|
---|
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 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 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 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 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 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 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 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 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: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 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) 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 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 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 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 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 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 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 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 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 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 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 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 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) 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
MONTHYEARML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All 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 ML20151X9371988-07-0101 July 1988 FOIA Request for Le Phillips 880407 Memo to Ma Ring ML20215K2791986-09-0404 September 1986 FOIA Request for Six Categories of Documents Re 1982 Civil Penalty & Ofcs of Investigations & Inspector & Auditor Investigations of Listed Facilities ML20212A7281986-07-25025 July 1986 Requests Institution of Proceeding to Revoke Util OL for Failure to Comply w/10CFR50.54(q) & (s) & App E Requiring Maint of Effective Emergency Plan.Radiological Accident Plan Encl ML20205E4081986-07-15015 July 1986 FOIA Request for Raw Data & Relevant Computer Programs for 1982-1983 Facility Type a Integrated Leak Rate Tests ML20090J5441984-01-0606 January 1984 FOIA Request for All Documentation Re Integrated Leak Rate Tests at Facilities ML20090J5621983-11-29029 November 1983 Marked-up Petition for Emergency Relief Re Primary Containment Leak Rate.Annual Integrated Leak Rate Testing Followed Unapproved ANS Proposed Std ML20082M6711983-11-29029 November 1983 Petition for Emergency Relief Concerning Unsafe Conditions Re Integrated Leak Rate Testing of Us Nuclear Power Reactor Containments.Severe Errors,Defects & Loopholes Exist in Current Methodology ML20087N9161983-11-29029 November 1983 Notifies of Unsafe Condition Re Ability of Primary Containment of Unit 1 to Fulfill Design Function & Provide Level of Containment of Reactor Fission Products Mandated by Law & Tech Specs ML20078P0381983-10-31031 October 1983 Forwards Joint Intervenors Application for Stay & Request for Action Prior to or Concurrent W/Scheduled 831108 Vote Re Reinstatement of Suspended Low Power License ML20073G1201983-02-15015 February 1983 FOIA Request for Drafts,Insp Evaluation Repts & Comments on J Keppler 820719 Rept Re Special Safety Insp of Facility During May-Jul 1982 ML20073D8231983-02-14014 February 1983 FOIA Request for Documents Re NRC Investigation of T Howard & Morella Allegations Concerning Facilities ML20071D5931983-01-14014 January 1983 FOIA Request for NRC Records Reviewing CF Braun Audit of HVAC Sys at Facilities.Waiver of Fees Requested ML20028D8621982-12-15015 December 1982 Petitions NRC to Revoke Facility OL Until Both Main Recirculation Pumps & All Other Parts of RCS Are Operating at Full Capacity ML20070F1391982-12-15015 December 1982 Submits Petition to Revoke OL Until Main Recirculation Pumps & All Other Parts of RCS Are Capable of Operating at Full Power & Order Investigation & Open Public Hearing Into Causes of Stuck Discharge Valve on Recirculation Pump a ML20028C3451982-11-30030 November 1982 Recommends NRC Refrain from Issuing full-power License on Basis of CF Braun Co 821027 Rept.Braun Rept Neither Statistically Valid,Nor Judgmentally Sound.Rept Fails to Provide Grounds for full-power Authorization ML20028B5271982-11-19019 November 1982 Submits Interim Rept Re CF Braun Independent Analysis of HVAC Sys.Requests Further Specific Info Not Included or Discovered to Complete Final Rept ML20028A0211982-11-12012 November 1982 Comments on CF Braun 821109 Analysis of Util HVAC Sys.Nrr Approval Should Wait for in-depth Review of Serious QA Breakdown as Well as HVAC Sys Weaknesses ML20023D1471982-09-0404 