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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 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 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 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 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 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 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 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 ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted 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 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 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 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 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 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 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 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: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 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 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 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 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 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 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] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML19325E9801989-11-0101 November 1989 Requests That Author Name Be Placed on Distribution List Re Schedule of Hearing in Alchemie Case.W/Certificate of Svc. Served on 891101 ML20247F8061989-07-0505 July 1989 FOIA Request for Documentation Re Incidents of Drug &/Or Alcohol Abuse During Past Five Yrs Amoung Employees or Contractors ML20247E6951989-06-27027 June 1989 Advises That Newly Formed Environ Conservation Organization Intends to Oppose Any Util Actions That Might Impact Negatively on Future Operability of Facility ML20247H3631989-06-26026 June 1989 Advises of Formation of Resources Conservation Organization. New Group Intends to Oppose Any Util Actions That Might Impact Negatively on Future Facility Operability.Ad Rossin Will Serve as Organization Coordinator ML20245B3981989-05-0808 May 1989 Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant ML20245B4081989-03-10010 March 1989 Requests Response to 881014 & 890119 & 23 Ltrs Re Technical & Safety Concerns at Plant ML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20245B4091989-01-23023 January 1989 Refers to Re Corrosion Inhibitors in Closed Water Sys at Plant.Last Sentence on First Page of Ltr Should Be Changed to Read One Example Is Loss of Air Cooling to Shutdown Board Rooms at Sequoyah ML20245B4101989-01-19019 January 1989 Requests That Jg Partlow Pursue Completion of Engineering Assignment of ED Buggs at Plant Concerning Corrosion Inhibitors for Closed Water Sys.Draft Engineering Rept Recommending Corrosion Inhibitors for Closed Water Sys Encl ML20206D8951988-10-15015 October 1988 Expresses Opinion That Plants Should Remain Closed Until Converted to Alternative Fuel Source ML20245B4121988-10-14014 October 1988 Informs of Several Technical Concerns Expressed While at Util & Requests That Jg Partlow Pursue Resolution of Listed Concerns ML20206D9711988-09-0808 September 1988 Forwards Ltrs Exchanged Between NRC & Author in 1984 Re Problems in Commercial Nuclear Power Field & Change in Federal Regulations to Allow Senior Reactor Operator to Deviate from Tech Specs in Emergency ML20206D9451988-08-12012 August 1988 Annotated Ltr Expressing Appreciation for Reply to & Assurance in Response to Concerns Pertaining to Operation of Ref Plants ML20245D6611988-08-0808 August 1988 Submits Listed Comments in Response to Re Safety Practice to Schedule Nuclear Plant Operating & Maint Personnel for 16 H Shifts &/Or Excessive Overtime ML20206E0281988-07-0707 July 1988 Advises That Nuclear Industry Overlooked Most Important Lesson Resulting from TMI Accident,To Wit,That Station Operator/Mgt Official Stationed in Control Room Would Have Prevented Accident ML20151X9371988-07-0101 July 1988 FOIA Request for Le Phillips 880407 Memo to Ma Ring ML20150A7961988-06-30030 June 1988 Comments on Util 880616 Request to Suspend Antitrust License Condition.Economic Advantages for Util Owning Nuclear Power Plants Have Failed to Materialize ML20155B6651988-06-16016 June 1988 FOIA Request for plant-specific Documents Re Fire Protection Requirements,Insp