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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 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 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 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 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 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 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 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:UTILITY TO NRC
MONTHYEARML20059H5321990-09-11011 September 1990 Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers ML20059H4271990-09-0707 September 1990 Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831 ML20059G0941990-09-0505 September 1990 Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp ML20059C6891990-08-30030 August 1990 Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary ML20056B4061990-08-21021 August 1990 Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements ML20059B8961990-08-14014 August 1990 Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed ML20059D1731990-08-10010 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels ML20058N2971990-08-0606 August 1990 Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21) ML20064A5491990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation ML20056A7031990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H7661990-07-24024 July 1990 Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20055G2011990-07-13013 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for LaSalle County Unit 1.Outage/Reduction 16 Corrected ML20055F1831990-07-0909 July 1990 Provides Status Rept on Breaker Replacements in Response to NRC Bulletin 88-010.Breaker Replacements for Plants Scheduled to Be Completed by 901031 ML20044B1751990-07-0909 July 1990 Responds to NRC Request for Addl Info Re Util 890726 Proposed Amend to Tech Specs to Allow Continued Operation for Period of 12 H W/Main Steam Tunnel High Ambient Temp & High Ventilation Sys Differential Trips Bypassed ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D1921990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues ML20055J2021990-06-26026 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-06 & 50-374/90-06.Corrective Actions:Perimeter Zone Repairs Commenced on Schedule & Completely Functional & Out of Compensatory Measures on 900614 ML20044A5071990-06-22022 June 1990 Forwards Revised Response to Station Blackout Rule for Plant.During Blackout Event,Plant Can Utilize RCIC Sys or HPCS to Provide Required Reactor Vessel Inventory Makeup ML20043E8651990-06-0707 June 1990 Forwards Relief Request RV-57 for Emergency Fuel Pool Makeup Crosstive Vent Valve 1(2)E12-F097.Expedious Review of Request Requested Because Valve 1(2)E12-F097 Inoperable & Will Remain So Until NRC Approval Received ML20043D3221990-06-0101 June 1990 Forwards Rev 33 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C8241990-06-0101 June 1990 Advises of Intentions to Review & Approve Cycle 4 Reload,Per 10CFR50.59 & Forwards Rev 1 to LAP-1200-16, Core Operating Limits Repts for LaSalle County Station Unit 2,Reload 3, Cycle 4, Per Generic Ltr 88-16 ML20043B6581990-05-25025 May 1990 Requests Schedular Extension of Two Human Engineering Deficiencies Re CRT Displays W/Current Ramtek Sys & Approval to Leave Seven Human Engineering Discrepancies Accepted as Is. ML20043B7921990-05-23023 May 1990 Forwards Endorsements 14 to Nelia Policy N-71 & Maelu Policy M-71 & Endorsements 12 to Nelia & Maelu Policies N-83 & M-83,respectively ML20042E8841990-04-30030 April 1990 Responds to Generic Ltr 89-04 Re Weaknesses of Inservice Testing Programs.Plant Has Implemented Rev 2 of Inservice Testing Program Submitted by Util 891002 & 24 Ltrs.No Equipment Mods Required as Result of Generic Ltr ML20042F3591990-04-29029 April 1990 Provides Suppl Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Precaution Added to Operating Procedures Which Allows ECCS Pump to Be Secured & Restarted as Necessary to Preclude Running Pumps at Min Flow ML20042F0341990-04-23023 April 1990 Forwards Part 3 to 1989 Operating Rept,Containing Results of Radiological Environ & Meteorological Monitoring Programs. W/O Encl ML20064A6281990-03-30030 March 1990 Submits Supplemental Response to Insp Repts 50-373/86-04 & 50-374/86-04 Re Fire Detection Concerns,Per NRC 900214 Request.Proposed Administrative Controls & Training