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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
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Text
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/^N Commonwealth Edison
) One First National Pina. Chicago. Illinois ypQ
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Address Reply to. Post Office Box 767
. Chicago. Illinois 60690 February 28, 1986 ?RIORITYRouTIigg
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Mr. James G. Keppler 01'NS h,r.h mr -
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Regional Administrator '-
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U.S. Nuclear Regulatory Commission MM 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
LaSalle County Station Units 1 & 2 Additional Information Regarding Plans and Programs to Upgrade Station Activities NRC Docket Nos. 50-373 and 50-374 Reference (a): C. Reed letter to J.G. Keppler dated February 4, 1986 (b): J. G. Keppler letter to C. Reed dated November 22, 1985
Dear Mr. Keppler:
Pclerence (a) transmitted Commonwealth Edison's response to your request for information, Reference (b), pursuant to 10CFR50.54(f), regarding Region III concerns involving the control of station activities at LaSalle County Station. Our response contained numerous commitments regarding station activities including many plans and programs to improve the station's control of work both prior to Unit 1 start-up and long term.
In a meeting with you and your staff on February 18, 1986 a number of questions were raised regarding our response. The purpose of this letter is to answer those questions. The Attachment to this letter addresses your concerns and should provide the necessary information to resolve the issues.
We believe this transmittal will satisfactorily answer all your questions regarding our 10 CFR50.54(f) response.
Very truly yours, M 9 $Lo,-J Cordell Reed Vice President
/klj I!56x ;!gg18au8t8%j; MAR 3 1986 P
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, i
S ATTACHMENT ISSUE: The olanned actions stated in our letter appear to be aoals/ expectations instead of formal commitments.
The planned actions stated in our letter are formal commitments. We believe the measures and actions make-up an aggressive, comprehensive program to improve station performance. We assure you that the described actions are being aggressively pursued. We would like to restate, however, that future reviews of these comunitments may reveal the necessity to make changes. If such-changes do become necessary, they will be reviewed with you or your staff for acceptability. To ensure a clear understanding of the commitments made to reduce the backlog of existing work, we have provided a list below:
Area of Concern Commitment Date
- 1. Non-outage Work Request Reduce backlog to 1400 Prior to Unit 2 Backlog Fall Refuel
- 2. SR, ASME, reliability- Reduce backlog to 300 Prior to Unit I related Work Request Backlog restart
- 3. Control Room Annuniciators Establish "blackpanel" One month after Unit 1 attaining full power
- 4. Control Room Work Request Reduce backlog to 20 Prior to Unit 1 restart Begin work next working day Completed No backlog relating to Prior to indicators / alarms used as: Unit 1
- degradation of reactor coolant press. boundary,
- initial condition in DRA anal.,
- pri indication of ECCS avail.
- 5. Modifications complete 82 Unit 1 outage Prior to Unit I related mods, startup.
Complete 22 high priority December 1986 non-outage related mods.
cont'd.
Area of Concern Commitment Date
- 6. Procedure changes Reduce backlog to 450 Prior to Unit 1 startup
- 7. On-site review Complete review to Prior to Unit 1 justify safe unit stkatup p'.artup ISSUE: Role of the Nuclear Safety Department Offsite Review function as related to the LaSalle County Unit I startup.
Offsite Review's normal duties require approval of safety evaluations for safety-related modifications, procedures, special tests and experiments and changes to technical specifications. LaSalle County Station also has a technical specification required Onsite Nuclear Safety Group (ONSG) of four personnel that perform the independent assessment of operational safety as required by NUREG-0731. Due to the problems experienced with the modification program in early 1985 at LaSalle County Station the ONSG has focused more effort on in-plant inspection of work in progress. This effort was implemented at both LaSalle and Byron in the summer of 1985. Since the present LaSalle Unit 1 outage represents the first major refueling outage at the Station, the Nuclear Safety Department will participate in the Onsite Review meeting concerning the readiness of the unit to return to service. In addition to this Nuclear Safety Department personnel including members of the ONSG will review the safety-related modifications performed during the outage and more importantly, verify that the existing management controls for modifications are adequate. The specific controls to be reviewed include the first and second level review programs implemented to provide reasonable assurance that modifications are installed, tested, documented and placed in service according to station procedures. In addition Nuclear Safety Department personnel will verify that the personnel assigned to perform modification work clearly understand the program and their responsibilities.
ISSUE: Rationale for not having procedure changes. associated with modifications.
completed prior to declaring the equipment operable.
Procedure revisions associated with modifications are classified by the cognizant sngineer as required or not required, prior to declaring the equipment operable in secordance with LAP 1300-2, " Plant Modifications". This designation is reviewed by 1 the Technical Staff Supervisor and an Operating Engineer during the modification l cpproval process. Any procedure revision which impacts on the operation of the squipment or which has reasonable potential for confusing or misleading personnel -
using the procedure is required prior to declaring the equipment operable.