repts,hardware-specific Deficiencies & NRC Communications W/Util ML20206E0361988-04-29029 April 1988 Opines That 10CFR50.54(x) & (Y) Superfluous & Dangerous.Nrc Should Instruct Operators Not to Depart from Tech Specs in Emergency.Author Resume Detailing Experience in Commercial Nuclear Power Field Encl ML20155A7431988-02-24024 February 1988 Discusses Safety Problems at Comm Ed Nuclear Power Plants Re Risking Fuel Meltdown by Turning Off Safety Sys as Directed by Util Policy in Emergency If Core Cooling Is Adequate. Vice President Instruction Encl ML20148G9001988-02-0101 February 1988 FOIA Request for Documents Re 10CFR50,App R Insps & Enforcements ML20206E0431988-01-29029 January 1988 Expresses Concern Re Two Hazardous Practices at Ref Plants, Including Risking Meltdown by Authorizing Operators to Turn Off Nuclear Plant Safety Sys During Emergency ML20149G1051987-12-18018 December 1987 Opposes NRC Reduction at TMI-2.Reducing Staff Prior to Completion of Core Removal Inappropriate & Misguided Move. Recent Shutdown of Oyster Creek for Incident Re Destruction of Data Decreases Util Standing W/Local Residents ML17303A6161987-09-30030 September 1987 Forwards Scenario Review for Rancho Seco Emergency Preparedness Exercise,871104. Incomplete Scenario Provided for Review.Plant data,in-plant Chemistry & Radiological Data & Controller Info to Support Fire Drill Missing Elements ML20235T7341987-09-0101 September 1987 Requests That EIS Documents Re Meltdown Prepared by Impartial Sources Be Made Available to Public.Observation of Plant Life Indicates Level of Contamination of General Environ Causing Widespread Severe Damage ML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20238E0261987-07-15015 July 1987 Responds to Recipient 870528 Response to Bg Strout Re Maine Yankee & Pilgrim.Author Distressed by NRC Answers & Requests Addl Response to Listed Questions ML20235L7061987-07-0808 July 1987 Opposes Util Application for Amends to Licenses,Allowing New Ownership & Financing Arrangement.Nshc Should Not Be Made W/O Public Hearings on Serious Financial Qualifications Questions ML20235K0421987-07-0202 July 1987 FOIA Request for List of All Licensed Reactor Operators & Senior Reactor Operators for Facilities ML20235F7451987-06-30030 June 1987 FOIA Request for Documents Re Safeteam Programs Being Used at Listed Facilities ML20215L4871987-06-23023 June 1987 Urges NRC Not to Approve Comm Ed Request for Amend of Any OL Re Braidwood 1 & 2 & Not to Determine No Significant Hazard Exists W/O First Holding Adjudicatory Hearings on Serious Financial Qualifications Issues ML20215L5051987-06-23023 June 1987 Provides Brief Updated Rept on Status of Comm Ed Proposal Before State of Il Commerce Commission to Restructure Ownership & Other Financial Arrangements Re Facilities.Urges NRC Not to Make Finding Prior to Hearing ML20215D6371987-06-12012 June 1987 Forwards Reply to Responses from NRC & B&W Owners Group. NRC Response Evidences No Independent Review of B&W Claims. Commission Urged to Take Personal Jurisdiction of Petition to Ensure That Latest Commitment Not Frustrated ML20236H1481987-05-30030 May 1987 Discusses Varga Reply to 870428 Mailgram Re Proof That LOCA Could Not Occur in Reactor Core at Plants.Evidence in Files of Repeated AEC & NRC Repression & Ignorance of Legitimate ACRS Concerns Cited.Congressional Hearings Requested ML20215K8391987-04-22022 April 1987 Opposes Licensing of Facilities for All the Same Old Reasons ML20214E2281987-04-16016 April 1987 FOIA Request for PRAs for Listed Plants Be Placed in PDR ML20214L0951987-03-13013 March 1987 Comments on Proposed Rule 10CFR50 Re Mod of Safety Rules to Enable Facilities to Startup Operation.Opposes Rule Due to Result of NRC Abdicating Responsibility as Protector of Safety of Populations Exposed to Radiation During Accidents ML20236D9381987-03-0404 March 1987 Partially Withheld Ltr Discussing Nuclear Power Industry Problems as Encountered During 6 Yrs of Employment at Limerick.Shoreham, & Hope Creek.Demotions & Terminations for Reporting Safety Concerns Described ML20215K8531987-02-24024 February 1987 Advises That Nassau County Board of Cooperative Educational Svcs Has Not Entered Into Any Agreement W/Lilco to Have Salisbury Campus Used for Relocation Facility in Event of Radiological Emergency ML20207T2381987-02-18018 February 1987 FOIA Request for Rept on Odds of Large Radioactive Release at Us Commercial Nuclear Reactors,Including