Will Eliminate Concerns That Assure Protection of Personnel ML20055E1461990-03-29029 March 1990 Provides Supplemental Response to Re Violations Noted in Insp Repts 50-373/89-18 & 50-374/89-18 on 890724- 0825.Corrective Actions:Plant Performs Safety Evaluation for Mods Not Designed by Corporate Nuclear Engineering Dept ML20012C6991990-03-15015 March 1990 Forwards Corrected Tech Spec Page to 881129 Application for Amend to Licenses NPF-11 & NPF-18,removing Specific Load Profiles for Each Dc Battery ML20012B6541990-02-26026 February 1990 Forwards LaSalle County Station Unit 1 Third Refueling Outage ASME Section XI Summary Rept, for Fall 1989 Inservice Insps Performed.Conditions Observed & Corrective Measures Taken Also Contained in Rept ML20006E7421990-02-0909 February 1990 Responds to NRC 900110 Ltr Re Violations Noted in Insp Repts 50-373/89-23 & 50-374/89-22.Corrective Actions:Ltr from Station Manager to All Dept Heads Was Issued on 891218, Discussing Personnel Performance Issues ML20005F5771990-01-0808 January 1990 Documents Guidance Given by P Shemanski Re Typos in Earlier Approved Amend to License NPF-11.Guidance Should Adhere to Wording of Unit 2 Tech Specs.Guidance Given on 900105 & Will Be Followed Until Correction Made at NRR Ofcs ML20011D9661989-12-22022 December 1989 Forwards Core Operating Limits Rept for LaSalle County Station Unit 1,Reload 3 (Cycle 4). Intention to Review & Approve Cycle 4 Reload Under Provisions of 10CFR50.59 Stated ML20005E1661989-12-22022 December 1989 Forwards Rev 32 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facilities.Rev Withheld (Ref 10CFR73.21) ML19332E4531989-11-29029 November 1989 Responds to Generic Ltr 89-21, Status of Implementation of USI Requirements. Response to USI A-48 Expected by 900319 ML19332C2461989-11-0808 November 1989 Provides Supplemental Response to Insp Repts 50-373/88-05 & 50-374/88-05 on 890302-10.Scheduled Completion Dates for Sample Panel Mods Changed from Third to Fourth Refueling Outages of Each Unit ML19325E5191989-10-31031 October 1989 Forwards Qualification Test Rept QTR87-018, Max Credible Fault Tests CM249-Q2 Carrier Modulator for Fermi 2 SPDS, in Response to NRC 890304 Request for Addl Info Re Facility Validyne Isolator CM-249 ML19325E3601989-10-26026 October 1989 Forwards Addl Info Re Application for Amend to Licenses NPF-11 & NPF-18,revising Tech Specs to Conform W/Diesel Generator Test Schedule Recommendations,Per Generic Ltr 84-15 ML19325E7921989-10-24024 October 1989 Submits Response to SALP 8 Board Repts 50-373/89-01 & 50-374/89-01.Expresses Appreciation for NRC Recognition of High Level of Performance in Area of Plant Operations, Emergency Preparedness & Security ML19325E0941989-10-24024 October 1989 Forwards Clarification to Summary of Changes Made in Rev 2 to Plant Inservice Testing Program ML19353A9051989-10-23023 October 1989 Responds to NRC 890921 Ltr Re Violations Noted in Insp Repts 50-373/89-19 & 50-374/89-19.Corrective Actions:Hose Connection That cross-connected Svc Air Sys W/Clean Condensate Sys Uncoupled & Secured ML17285A8081989-10-18018 October 1989 Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 70 ML19325D1931989-10-13013 October 1989 Forwards Quarterly Rept on Static-O-Ring Failures Third Quarter 1989,per IE Bulletin 86-002.Stated Switches Replaced ML19327B0431989-10-0505 October 1989 Responds to NRC 890821 Ltr Re Violations Noted in Insp Repts 50-373/89-15 & 50-374/89-15.Corrective actions:post-order for Assembly Revised to Provide Specific Guidance on Use of Siren & Loudspeaker on Mobile Vehicles During Assemblies ML19327A7491989-10-0202 October 1989 Forwards Rev 2 to Combined Units 1 & 2 Inservice Testing Program for Pumps & Valves. Implementation of Program Will Require Procedure Revs Expected to Be Completed by 900228 ML19325D3271989-10-0202 October 1989 Forwards Rept Re Findings & Conclusions of Investigation Re 890826 Scram ML20248D0881989-09-21021 September 1989 Forwards Rev 56 to QA Program Topical Rept CE-1-A ML20247Q6431989-09-21021 September 1989 Documents Relaxation of Commitment Re Disassembling & Insp of Sor Switches ML19327A7681989-09-18018 September 1989 Forwards Response to Allegations Re Potential Employment Discrimination.Encl Withheld (Ref 10CFR2.790(a)(7)) 1990-09-07
[Table view] |
Text
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f"N C:mmenw:alth Edison
~ ) One first Nat onar Piaza. Chicago. nhnois
[.
