dempsey of Nuclear Services Corporation in response to a letter that I sent to Mr. Naymark of Quadrex Corporation dated January 24, 1980 on this subject.
I am also enclosing a copy of my l9tter to Mr. Naymark and the attachments which were enclosed with that letter, for your information, g ti
( \. (
&0'dh fe"4
/ 800 2210 62qg
SARGENT & LUNDY ENGINEERS CHIC AGO Mr. Mark Hartzman February 4, 1980 Nuclear Regulatory Commission Page 2 Based upon a review of the Nuclear Services Corporation letter dated January 28, 1980, Sargent & Lundy has concluded that the problem that was brought forth in NRC IE Information Notice No. 79-36 did not exist on any of the work performed by Nuclear Services Corporation in either of the Zimmer or La Salle projects.
I will assume the information provided you with this letter will satisfactorily alleviate the concerns that you raised in your conversation with Mr. Beck.
Yours very truly, G. C. Kuhlman Project Director GCK:cim In duplicate Enclosure Copies:
W. A. Chittenden (1/l)
W. G. Hegener (1/l)
R. J. Mazza (1/1)
R. F. Scheibel (1/l)
C. F. Beck (1/l)
E. B. Branch (1/1) 4oeJ
- 03
r ,
fpDUCLC7R 9 SERVIC3S CORPDRATIOD k J 1700 DELL AVINUE CAMPBELL. CALIFORNIA 95008 TELEPHONE t408) 44-2500 Twt 910-596 2438 4 DivlS1C4 08 OLIADREX CO APO A ATION January 28, 1980 Mr. G. C. Kuhlman Sargent & Lundy 55 East Monroe Street Chicago, Ill 60603
Subject:
Zimmer and LaSalle Projects - NUPIPE ELAST0J0 INT Problem
Reference:
- 1) Letter from G. C. Kuhlman (Sargent & Lundy) to S. N. Naymark (Quadrex) dated January 24, 1980
- 2) Letter from it. D. Barentsen (CDC) to C. Beck (Sargent & Lundy) dated January 16, 1980
- 3) Letter from S. fl. Naymark (Quadrex) to R. Detersen (CDC) dated December 19, 1979
Dear Mr. Kuhlman:
l t
Per your request, Reference 1, we have reviewed our records of the pipe stress analyses performed by Nuclear Services Corporation for the Dn. H. f Zimmer Station - Unit 1 and LaSalle County Station - Units 1 and 2 (P.O. #CD-3021). !
The results of this review indicate that the four conditions, which are necessary in order for the problem to arise, do not exist. Hence, the flaw described in References 1 through 3 does not exist in any of the analyses which we have performed for Sargent & Lundy.
I hope that this response satisfies your concerns in this matter. If you have any questions, please feel free to contact me.
Yours truly,
[ ,A'j
- 1oel
' 104 R.H.N(mpseympVL/
i e
Senior Vice President Operations and Projects RHD/bd
\
SAnoENT & LrNny zxoisszna ,
g roumoto et recDemica Samorat iees 55 CAST MONROE STREET CHICAGO.lLLINOIS 60603
, ug.
TELapwoNC = 312-269-2000 3t3 3e9 3758 CAeLE ADDRESS - S ARLUM* CHICAGO January 24, 1980 ;
The Cincinnati Gas & Electric Company Wm. H. Zimmer Station - Unit 1 -
Commonwealth Edison Company La Salle County Station - Units 1 and 2 NUPIPE Mr. Sherman Naymark President Quadrex Corporation 1700 Dell Avenue Campbell, California 95008
Dear Mr. Naymark:
Qurdrsx Corporation has in the past, and is presently performing piping weight, thermal and seismic analysis under contract to Sargent & Lundy on the Zimmer project for The Cincinnati Gas &
Electric Company and the La Salle project for Commonwealth Edison Company. Since this activity has, and presently is being performed by your organization, it is necessary to have you provide us an assessment of the recent occurrences that have been brought forth in various documents regarding the use of the NUPIPE computer program that it is our under-standing you have used in these activities.
Sargent & Lundy has received a letter from Control Data Corporation dated January 16, 1980, appended to which is a letter from you to Control Data Corporation dated December 19, 1979, pertaining to the fact that an NRC 10CFR21 has been filed relating to some technical problems relating to the NUPIPE computer program.
These letters are, likewise, directly cal a t'_d to a recent NRC IE Information Notice No. 79-36 that was distributed on January 2, 1980.
We, therefore, recuire that Quadrex provide Sargent & Lundy ,
with written information to verify the following:
10A1J 2nr Determine if any safety-related systems were analyzed i/ JU3 1.
by Quadrex nn the Zimmer and La Salle projects where the problem, as outlined with the NUPIPE system, could ~ -~
have caused possible flaws in the output data from the analysis. If this has occurred on any of the analysis
SARGENT & LUNDY I ENGINEERS CHICAGO
'\
Mr. Sherman Naymark January 24, 1980 Q 1adrex Corporation- Page 2 work performed on these projects, it will be necessary for Quadrex to verify to Sargent & Lundy that they have taken the appropriate corrective action on such analysis to verify acceptability or the need for any changes to the design output information that you have developed.
- 2. Determine whether any analysis was performed on any non-safety-related systems. We will require confirmar'an from you that either will state that the problem with the NUPIPE computer code does not apply to systems analyzed, or that you have taken the necessary corrective action to verify that the design must be either corrective or is acceptable.
If you have any questions on the above, please contact me.