Surry,Peach Bottom,Sequoyah,Grand Gulf & Zion ML20236D1281987-02-15015 February 1987 Forwards Preliminary Investigation of Worker Allegations About Safety of Plant Conducted by Gap in 1986.Investigation Revealed Enough Info to Raise Serious Questions Re Const Quality.Petition Per 2.206 Forthcoming ML20211B6601987-01-0505 January 1987 FOIA Request for Documents Re Allegations,Investigations, Fines,Convictions & Other Dispositions of Cases in Which Operators of Listed Facilities Charged W/Violating Federal whistle-blowing Statutes ML20207Q0971986-12-29029 December 1986 FOIA Request for Documents Re Util Proposed Reduction of EPZ at Seabrook,Changes to Containment at GE Plants, Including Pilgrim & Vermont Yankee & Insp of Pilgrim 1 Since Shutdown in Apr ML20215K9121986-11-26026 November 1986 Requests Opinion of Fairness of Shoreham Proceeding ML20212D7651986-11-12012 November 1986 Expresses Safety Concerns Re Containment Pressure Boundary, Based on 850916 Sser ML20215K9561986-09-22022 September 1986 Supports Licensing of Facility Due to Close NRC Scrutiny of Const & Operation ML20213C7931986-09-12012 September 1986 FOIA Request for Documents Re Western Piping & Engineering Pipe Clamps Furnished to Perry 1 & 2 & Van Meter 820607, 0721,0818 & 840125 Complaints to NRC Re Design Deficiencies at River Bend ML20211C5631986-09-12012 September 1986 FOIA Request for Three Classes of Documents Re Use of Western Piping & Engineering Clamps at Perry Nuclear Power Plant & All Complaints/Correspondence Involving Deficiency Complaint at River Bend Plant ML20215N9491986-09-11011 September 1986 FOIA Request for Ltrs,Depositions & Other Communications in Connection W/Nine Mile Point & Shoreham Nuclear Power Stations ML20215L4061986-09-11011 September 1986 FOIA Request for All Ltrs,Depositions & Other Communications Re Facilities 1989-07-05
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Acoress Reply to Post Othce Box 767 /T- ' ' *
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CNeago. Ilknois 60690 a
August 13, 1982 C.F. Braun & Co.
Power Division 1000 S. Fremont Avenue Alhambra, California 91802 Attn: Mr. George Boddeker
Subject:
Independent HVAC Review - LaSalle County Station
Dear Mr. Boddeker:
The United States Nuclear Regulatory Commission has requested that we have an independent HVAC review performed at our LaSalle County Station. Attachment A contains the special technical requirements by which the review must be performed. In general, however, it is intended tnat you verify that the HVAC installati.on is in accordance with the design.
You should provide us with a documented write-up outlining the plan by wnich you would perform this review. This plan should discuss your organization, qualifications, resumes of personnel, and any procedures and plans you would intend to use. I call your attention to the section of. Attachment A concerning the independence of review. Your eview should be performed with the guidance outlined therein, but you should feel free to suggest substitute forms of a similar. nature that C.F. Braun may have previously used.
LaSalle County Station Unit #1 is currently scheduled to complete 50% power. testing ab.out September 15, 1982. This schedule may l
, enange ba. sed on testing progress; however, we request you to supply L adequate support to this effort to provide a report by September 15 1982 I
tnat can be forwarded to the.NRC. All submittals would be provided to -
( Commonwea'lth Edison Company for direct forwarding to the NRC.
N 8.8. Stephenson ey hk 9//g,
, T.E. Watts 8.R. Shelton l B. Lee, Jr. LaSalle County Station C. Reed -
Project Engineering Manager L.0. DelGeorge C.W. Scnroeder R.E. VanDerway J.A. Harper R.J. Mazza - S&L D.C. Haan - S&L A.M. DeFusco - C.F. Braun A.J. Kempiak - C.F. Braun
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Attachment A N
LASALLE COUNTY STATION '
INDEPENDENT HVAC SYSTEMS REVIEW I. INTRODUCTION At the request of the Nuclear Regulatory Commission (NRC) staff, Commonwealth Edison Company (CECO) is to obtain the services of an outside consultant to conduct an independent review of the safety-related and seismically supported Heating, Ventilating and Air Conditioning (HVAC) systems at LaSalle. The consultant will verify that the HVAC installation is in accordance'with the design
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as described in Mr. C. Reed's August 4, 1982 letter to Mr. H.