3 TJ J'? Address Reoly lo: Post Othee Box 767
\ / Chicago. Ilhnois 606??
2 March 27, 1981 Mr. B. J. Youngblood, Chief Licensing Branch fl o . 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Supplemental Information in Response to NUREG-0519 Open Items NRC Occket Nos. 50_373/374 -
% l References (1): L. O. DelGeoge letter to B. J. Youngblood dated March 6, 1981 l
Dear Mr. Youngblood:
The pyrpose of this letter is to provide supplemental ,
information which adoresses the open items defined in Section 1.8 of the LaSalle County Safety Evaluation Report (SER), NUREG-0519. Each of these items with the exception of item ) is addressed in an enclosure to this letter. With respect to item I, the required occumentation of conformance to the safety significant regulations was submitteo in Reference 1 If you have any questions on the attached materials, please
, direct them to this office.
Very truly y urs, L. O. D e 1 %3 o rg e Nuclear Licensing Aoministrator l Enclosure cc: NRC Resident inspector - LSC5
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Enclosure 1 1
-Item 2. .Small Pipe Visual Inspecton During Preoperational Tests 13.9.2.1) J Commonwealth Edison has reviewed the additional
. surveillance recommended by the NRC Staff and with one exception '
will: perform the inspection proposed. A detailed discussion of our planned inspections is presented below.
- 1. R e a c *. o r pressure vessel level indicator instrumentation lines A visual inspection of vessel level and pressure instrumentaton lines will be'made in conjuction with Startup Test Procedure (STP) 34, " Vibration Measurements." The visual. inspection will be conducted to identify any excessive vibration that could result in fatigue' failure.
- 2. Main Steam instrumentation lines for monitoring main steam flow l Although Commonwealth Edison has evaluated the performance of this test, it is judged to be impracticable and,.therefore, a comm1tment can not be made.
(a) A meaningful test can not be performed without steam flow.
The environmental conditions including temperature and radiation make it impossible for this test to be performed visually.
(b) Instrumentation of the subject lines can not be achieved without jeapardizing existing test schedules. In this regard, it should be clearly understood that this syctem was never under consideration for vibration monitoring under Preoperational Procedure 14.2-4 5 o r S tartup Tes t Procedure 14.2-130. In fact, the NRC did not raise the possibility of monitoring this additional system until February, 1981, notwithstanding the acceptace by the Staff
- < the proposed testing in 1979 Furthermore since the instrument lines in question provide input to op transmitters, were a tailure to occur, the
- resulting hi-dp signal would result in a vessel isolaion which is an analyzed transient not limiting to the plant design.
For these reasons, it is judged that this test need not be performed, due both to the fact that it does not add to the safe operation of the plant, and its addition at this time imposes an undue burden.
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- 3. Reactor Core isolaton Cooing Lines on the RC IC s team line outsiae containment.
The requested visual inspection of these lines to identify any excessive vibration is-currently planned as a-part of the Orywall Piping Vioration Test (see Table 14.2-136).
.4. -Control Rod Drive (CRO) lines inside containment The requesteo visual inspection to identify any' excessive vibration will be performed for all CR0 withdraw and insert lines insice contain' ment in conjunction with Startup Test Procedure 34, " Vibration Measurements".
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Enc losure 2 l
l Item 3. Dynamic Qualification-(3.10)
All safety-related equipment covered by the SQRT program were covered by an' extensive dynamic qualification program. this complex program included many activities that may be summarized as l
follows:
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- 1. ' Comprehensive evaluations for~the original seismic qualifications in view of the new acceptance criteria based on- t
. :a. All new loading combinations (including LOCA and pool
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dynamic loads).
l b. U.S. MRC Regulatory Guide 1.92
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- c. IEEE 345-1975
~d. U.S. NRC Regulatory Guide 1.100
- e. 0.S. NRC SRP -3.9.3 and 3.10
- 2. Requalificat' ion efforts, using testing, analysis or both, to
. demonstrate the acequacy of equipment for which the original seismic avalificatons did not meet the requirements of the new acceptance criteri).
- 3. H ardwa re . de s i gn mo'a i f ic a t i ons f o r equ i pmen t which failed to meet ,
I the requirements of the new acceptance criteria.
- 4. ' Replacement of equipment which cannot be modified to meet the new acceptar.ce criteria (this happened only in one case).