We will be looking forward to a response to this letter at your earliest convenience.
Yours very truly, a
e ...t - m G. C. Kuhlman Project Director GCK;cim In duplicate Attachments Copies; W. A. Chittenden (1/0)
W. G. Hegener (1/1)
R. J, Mazza (1/1)
R. F, Scheibel (1/1)
C, F, Beck (1/0)
E, B. Branch (1/1)
- 9AJ 306
= # Whrv; 44 dress / Son 0 - ,-
%s. un . ssuo
~)
( I -
. CONTROL DATA CORPOR6 TION January 16, 1980 Mr. Charles Beck .
Sargent and Lundy Engineers 55 East Monroe Street Chicago, IL 60603
Dear Mr. Beck:
In accordance with the provisions of the NRC's 10CFR21, Control Data Corporation would like to inform you that an error has been detected in the current version of NUPIPE available on the CYBERNET network.
- The error affects the calculation of stresses in piping systems. Specifically, the error would affect safety related piping designed to the ANSI B31.1.0 - 1976 code and where an 8
ELBOW-ELASTOJT connection exists. A complete description of
! the problem can be found in the attached letter from the Quadrex Corporation.
As mentioned in the letter, the error should be corrected in mid-January at which time Control Data Corporation will I re-install NUPIPE on the CYBERNET network. Should you have any questions or comments concerning this matter, please contact me at 612/853-6327.
(
! Sincerely, CONTROL DATA CORPORATION I
b %%
D. Barentsen, Manager
'M.
Applications Quality Control COMSOURCE t
/k6985A-C Enclosure -
o e 1, ;07 I
eam
@CO(_n- E REx .NUE CAMP 8tLL. CAlff0RNIA 15;ca Tiltrm (4:5) 4 4 2300 TWX 11011>2413 A AQ A ATION IJ03 OILL TELIE 35 2011
/
I \;
\ s
\
N
. December 19, 1979 i
Mr. Ron Petersen Manager, '<!estern Region PS-SES ~
Control Data Cercoration -
215 Moffett Park Drive SVAFAC Sunnyvale, CA 94036
Dear Mr. Petersen:
As.of Monday, December 17, 1979, Quadrex Corcoratica has informed the Director, Office of Inspection and Enfercement, t'uclear Regulatory Comission, of a defect in a ccmcuter ccde used to calculate stresses in piping systems. This action.is in ccepliance The with the Code of defect '.culd only occur fer Federal Regulations, Title 10-Part 21.
those pcwer plants where safety-related piping wn designed to tne ANSI B31.1.0 - 1976 Code and v.here an ELEC'.l-ELAST0JT* connection exis NUPIPE is a proprietary computer program which is used to calculate stresses in piping systems to determine the location and type of oipe hanger necessary to suppcrt and restrain piping. The conditions for which NUPIPE is used include ASME service level A, B, C and D loadings, including the design base seismic event. Althcugn all piping c:ments, forces, deflecting and pipe restraint reaction loads calculated by NUPIPE are correct, the stress calculation of an ELS0W to ELAST0JT boundary element is incorrect. The NUPIPE prcgran can calculate an
' incorrect stress only when all the following conditions exist:
I o An ANSI B31.1.0 - 1967 Code version analysis is being conducted, I
. and
=
i o an. ELB0'd-ELAST0JT connection exists, and .
o an abso' lute sum (MODFLEX combination) of two load cases is being -
forced, and ,
o the elbow toisional coment axis does not align with the ELAST0JT -
local x-axis. -
. 4 n n a, z. g 8
.. t ,
- An ELAST0JT eier.ent is an infrequently used element in the NUPIPE Code used to connect two piping node points with user supplied stiffness values. y, _ .
e
f; *
- - [!%DDEH CO APO A ATION
\ i s \
. \
The only incorrect values in the flUPIPE output, due to this defect, Depending on are the stresses at the ELE 03-ELAST0JT connecting nede.
the ' exact case, the correct stress may 1;e lower or higher than the computed stress. It is unlikely, however, that a highly stressed location in which the correct stress v.ould be significantly higher than the calculated stress, would have escaped attention since the stresses at the opposite (non-ELAST0JT) end of the elbcw are computed correctly
- by NUPIPE.
You should carefully review the NUPIPE has been issued since mid-1972.
work perfcmed that has included fiUPIPE analysis. The review should first determine if the four conditions described above do actually exist. If all fcur conditions do exist, the stresses at the ELEC'J- Cepending en the
- ELAST0JT connecting node cust be hand recalculated.
magnitude between the correct stress and the previously calculated
^
stress, and the reanalysis of piping system:
o The differences cay be negligible and no further action is requii ed, o Additional pipe hangers may be required at piping in the vicinity of the ELS0W-ELAST0JT boundary.
o The present pipe hangers in the vicinity of the ELE 02-ELAST0]T boundary may require codification to lcwer the pipe stresses so that Code allowables are not exceeded.
o For power plants that have been operating and the difference in the correct and calculated values are large, the effect en the design fatigue life will have to be considered.
The NUPIPE program is presently being mcdified to eliminate the defect and will be reissued as '!ersion 1.4 in mid-January 1950.
9 Quadrcx Corporation will continue to ;c unicate to you any events which k c a direct bearing on the defect i;UPIPE or the ramifications of that u fece.
19/J 309 .
Very truly your
' r - M _ ,W ,
Mcan itay= ark, Presic nt
- , Quadrex Corporation y ., SES TCSD n
DEB 2 0 W83 ~
WESTERM CEE