Denton (Exhibit 1).
II'. SCOPE OF WORK ,
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Tne independent reviewer will review all seven LaSalle ,
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l safety-related HVAC systems.
- Control Room HVAC System (System Identification Code VC)
- Auxiliary Electric Equipment Room HVAC System (VE)
~ - Diesel-Generator Room Ventilation System (VD) .
- CSCS Equipment Area Cooling System (YY)
- Switch Gear Rooms Ventilation Systems (VX), except for the recirculation duct in the Auxiliary Building HVAC Equipment Room.
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Attachment A -
Page 2 j- 11. SCOPE OF WORK (continued)
- Portions of the Reactor Building Ve,ntilation System (VR): The
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, following parts of the reactor building ventilation system are safety-related: ,
- Supply air duct,between and including the secondary containment isolation dampers.and the duct penetration of the secondary containment boundary.
- Exhaust air duct between and including secondary containment isolation dampers, and the duct penetration of the secondary
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containmen't boundary.
- Those portions of the Standby Gas Treatment System SGTS (VG) installed by the Zack Co.
The independent reviewer will review the supports for all three ,
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non-safety-related but seismic ~ ally supported systems:
- Primary Containment Ventilation System (VP)
- Primary Containment Purge System (VQ)
- Reactor Building Ventilating System (VR)
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Attachment A
's Page 3
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II. SCOPE OF WORK (continued)
The reviewer shall compare the Zack HVAC installation to the S&L design, review design changes, material, and testing done in the field up through the construction testing and whatever other aspects of these systems he deems necessary to:
- " Verify that the HVAC installation is in accordance with the design. This will include, but not be limited to a review of the materials in. stalled, the field and shop welding on supports and ductwork, the operability of associated mechanical equipment, and significant design changes. The reviewer will be directed to independently verify the reliability and
- adequacy of existing material.. structural and f.ield testing a'Iready performed;.and determine any, i additional testing or changes necessary.to reach the i
conclusion that the HVAC system fulfills its safety function."
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4 Attachment A
'III. GENERAL Tne submittal should address the Quality Assurance *and Quality Control Plan that will be used to conduct the review.
All reviews should be done by appropriate procedures.
All personnel should be qualified for the, job they are required to
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perform. Suitable document ~ation should be available to demonstrate this qualification; e
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Attachment A Page 5 ,
IV. INDEPENDENCE
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Edison will make available to the independent revie'wer all dotuments requested by the independent reviewer needed to perform this review'. Any reports concerning this review shall be sent to Ceco who will in turn concurrently distribute the reports, unedited, to the NRC, S&L and internally within CECO. Prior review or editorial control of the written report by any of these parties is not permitte,d.
Any and all potential findings, shall be submitted in a timely manner to an internal finding review committee within the independent review organization composed of senior technical personnel with broad experience.in-technical management. This internal committee is to determine if the potential finding is accurate and has the potential for a safety concern. If the committee determines that the potential finding is accurate, but is i
i not a safety concern, it shall be properly documented, and submitted to Edison and dispositioned. Dispositioning may involve field correction, additional analyses or both, to ensure that
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required design margins are maintained.
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Attachment 2 Page 6 IV. INDEPENDENCE (continued) '
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If the finding is a potential safety concern, a second level internal committee will review those findings expeditiously and if the concern remains will notify Commonwealth Edison immediately.
Commonwealth Edison will properly document and disposition such findings (including taking proper action in accordance with the -
technical specifications), and notify the NRC. ,
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The individuals involved in this review shall complete Exhibit 2 and shall be free of substantive interest in Commonwealth Edison Compani or Zack. Examples of substantive interest are:
- 1. For full time personnel: any work experibnce in design, construction or quality assurance of the LaSalle County'
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Station, with Commonwealth Edison Company. or with the Zack Co.
cu'rrently or within the past five. years.