Evaluation Results The evaluation process was completed a year ago and all pieces'cr equipment for which the qua lit ication did not meet the new criteria . vere ioentified. A study was made to categorize areas of deflCiency and develop a plan cf attack to address these ceficiencies. ,
Requalification Efforts I. Analysis
- a. 300 reports were revised to include the new loads. This work has been completed.
- b. 30 reports including new detailed dynamic analyses for all new requirements were completed.
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- c. Fatigue evaluation for LPCS pump and the RHR Heat Exchanger was conducted for the extended duration of the pool dynamic loads and completed.
- d. A valve flexibility study to Justify all amplificaton factors used in the qualitication is in progress.
II. Testing
- a. Laboratory Tests Complete new qualification tests were (and are being) conducted for 17 peices of equipment (mainly electric) and 30 pieces of instrumentation equipment.
- b. In-plant Testing
.i) Impedance testing was completed for 16 pieces of equipment mounted on pipes and on the floor. The evaluation.of the data'is in progress.
ii)' SRV testing - 5 floor mounted equipment plus tew pipe mounted equipment will be monitored during the test.
Design Modification A number of design modifications were required and implemented in the cases of four valves, hydrogen recombiner and numerous HVAC hangers to 9 duce the severity of the input to dampers. A few aoottional i cifications are being studied but are not finalized yet.
Equipment R4ulacement Certain sub-components of the RCIC pump turbine have been replaced. '
This is the only case to be reported at the present time, but this aption ;s stil' Ivailable it needed for use in the future.
- STATUS 95% of dOP equipment qualifications are completed. The 5% remaining is in progress and scheduled to be completed by the end of May, 1981; except for. valve operators which may extend to June 1981. 80%
of NSSS equipment qualifications are completed. The 20% remaining ,
is in progress and will be completed by May 1981 except valve operators which may be extended to June 1981.
Conclusions All equipment will be qualified to meet the new acceptance criteria cy .iune-198'.
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1 Our equipment qualification demonstrates structrual integrity, functionability and operability.
j Our equipment qualifications has the following built in conversatism l and/ir margins:
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a) use of low damping values (1% & 2%)
b) use of racial resultant of the pool dynamic ioads in both horizontal directions c) use of response spectrum curves i n lieu of time histories c) use of peak broadened response spectrum curves for all dynamic loads.
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Enclosure 3 Item 4 Environmental Qualification (3.11)
Commonwealth Edison has idenitified the electrical,
' equipment-at LaSalle Station Units 1 and 2 which may experienc2 HARSH environments due to Loss of Coolant Accidents (LOCA) Feedwater Line Breck Outside Primary Containment and High Energy Line Break accidents (HELB). The equipment identified by Edison included:
- a. Equipment neeoed to bring the reactor to a cold shutcown condition following the defined accidents.
- b. Equipment needed to remove core decay heat to preserve integrity of fission proauct barriers.
- c. Equipment that must not fail in manner detrimental to the above two safety functions.
Plant lo.ations and. equipment functions have been idenified i n terms of safety,.i.e., active (must function), passive (must preserve pressure boundary i ntegity), and "important to safety" if the equipment must r<ot function or interact deleteriously with safety equipment.
<A review of all LaSalle County 5tation safety-related electrical equipment in. harsh environments was completed against the 00R Guidelines-(Guidelines for Environmental Qualification of Class'IE
- Electrica'i Equipment in Operating Reactors), and was submitted ~to the NRC Staff on October 31, 1980.
The results of this review showed that approximately 85% of i tems in harsh-environments were qualified to the 00R Guidelines, approximately 10% were awaiting documentation and approximately 5%
were;uncergoing E.Q. testing.
' The conclusions evident from this original comparison to 00R Suiceliset'*ere-as follows:
- a. All Class lE equipment was environmentally qualified with occumented records, or was qualfied but wri. ten reports were still being assemblea, or the devices were undergoing E.Q. testing.
- b. .The only exception was the change out of a limit switch to obtain a suitaole qualified model.
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. Based on the results of the E.Q. comparison 1to 00R Guidelines, a
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plant _ systems, review was made for all. systems employing Class lE
' cevices whose E.Q. documentation was not completed. This systems review-would,conclud that the required plant safety functions were invalidated by failure of'any individual item on this incomplete
-documentation list._-The bases-included the following: functional time: analysis, similarity analysis, knowledge'of test results net
,' yet in_ report format, ana comparison analyses.