September 1982 Discusses Concerns on Behalf of at Howard & s Marello,For NRC Consideration in Review of CF Braun Final Proposal to Conduct Independent Review of HVAC Sys at Facilities,Per 820824 Meeting ML20023D1401982-08-16016 August 1982 Comments on 820811 Meeting W/Nrc & Util Re CF Braun Audit of Facilities.Cf Braun Should Rept Directly to NRC & Should Audit All Critical Areas at Facilities ML20023D0661982-08-13013 August 1982 Requests That Region III Monitor CF Braun Activities in Independent Review of HVAC Sys at Facilities & That T Howard & s Marello Experience & Knowledge Be Utilized in Review Process.Util 820813 Ltr to CF Braun & Co Encl ML20023D1381982-08-13013 August 1982 Advises That at Howard & SS Marello Do Not Object to Selection of CF Braun to Conduct Third Party Investigation of Charges Against Zack Co,Subj to Listed Conditions.Related Info Encl ML20023D0391982-07-27027 July 1982 Offers Assistance & Cooperation in Investigating Zack Co. Suggestions Discussed ML20023D0331982-07-26026 July 1982 Requests Investigation of Region III Inadequate Investigative Oversight Re QA Breakdown & Possible Criminal Falsification at Zack Co,Hvac Contractor at Facilities.At Howard & s Marello Allegations Discussed ML20027A8081982-07-0505 July 1982 Forwards Request to Institute Show Cause Proceeding & Other Relief for Filing W/Nrc ML19290F1001980-02-20020 February 1980 Comments on Proposed Export to Philippines by Westinghouse. Urges NRC to Make Health & Safety of Nearby Residents Prime Consideration.Nrc Should Recommend Refusal to License Vendor for Const at Bataan ML19209C2901979-09-0707 September 1979 FOIA Request for Supplemental Records & Files Defined in FOIA-79-264 & Citizens Against Nuclear Power Petition for Suspension of Revocation Fo Facility License ML19260C4321979-08-21021 August 1979 Forwards 790821 Petition to Institute Proceeding to Suspend or Revoke CP ML19276G8851979-08-21021 August 1979 Forwards Petition by Citizens Against Nuclear Power,Il Valley Citizens Against Nuclear Power,Citizens United for Responsible Energy & Appleseed for NRC to Institute Proceeding to Suspend &/Or Revoke License ML19209A8151979-08-21021 August 1979 Forwards 790831 Petition to Suspend Proceedings,Submitted by Intervenors Citizens Against Nuclear Power,Il Valley Citizens Against Nuclear Power,Citizens United for Responsible Energy & Society Against Nuclear Environ ML19249D7171979-07-15015 July 1979 Expresses Concern Over Radwaste & Urges Halt to Plant Before Operation Begins ML19248D5981979-07-0606 July 1979 FOIA Request for All Documents Pertinent to Facility Const Delays 1989-03-08
[Table view] |
Text
,
o -
GOVERNMENT ACCOUNTABILIT( PROJECT +
~
Institute for Policy Studies 1901 Que Street. N.W.. Washington. D.C. 20009 (202)234 9382 November 19, 1982 Mr. Harold P. Denton <
Office of Nuclear Reactor Regulation '
Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: C.F. Braun Independent Audit LaSalle Nuclear Power Plant
Dear Mr. Denton:
On November 9, 1982, we received a four-volume report of the C. F. Braun Company's independent analysis of the heating, venti-lation, air conditioning system (HVAC system) at the LaSalle Nuclear Power Station in Illinois.
Although we are submitting a report to your office today, we must poirt out that it is an interim report. We have detailed our concerns, and in some cases provided some detailed justification for those concerns. We were not able to get back to the two Zack witnesses, Mr. Terry Howard and Ms. Sharon Marello, whose input into this analysis is critical.
Our final report will contain those comments, a review of the Commonwealth Edison Company's (CECO) failures to identify the HVAC quality assurance violations, and a more detailed justification of the items highlighted in this report.
Within the context of this interim' report by the Government i Accountability Projecti (GAP) is a request for further specific information not included or discovered wi. thin the C. F. Braun four-volume report. -
It is imperative for our consultants and staff to have this additional information in order to draw final conclusions about the reliability of this audit and the implications of the l~
findings affecting the safety of the public and of the site l employees. -'
Our' interim findings follow.
~
+. XA ;
l November 19,~1982 Mr. Harold P. Denton-1
' The C.F. Braun independent review of the safety-related and seismic supported non-safety related systems at LaSalle comes to the conclu-sion that the " installation by the Zack Company is in accordance with l the Sargent and Lundy design and the workmanship to be of adequate l
quality."