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- 2. For short term personnel: currently a.ctive on any other l
LaSalle County Station, Commonwealth Edison, or Zack Company l
l work.
L NOTE: No single short term person shall exceed 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per week and the cumulative effort of all such personnel snall not exceed 10% of the total project ef fort.
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I Attachment A Page 7 s
IV. INDEPENDENCE (continued)
- 3. An immed'iate f amfly member is employed by Commdgwealth Edison-or Zack Company or is engaged directly or indirectly in the design or constructio'n of the LaSalle County Station.
4 ., A cumulative ownership. and creditor interest in Commonwealth Edison or Zack Company Which exceeds 5% of their gross f amily annual income.
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Attachme'nt f
["g Ccmm:nw:cith Edison -
One Fast Natenat Plata. Chicago. Ithno s l
j Acoress Reply kr Post Office Boa 767 l Chicago. Illinois 60690 l
i N. ,
August 4, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 , _
SUBJECT:
LaSalle County Station Units 1 and 2 '
Resolution of HVAC Concerns NRC Docket Nos. 50-373/374
Dear Mr. Denton:
Commonwealth Edison has taken steps to resolve the quality assurance documentation deficiences of the heating, ventilating and air conditioning
. (HVAC) system installed by the Zack Company at our LaSalle County Nuclear Power Plant throughout the course of the project. Nonconformance reports (NCR'S) issued by Zack have been reviewed and dispositioned by our engineering department and the architect-engineer, Sargent and Lundy.
Also extensive field inspections have been conducted by an independent testing agency Conam.- Additionally, materials have been tested in the fielci and. verified they met applicable material specifications. Based' on these investigations, Comonwealth Edison is confident that the HVAC system as installed can perform its design safety function.
However, to add another level of assurance, Edison will have an independent
. review of the safety-related portion-of the~ HVAC. system perfonned by consultants with expertise in HVAC system design, installation and'
. operation. The following general scope has. been. developed for the. review:
' I'. Verify that the HVAC instaliation is'in accordance with the design. This will include, but tot be limited to a review of the materials installed, the field and shop welding on supports
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and ductwork, the operability of associated. mechanical equipment, and significant design changes. The reviewer will be directed to independently verify the reliability and adequacy of existing material, structural and field testing clready perfonned; and determine any additional testing or changes necessary to reach the conclusion that the HVAC system fulfills its safety function.
- 2. Notify Comonwealth Edison immediately if a safety concern is discovered.
A more detailed scope will be developed after discussions with the consultants-and a report of their review will be submitted to the NRC by September 15, 1982. The consultants review will not be constrained by operational considerations.
Page Two August 4, 1982 e
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In the event this verification program identifies any si deficiencies which would prevent the effected portion of the (s)gnif'icant HVAC sy's tem from fulfilling its safety-function, remedial action will be taken innediately in satisfaction of applicable technical specification
.'N requirements to restore adequate margin and assure the system it operable.
Operation beyond 50% pcier will not proceed until this assessment and any required remedial action has been completed.
To the extent deficiencies of lesser significance are identified, they will be do'cumented and reviewed with the NRC Staff and remedial action.
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/ if necessary, completed on a schedule agreed upon with the NRC Staff.
If there are any questions in this matter, please contact th,is office.
Very truly yours.
(['. . (2s s:<-k Cordell Reed -
Vice President ,
A cc: Mr. James G. Keppler
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.- Exhibit 2 LaSalle County-Station i Independent Design Review Agreement I - ---- - ----- --- -- - - - - - - - -
(print or type name) _
nereby agree that:
I will treat all information revealed to me in the course l'.
of my work on this project aE; confidential and will not disclose it to others not involved in the project except as directed by the Project Manager.
- 2. If I identify what I believe to be a potential finding having the potential for a significant safety impact, I will immediately notify the Project Manager for further evaluation. - - -
- 3. I will. notify the Project. Manager if during the term of.
this project I, or any member of my immedi' ate family (parents, spouse, children and grandchildren) acquire any.
financial. interest in Commonwealth Edison or Zack Company.
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l Signature . Date l
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