Suosequent to this original eva~1uation against the 00R Guidelines,
- but prior to the NRC Staff directive of February 13, 1981 to perform th'ereview to NUREG-0588, Commonwealth Edison contracted Wyle Laboratories to upgrace the environmental qualification of Class IE equipment at-La Salle CountyLto the Category II requirements of NUREG-0588 " Interim Staff Position on4 Environment Qualification of Safety-Relatea Electrical Equipment".
The' current'. expanded program'is designed to, reevaluate the
-previously. identified items and through analyses using existing test documentation or through'new testing . achieve-full' qualification status to NUREG-0588 (Category II) requirements.
' Plant' environments have been tabulated for equipment l o c a t i o.o s .
These environments have been grouped into a number of bounding environmantal envelopes for the purpose of simplifying toe qualification analysis and testing efforts.
Equipmentfitems have been grouped by Manufacturer and Model number into equipment lists; the HARSH environemnt zone shave 88 separate list entries. Ninety-five list ert<ies are associated with NON-HARSH environemental1 zones.
Extensive' data search through environmental qualification reports ,
and records at Wyle Leboratories and other sources plus the vendors
' engineering record files is nearly completion. A n a l y t t,c a l avaluati3ns on aging are underway on 49 of the 88 list entries.
Qualification assessment files are retained open for receipt of 4 aplicable data until the analytical work is complted. At that time a reccanendation is made for qualification testing to assure f u l '.
compliance witn the NUREG-0588 requirements.
The sequen'ce of indiviaual list entries therefore, produces a sequence of test recommendations. These~ recommendations are reviewed by the utility for test approval or a replacement
-aecision. Test procedures are written for groups of similar equipment where aossible. -These test procedures are amplified into test schedules to assure that effective testing is done on a scheduli which meets the objective dates.
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Major milestones for LaSalle as documented in the L. O. DelGeorge letter to B. J. Youngblood of March 9, 1981, are as follows:
Initial Submittal to NRC of EQ Report October 31, 1980 Completion of Evaluation (Analysis) June 30, 1981 Decision of Last Recommendation July 31, 1981 Completion of Last Test Series May 1, 1982 Final Qualification File Completed June 30, 1982 (Note that the above dates are the completion dates for the final activity of that action category).
Analytic 11 techniques used in Reevaluation of equipment include:
thermal lag analysis, test duration analysis, degardation equivalency analysis, safety functional time analysis.
Combinations or categories of equipment items into test groups based on environmental profiles enable sequential testing with minimum schedule upset. The sequence of testing includes:
A.) Test Plan (Procedure) 8.) Baseline Functional Tests C.) Radiation Aging D.) Functional Tests E.) Time-Temperature From Aging or Cyclic Aging F.) Functional Test a.) Extreme Environments n.) Functional Tests I.) Seismic Qualfication J.) Functional Test K.) Harsh Environments L.) Functional Test M.) Test Report issued l I
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A meeting with the NRC Staff i s scliedu led for March 31, 1981 to review the existing LaSalle County environmental qualification records in order to clarify the current status of those records for the Staff. It is hoped that subsequent to this i meeting and understanding will have been reached regarding the extent to which docketed qualification summaries require f augmentation prior to the Staff initiating its audit of qualification records.
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a Enclosure 4 Item 5. Fuel Claa Ballooning and Rupture ( 4 . 2 . 3 )_
General Electric Company is currently completing sensitivity studies which bound NUREG-0630 data. This study, utilizing the CHASTE OS (fuel heat-up code), is expected to show a maximum peak clad temperuture (pct) impact of less than 200F. No change in maximum average planar heat generation rate (MAPLHGR) is expected.
The NRC Starf has expressed cuncurrence aith this approach as a basis for resolving the fuel ballooning issue for LaSalle County, and any other BWR NTOL plant ror which the sensitivity study is representative.
A draft copy of this report is expected to be provided the Staff on March 31, 1981, with the formal documentation of the study targeteu for April 2, 1981.
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-w Enclosure 5 Item 6 Compliance with 10 CFR 50 Appendix G(5.3)
- The response to this item can be divided into two parts
(1) those requirementsf. stated'in the current provisions of 10 CFR 50 Appendix G which can not be met due to the change in code requirements ~since component purchase, and as such require an exemption from current rules; and (2) full documentation of the i L
bases for conformance to all other provisions.to 10 CFR 50 Appendix l G. !