! The Government Accountability Project takes general and specific exception to this conclusion. We urge the Nuclear Regulatory Com-mission Office of Nuclear Reactor Regulation to take a number of I specific actions in response to this audit:
Require Commonwealth Edison to recall C.F. 'B'raun; modify' 1) the terms of Brawn's contract, and continue with the probe at the La Salle facility. The scope of their work simply i
must include a more comprehensive view of the -safety systems at the f acility.
- 2) Restrict the La Salle license to 48% power until there is further work done to identify the Zack errors that need to be repaired, replaced, or reworked, and that required repairs i .
are completed.
- 3) Request Region III to consider enforcement action against Commonwealth Edison for f ailing to adequately supervise sub-contractor in their procurement and' supply of materials to be used in the plant.
m
- 4) Assign a Region IV vendor inspector to audit / review these conclusions in the light of specific C.F. Braun statements I
which disregard 10 CFR 50, Appendix B.
- 5) To consider this letter as an interim A more report, prepared for detailed analysis of-the your immediate consideration.
specific Zack allegations, as well as review by Zack Nuclear witnesses will follow this report by a few days.
As you are aware se are specifically engaged in both the Midland and the Zimmer plants--both'of which are in intensely active stages of NRC involvement. At the William H. Zimmer plant in Ohio, GAP Legal Director Tom Devine is working with officers of the Federal Bureau of Investigations to review the massive amounts of evidence and talk to nuclear witnesses. His comprehensive knowledge of the Zimmer plant is irreplacable and therefore he has been delayed from finishing the
.~
significant portions of his analysis. .
Bille Garde, Director of GAPS Citizens Clinic has beed equally as involved in the investigation of the Midland Nuclear Plant in Midland,-
Michigan. The GAP investigation on the Midland site has become a full scale probe, and as you are aware this is a particularly critical time period at Midland. .
Mr. Harold P. Denton November 19, 1982 Further, those experts and analysts who have made their services available to GAP have had only a very short time period to deal with an incredible amount of almost totally unorganized raw data.
The first opportunity that was provided for us to review this four-
' volume report came last Tuesday, after GAP had contacted the NRC to receive a copy of the C.F. Braun study. We understand that there was a September 5th interim report provided to the NRC, of which we did not receive a copy; and that other individuals in the press and Illinois received copies as much as ten days prior to our receipt of the final copy. This oversight unfortunately has caused unnecessary delay and expense for all parties.
However, the most significant delay in finishin'g our analysis has come from the shocking conclusions reached by,the C.F. Braun audit team. It has lef t us no option but to go back into the raw data of the report --almost item by item -- to scrutinize each conclusion reached by Braun. The NRR staff can expect our final analysis no later than Tuesday, November 23, 1982.
Critique of C.F. Braun Summary The following comments summarize the major flaws that GAP' analysts have.found to date in the C. F. Braun audit of Zack's work at the Further LaSalle Nuclear Power Station near LaSalle, Illinois.
development of each item will follow in our expanded response to the C. F. Braun assessment.
- 1. The methodology employed by C. F. Braun in selecting the hangers, ducts, and other pieces of equipment invalidate the Co nclu sions .
During the August 24, 1982 Region III meeting, and in his September 4, 1982 letter, GAP warned that the criteria to select items _for the audit could prejudice the project. Unfortunately, our concerns were realized.
In our opinion, it is clear that the study's conclusions were biased by tha sample. Expert industrial quality control analysts contacted l
l by GAP reiterate that for any sample to validly reflect the entire population (in this case total number of hardware items), that.. sample must be randomly selected from the entire range of possibilities. -
C.F. Braun did noc employ this basic industry quality assurance -
standard. The " Summary of Work" is clear; the selection process is subjective:
These selections for inspection we,re made based on their own engineering knowledge and experience in con-junction with some basic guidelines as follows.
4 .
v Mr. Harold P. Denton November 19, 1982 If Braun intended to limit its review to less than a 100% inspection effort, it should have employed a random selection process for all i pieces of equipment reviewed -- not for just a few systems.
The consequences of Braun's risk are extremely serious. The NRC and the public are left with only two options:
- 1) Reject the Braun report because of a basic generic flaw in its methodology; or ,,
- 2) Accept the Braun report, pretend that it was a valid assessment and do an analysis of the conclusions based on the mythical assumption. -
After several consultations with nuclear power analysts, statisti-cians, and industrial quality control professionals, it became clear that the only option available to the NRC is to reject this report's general conclusions. In fact, it was the unanimous opinion of the f .
analysts we contacted that without a random sample the conclusions are meaningless. As one person put it: " Virtually all of the techniques used to analyze data require that this data be obtained in accordance with well-specified rules of random sampling."