Procedure revisions not required prior to declaring the equipment operable are ccheduled for completion within 30 days of modification completion. !
Examples of procedure revisions not required prior to declaring the equipment operable are as follows:
1
- 1. Surveillance procedures for surveillances that will not be performed within 30 days.
- 2. Revisions to Hathaway Alarm Typer Point numbers which do not change the print-out message.
- 3. Removal of a precaution that is no longer necessary but which has no potential for causing an incorrect action.
ISSUE: If the Majority of Safety-Related. ASME Code-related and reliability-related work requests are typified as repair / return to storeroom, weld repairs on non-safety systems and other work not impacting safety, how are the remainder of the work requests typified.
Typical examples of work requests included in the 300 Code, Safety and reliability work requests which will not be completed prior to Unit 1 startup are as follows:
Circuit board repairs which will be returned to stores; welding jobs on plant cquipment, reactor water cleanap valve repair work requests awaiting parts delivery, spare control rod drive rebuild work requests, rebuild work requests for various ITT damper actuators throughout the plant, rebuild work requests for valve motors and limitorques being returned to Stores, various work requests for fire protection in out building warehouses and solenoid valve repairs for return to Stores. All 300 outstanding work requested are typified above. There is not a remaining number of work requests in other categories. The statement in our letter used the term " majority". It could have said "all". In summary, 45 percent of the cubject work requests are repairs for return to Stores, 40 percent are welding jobs cnd 15 percent are Safety related or Code work requests which are not critical to plant operation, i.e.
- 1) ASCO valve repair for spares,
- 2) Fuel pool clean up valve packing and actuator repairs,
- 3) Water tight door improvement / awaiting parts,
- 4) Control Rod Drive rebuilds (spares).
- 5) RHR vent valve local indication,
- 6) Rebuild ventilation damper actuators.
ISSUE: Completion of High Priority Hodifications extend through end of 1986.
The "high" priority classification was assigned to these modifications to indicate that they should be scheduled for completion before those modifications classified in the " medium" or " low" priority classifications. The following list summarizes the scope and the expected installation schedule for the twenty-two "high" priority modifications. Eight of the twenty-two modifications are classified as
cafety-related because at least a portion of the modification pertains to cafety-related structures or components. None of these modifications represents a cafety concern.
- 1. 1-0-81-025; This modification installs a time delay relay in the pump auto start circuitry for the Security Diesel Generator Day Tank Makeup Pump. This modification is non-safety related. It will provide an alarm only when the makeup pump fails to start or restore day tank level in lieu of the current arrangement which causes an alarm every time the pump starts.
Scheduled Installation: October 1986
- 2. 1-0-82-121; This modification provides in place backwash capability for Condensate Polisher strainer OCP01M. It is non-safety related and eliminates a repetitive maintenance problem.
Scheduled Installation: October 1986
- 3. 1-0-83-019; This modification provides a method for draining water that accumulates inside the curbing surrounding the Electrode Boilers. It is non-safety related and eliminates a recurring housekeeping problem. INPO concern.
Scheduled Installation: May 1986 (75% complete)
- 4. 1-0-83-022; This modification moves the Radwaste Discharge Process Radiation Monitor Skid from the Valve House to the Turbine Building. This modification is safety related. It will eliminate past problems with freezing of the sample lines and a potential contamination problem in the Valve House (Offsite Area).
Scheduled Installation: May 1986 (95% complete).
- 5. 1-0-84-005; This modification provides permanent heat tracing for the stack i isokinetic probe. It is non-safety related and is intended to replace the current temporary heat tracing. The current temporary arrangement works well and has eliminated the freezing problems experienced with this line in past winters.
Scheduled Installation: May 1986 4
- 6. 1-0-84-058; This modification revises the water /cludge interface r instrumentation on several Radwaste vessels. It is non-safety related. The current instrumentation has performed very poorly and has resulted in tank overflows and large area contaminations.
Scheduled Installation: December 1986 (tentative)
This is a major job. An exact date for completion cannot be determined at this time.
- + - - , - - . , , - - - - ,- , , . . , - - , -
t
~5-
- 7. 1-0-84-060, 1-0-85-011, 1-0-85-014; These modifications concern ... j installation of the Interim Radwaste Storage' Facility (IRSF). i They are all non-safety related. l Scheduled Installation: August 1986
- 8. 1-0-85-019, 1-0-85-020; These modifications provide for installation of
-additional Chlorine detectors, replacement of existing Chlorine detectors with a more reliable model and modification of the '
trip logic for initiation of the Control Room Ventilation System Emergency pressurization Mode to tolerate a single failure or spurious signal. They are safety related. These modifications represent a backup contingency plan in the event the Technical Specification change to remove these detectors is not approved.