With. regard.to the first class, Commonwealth Edison
. submitted in the~L. O. DelGeorge letter to B. J. Youngblood dated.
l February 18, 1981 information aadressing RPV materials. This j information wiLil be formally documente'd in FSAR~ Amendment 56. )
Gith respect to the second. class, Commonwealth Edison has initiated the~ record retrieval and accumentation program necessary
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-to confirm.that no exceptions are required. It is worth pointing out that the regulations do not demand submittal of this information' 'The NRC Staff request.for this information in February, 1981.is a review ratchet that will be dificult to L accommodate quickly. The same. personnel are' heavily involvea in I retrieving and summarizing records relat,ed to the safety-related I. equipment environmental qualification and this work currently is )
assigned the highest priority. '
Although we will submit a-detailed schedule for completion of the Appendix G work by April 15, 1981, depending upon the depth of reporting requireo, this program could take as much as 90 days.
Your assistance in minimizing unnecessary effort would be grectly apprec t'a teo .
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Enclosure 6 Item 7. Criterion 51 of the General Design Critiera (6.2.7)
This program, as first discussed with the NRC Staff on February 6, 1981, is scheduled to be completed by April 10, 1981.
Therefore, we expect to provide the requested assessment accumentation on or betore April 15, 1981.
e 1665B
l Enclosure 7 I
Item 8. Review of Independent [nspection of Cable Routing (8.4.6) in response to the request for a 10% field audit of cable separation contained in Reference (a), and as committed by
' Commonwealth Edison in Reference (b), the results of the subject l Cable separation: audit'are attached. This audit reviewed a sample l consisting of approximately 10% of the total installed safety-related cables, associated cables and electrical equipment at LaSalle County Station, Unit 1. Specific cables and equipment selected for audit and the criteria to be used to assess the adequacy of the. Installed cable and equipment was delineated by the Architect-Engineer, Sargent'& Lunday ($&L). the actual audit was i performed under the auspices at the Commonwealth Eaison Quality Assurance Department with the technical assistance of S&L represent atives f amiliar with electrical design but not involved in
'the' design.of LaSalle County Station. The actual audit plan is providea as Attachment E7-1.
i The results of the audit were documented in Commonwealth l Eaison-LaSalle County. Audit No.-1-80-63, the aetails of which are on I file at.the. plant site. Included in Attachment E7-2 is a summary of l the auait'results'as well as the engineering evaluation of those results.- This attachment is judgec to provide the necessary documentation to resolve the subject open item.
Peoples dated 1 Referencts (1): .8. J. Youngblood letter to D. L.
May 7, 1980.
(2): D.L. Peoples letter to 3. J. Youngblood cated May 27, 1980 i
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Attachment E7-2 LaSalle County Unit 1 Separation Aucit 1-80-63 Summary of desults The audit conducted involved 398 Class lE cables, and conduit and 384 associated cable and conduit.. The audit. included a review of these cables for separation and markings as well as related termination requirements; and involved in excess of 10% of the-total-cables included in the 22 safety-related systemse selected for audit.
The audit resulted in 3 f indings and 1 observation all of ,
I which were' determined upon investigation to be of an insignificant nature. 'These results,Lthe subsequent evaluation performea and !
subsequent actions taken are providea in LaSalle-Q.A. Surveillance
. Report tio. 81-79, 81-94, 81-97 and 81-101 which are attached.
It should be clearly noted that after_ this very thorough:
aucit only one-(1) verified violation of established separation criteria was. identified. This isolated deficiency, discussed in greaterfdetail in Surveillance Report No. 81-97 has been corrected.
the' remaining deficiencies can be broken down into three categories, all effecting cable or conduit marking: (1) correctible deficiencies due to broken, misplaced, illegible or improperly taged components; (2) apparent deficiencies resolved after engineering review 1to be within the established aesign criteria; such as tag location on flexible conduit, associated cable taping and associated cable bu idling; ano (3) auditor errors reconciled after resurveillance.
The verified deficiencies, being all related to cable marking do not effect the safe operation of the plant. oCumulatively the deficiencies represent a very small percentage of the total sample addited. Augmented QC surveillance prior to system turnover as & part of the final system walkdown which precedes plant 5tartup will identify all other deficiencies of this type. However, resciution af such deficiencies, though expected prior to fuel loacing will be accomplished as soon as possible. Because caole marking aeficiencies alone do not effect the safe operationa+.e- of the olant, it is judged that such deficiencies can De-remedied fuel load out prior to full power operation.
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