Although it would have been reasonable to conclude our review with a rejsetion of the Braun assessment purely on the grounds of a flawed Our methodology, we nevertheless proceeded with our own assessment.
review, however, should not imply that we accept the 335 selected pieces of HVAC equipment as a valid sample.
Despite the conclusions, the substance of the Braun report confirms Mr. Howard's and Ms. Morello's concerns. It demonstrates that GAP's initial reservations about the weaknesses of the audit were well- ~
founded. In fact, each unresolved concern raised by GAP in the series of meetings and correspondence surrounding the beginning of Braun's work has proved to be a forewarning.
l .
- 2. Of the 335~ pieces of equipment reviewed, Braun concluded that 34 % (117 items) had discrepancies of varying significance.
The extrapolation of a 34% error rate to the What entireeven remains HVAC system more at frightening the LaSalle plant is frightening.
is the significance that this error rate has for the rest of.th,e
~~
HVAC system. If the Braun sample truly is representative, clearly one-third of the HVAC system at LaSalle is in a disqgepant condition.
One NRC inspector estimated that there are 45,000 potential pieces j of HVAC equipment (safety and non-safety) on the LaSalle site.
Because it has been impossible to turn up more realistic data,
(
' that number is offered merely to illustrate'the significance of Braun's audit findings. A 100% review of the 45,000 pieces could _
k W e
e
,- - -_.m .-
November 19, 1982 Mr. Harold P. Denton predictably produce 900 " findings," Given 30,600that observations, and only the 335 pieces actually 12,150 non-discrepant conditions.
used reflected a biased sample, it is probable that the actual review would produce even worse results.
In order to produce a more accurate assessment, GAP analysts need significant additional information missing from the' current version of the report --
- 1) The total number of pieces of HVAC equipment on the ~
LaSalle site, broken down by safety or non-safety related functions;
- 2) The total number of pieces in each system,.rather than just the percentage of hangers in the system that were reviewed; 1
- 3) .The total number of possible " finding" if all potential saf ety-related defects were actualized; and
- 4) In each instance, the variance for acceptable limits of error as specified by the approved design.
The most dramatic cxample of C. F. Braun's disrespect for NRC reg 61ations is evident in the study's conclusions on welder quali-fications:
The Zack welding performance qualification records (PQR) were reviewed. Although some PQRs are incomplete, Braun does not feel that this degrades the welding program since Zack was not required to conform to a specific code or standard. It'has been determined that the weld quality is consistent on all supports regardless of who performed the welding.
Clearly, the Nuclear Regu'latory Commission First, cannot Braun's accept Zack's obser-willingness to waive nuclear safety laws.
vation that "Zack was not required to conform to a specific code or standard" is simply wrong. The Atomic Energy Act requires welders to'be qualified. Regardless of Braun's conclusion that "all is well" despite an inability to prove welder qualifications, 10 C.F.R. 50, Appendix B, Criterion II is clear that personnel J
participating in a quality assurance program must be properly '
~
trained and qualified. The only way to avoid this requirement' would be to remove safety-related HVAC welding from ,0A coverage --
an illegal loophole that Braun tacitly accepts.
i At Zimmer the problem of welders whose qualifications could not including a l be verified has led to severe enforcement actionContinuing doubts about massive recertification program.
proof of welder qualifications played a major role in the .
k "
e
a November 19, 1982 Mr. Harold P. Denton Commission's November 12, 1982 shutdown of the facility.
In the documentation provided in the Braun report there is little room for doubt about the qualification of Zack's welders.
In .the September 14, 1982 review, of the 111 welders tested 4 2 failed the test; in the second round of tests given in earl'y October, 24'of 123 failed to qualify. Even in the final qualification review on October 26, 1982, there were 12 unqualified welders from the 52 tested. ,
Braun's "f eeling" that the lack of qualification for Zack's welders does not degrade the welding program casts serious doubt on all of Braun's assessments. It should not be necessary to debate that weld quality has a significant relationship to the verifiable qualifica-tions of individual welders.