Modifications are expected to significantly reduce unnecessary ESF actuations.
Scheduled Installation: July 1986 or as soon thereafter as possible if the modification proves necessary.
- 9. 1-0-86-001; This modification provides for replacement of the low oil pressure switches on the Auxiliary Electric Equipment Room Ventilation System compressors. It is safety related. The current model switch is no longer manufactured.
Scheduled Installation: July 1986
- 10. 1-0-86-002; This modification provides for installation of local audible alarms on High Radiation Doors. It is non-safety related. It is expected to assist in resolving LaSalle's problem with respect to High Radiation Doors being inadvertently left open or unlocked.
Scheduled Installation: June 1986
- 11. 1-1-82-249; This modification adds a time delay for the alarm on the-watertight door to the Unit 1 Residual Heat Removal Service Water pump room. It is non-safety related and provides for elimination of a nuisance alarm.
Schedule Installation: March 1986
- 12. 1-1-83-088; This modification provides for revision to the Control Room Breathing Air System. It is non-safety related. The current isolation valves are prone to leakage and isolation valves are not provided for individual bottles. The modified arrangement will make the system much easier to maintain.
Scheduled Installation: September 1986
r-t t
- 13. 1-1-84-108; This modification provides for installation of a larger strut assembly on a Service Water line that is experiencing vibration problems. It is non-safety related.
Scheduled Installation: June 1986
- 14. 1-1-85-027, 1-2-85-034; These modifications replace the Standby Gas Treatment high flow alarm switches with dual setpoint switches.
The current low flow alarm is provided for heater protection and is set too low to warn of a potential Technical Specification violation. These modifications are safety related.
Scheduled Installation: August 1986
- 15. 1-1-85-049; This modification revises the probe data processor so that the control rod full in light works off either the 00 or Full In reed switch. Aids the operator in determining that all rods are in following a scram. This modification is safety related.
Schedule Installation: March 1986
- 16. 1-2-84-078; This modification puts an instrument snubber in the sensing line for the Fuel Pool Cooling pump low suction pressure switch.
Currently the pump trips when started due to pressure surges.
This modification is non-safety related.
Scheduled Installation: June 1986 17 1-2-84-187; This modification changes the Vent and Purge System flow transmitter from a Hays Republic Model 252A to a Validyne Model P232A. The current model has proven to be unreliable. This modification is non-safety related.
Scheduled Installation: June 1986
- 18. 1-2-86-002; This modification installs High Density Fuel Racks in the Unit 2 Fuel Pool to increase storage capaci6y. This modification is safety related.
Schedule Installation: August 1986 This date is extremely tight. If the modification cannot be installed prior to the Unit 2 refuel outage, it will be postponed to a later date. The additional storage capacity will not be required for several years.
).
ISSUE: Residual Heat Removal Service Water Pumps There are fifteen (15) pump motors in the subject areas which could be subject to failures similar to those experienced with the Residual Heat Memoval (RHR) Service Water pump motors. There are eight (8) RHR Service Water pumps, five (5) Diesel Generator (DG) Cooling Water pumps, and four (4) Fuel Pool Emergency Makeup pumps located in this area. The two (2) Diesel Generator Cooling Water pump motors for i
the HPCS Diesel Generators, although located in the subject areas, are sealed j motors manufactured by General Electric and are not believed to be susceptible to j this type of failure. All motors believed to be subject to failure were
- manufactured by Reliance.
1 The majority of problems experienced have been with the RHR Service Water pump motors. All eight (8) of these motors have been rewound since the construction 2
period when the potential for cement dust intrusion existed. This problem is considered resolved for these particular motors.
l With regard to the Diesel Generator Cooling Water pump motors, two of the motors susceptible to this problem have been rewound. The motor for the 2A Diesel Generator (2DG0lP) has not been rewound. This motor will be replaced with a rewound motor prior to December 1986. The long time frame for this motor is based on a 26 week delivery time for obtaining a spare motor.
I The 2A diesel generator, including the 2A diesel cooling water pump, is tested at least every 31 days in accordance with the Technical Specifications. To date, i there have been no failures of the 2A diesel cooling water pump motor (original I
motor installed).
1 i Four diesel generators are required by Tech Spec 3.8.1.1 for Unit 2 operation (0, 2A, 2B and 1A). A failure of the 2A D/G Cooling Water pump would pose no
! oignificant threat to our ability to safely shutdown Unit 1 or 2, based on:
! 1) The favorable operating history of the offsite power system and the diesel
- generator, j 2) The number of available paths to the onsite power buses from the offsite sources and, i
j 3) The fact that one ESF division can safely shutdown the unit for a loss of offsite power.
We believe the probability of failure of this motor during the remainder of 1986 is 4
relatively low. Should a failure occur, the requirements of the Technical Specification action statement for an inoperable Diesel Generator will be implemented.
)
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