Other examples of major flaws that we have discovered within the Braun assessment are highlighted below:
- 1) It is apparent that numerous design changes, designer justifications, and changes in the drawings resalted from the errors found.
It is not clear that the initially approved NRC design was signifi-cantly' changed as a result of hundreds of changes, revisions, and resolutions. Further, in most cases, Braun did not analyze the Sargent & Lundy justification; Braun merely accepted at f ace value whatever S&L concluded.
- 2) A review of the Inspection Report log reveals that out of 335 alleged system inspections 7 pieces that were covered by-the sample did not receive full inspections.
The comment, " Hanger could not be inspected due to location," was noted for S-978, S-964,(S-987, S-986, S-973, S-1327 and S-1332.
So even the number 335 1s not an accurate reflection of what was inspected. .
- 3) There are numerous examples of Braun ' conclusions based on CECO's regularly scheduled tests or start-up tests.
As we had f eared, the Braun audit appears to amount _tg little more than an industry rubber stamp.
- 4) It is not clear how many findings were reported to the Braun Internal Review Committee and Commonwealth Edison Company from the site team.
e
, e e
Mr. Harold P. Denton November 19, 1982 We do know that eventually three w'ere repor'ted-to the NRC; however, since there were two levels of review prior to NRC notification, it is impossible to determine whether more of the observations were being considered as findings.
- 5) on page 23 of the summary there is an interesting but significant typographical error.
The second paragraph has obviously been "doctoredr" It is unclear by whom the changes were made. The purpose of the doctoring appears to be to remove certain statements about the Zack non-conformance reporting system. We would like to request that the NRC review the initial page 23 -- prior to doctoring -- and make a determination of .what was removed, why and by whom. This unfortunate slip-up reveals last-minute company changes in the Braun report and under-mines the credibility which it is supposed to guarantee.
The substance of Braun's comments suggests that the numerous %ack nonconformance reports should have been Quality Control Inspection Reports. Our experience with duplicate NR forms leads us to strongly disagree with this Braun conclusion. (At Zimmer, there was a similar change made to undermine the NR procedure. This replacement pro-cedure contributed significantly to the plant's condition being "ind.e te rmina te. " )
- 6) Other observations that our staff has made that will be further developed in our final report are listed below:
l
-- The lack of organizational independence of C.F. Braun from CECO.
-- The lack of informational independence of C.F. Braun from i CECO.
-- The failure of C.F. Braun to make independent evaluations i
of CECO and S&L judgement.
-- The failure of C.F. Braun to extend the size of the sample after. discovering critical problems.
! -- The failure of C.F. Braun to follow through with disposition of their findings. .
-- The failure to cite relevant professional code requirements to justify their procedures. .
4- The failure to justify their conclusions with relevant pirofession l
code requirements. .
i
-- The absence of hardware tests. _
-- The non-specific quantification of the numbers reviewed. --
m
s Mr. Harold P. Denton November 19, 1982 The reliance of C.F. Braun on Zack, S&L, and CECO tests and analysis.
FAILURE TO ADDRESS SPECIFIC ISSUES RAISED BY THE WHISTLEBLOWERS The extraordinary remedy that created Braun's review is the direct result of,whistleblowing disclosures from Mr. Howard, Ms.
Marello, Mr. Ronald Perry and other former employees of the Zack,.
Corporation. If subjective assessments are to repla~ce standard statistical sampling techniques, no opinions come with better credentials than theirs. Unfortunately, Braun chose not to even attempt token communication with the whistleblowers, despite their announced eagerness to assist. As a result, Braun's report does not even report to address the specific concerns targeted by those responsible for the probe.
To illustrate, the report failed to --
- 1) guarantee that all relevant Nonconformance Reports ("NCR")
were reviewed. Although the report discussed a review of 1756 NCR's; fewer than Mr. Howard and Ms. Marello estimated were included in the scope of their equivalent effort, and fewer than the 2200 figure that Braun concedes it received.
- 2) review and establish current HVAC site specifications at Lasalle, which were unknown to Zack when certain materials were originally purchased.
- 3) items never reached by the still-incomplete Zack internal document review.
}
- 4) target items covered in the suspect February 1982 CECO audit which Mr. Perry challenged.
- 5) all site records generated after January 1982, when Sargent and Lundy ceased indpendent reviews of Zack site documentation.
- 6) purchase orders from unapproved vendors, either because they never qualified for or were removed from the Approved Vendors List.
- 7) purchase orders where there is evidence of questi.onable .
,_. records alteration or forgery. ..
CONCLUSION To some extent the explanation for the flaws in the Braun 4 -
e h
~'~ November 19, 1982 Mr. Harold P. Denton report is that the NRC exercised only token oversight. While CECO audited the " independent" reviewers, NRC site supervision was limited to one visit by one inspector. While staff priorities are understandable, the net result is that this third party report cannot legitimately serve as the basis for any final regulatory decision on Lasalle. The necessary facts will not be in until the staff releases its own reports.
If anything, the substance of the Braun finding's are both Despite its mandate, Braun ominous and understated in the extreme. It relied produced a paperwork review of a paperwork breakdown.
extensively on factfinding from the targets of the inquiry. It accepted at face value the suspect design changes approved without design requirements question by Sargent and Lundy, which rewrote the'To approve full power for as needed to " legalize" Zack's violations.
Lasalle on the basis of this report would represent a regulatory decision in spite of the facts.
Sincerely, Thomas Devine Legal Director Billie Garde i
Citizens Clinic Director cc: Mr. Thomas Novak TD:BG/my .
% N s
- e . - .
~
~.) -
f PLEASE REVIEW THE DUE DATE IMMEDIATELY IF THE DUE DATE DOES NOT ALLOW ADEQUATE oTIME TO RESPOND TO THIS TICKET, YOU !MY
' REQUEST A REVISED DUE DATE. THE REQUEST
'MUST INCLUDE A VALID JUSTIFICATION AND BE IMDE THROUGH YOUR CORRESPONDENCE CO-ORDINATOR TO THE NRR MAIL ROOM (VAREN JOHNSON OR MELANIE GARVER) SUCH REQUEST FOR GREEN TICKETS MUST BE !MDE WITHIN 3 DAYS AFTER ASSIGNMENT (3 DAYS AFTER BEING
- ASSIGNED IN NRR MAIL ROOM) REQUEST FOR REVISION OF YELLOW TICKET DUE DATES MAY BE IMDE, WITH JUSTIFICATION THROUGH THE .
WEEKLY WITS UPDATE. (ONE WEEK AFTER ASSIGNMEllT IN NRR IMIL ROOM) THE DUE I
- DATE,TIF APPROVED BY PPAS WILL BE USED I TO TRACK DIVISION CORRESPONDENCE COMPLE-TION SCHEDULES. ALL GREEN TICKETS ARE j
, DUE TO MR. CASE /VIA NRR IMIL ROOM TWO ,
- DAYS BEFORE THE ED0-STATED DUE DATE ,
LEASE DO NOT HAND CARRY CONCURRENCE
' PACKAGES WITHOUT GD1im. a nxcuati $t, xxx,
[MAILROOMFIRST. i.
a D.ft OS 00cuwE~t D.tf npeteven M ,
,,g, ,
NRR-82-489 Thoran Devine ,
11/19/82 & 11/30/82 12/2/82 Ovesa
. tra wi uo acroat g
\
^?
r .
Oa.o Cc Oi-i-H. Denton .ct,0~ ~, cess...
o w . m ....c. o o... .~,. ..o
' * *c "" c"5^"' O m==*~r O . 12/30/82 Pos t op p act peLE COOf
'~CLJ.nses RfG ~O pt$CRsPYso~ 6 Muse .e U$end4st' Rf f f RMEO TO D.i f REC (ty(D .y 0.f4 C. F. Braun independent audit Eisenhut 12/2 cc: Case LaSalle Nuclear Power Plant w y_ Derteri fY au
~~" '
M 3Ws;er
- 5. Thompson
- 6. Ched i
2 letters dated Nov. 19 & 30 7. Snyder for appropriate action hd 'E c' rit or Nacb ,r -m
"'"'""hg3 pon n!r SIC'!EU:G OF DIF C"On,I G DI113102 DIEICTOR 02 LZ3IGNZE uu -
Jh%t/
,,s" N -~---
____ _y MAIL CONTROL FORM , $,'