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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 05000373/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal1999-05-0707 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal ML20206K7081999-05-0707 May 1999 Forwards 10CFR50.46(a)(3) Rept Re Significant Change in Calculated Pct.Loca Analyses for Both GE Fuel & Siemens Power Corp Fuel Demonstrates Results within All of Acceptance Criteria Set Forth in 10CFR50.46 ML20206K1861999-04-30030 April 1999 Informs That in Comed Submitted Annual Exposure Rept for Personnel Receiving Greater than 0 Mrem/Yr Rather than 100 Mrem/Yr.Updated Rept Limiting Data to Personnel Receiving Greater than 100 Mrem/Yr,Attached ML20206R0751999-04-30030 April 1999 Forwards License Renewal Applications & Certification of Medical Examinations for LaSalle County Station Personnel Whose Licenses Expire in Nov.Personnel Listed.Without Encls ML20206F0931999-04-30030 April 1999 Forwards LaSalle County Nuclear Power Station,Units 1 & 2 Effluent & Waste Disposal Semi-Annual Rept for 1998. LaSalle County Station Tech Specs Recently Revised to Reduce Periodicity of 10CFR50.36a ML20206D5921999-04-28028 April 1999 Forwards Annual Environ Operating Rept for 1998 for Environ Protection Plan, for LaSalle County Station,Units 1 & 2. Rept Includes Info Required by Listed Subsections of App B to Licenses NPF-11 & NPF-18 ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205L8161999-04-0808 April 1999 Advises NRC of Util Review & Approval of Cycle 8 Reload Under Provisions of 10CFR50.59 & Transmit COLR for Upcoming Cycle Consistent with GL 88-16.Reload Licensing Analyses Performed for Cycle 8 Utilize NRC-approved Methodologies ML20205J9451999-04-0505 April 1999 Submits Petition Per 10CFR2.206 Requesting That LaSalle County Nuclear Plant Be Immediately Shut Down & OL Suspended or Modified Until Such Time That Facility Design & Licensing Bases Are Properly Updated ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207J9841999-03-0505 March 1999 Informs That Effective 990212,KC Dorwick Has Resigned & No Longer Requires Use of NRC License for LaSalle County Station ML20207F9581999-03-0101 March 1999 Requests That Initial License Examination Currently Scheduled for Weeks of May 15 & 22,2000 Be Changed to Weeks of Nov 13 & 20,2000.Class Size Is Projected to Be Twelve RO & SRO Candidates ML20207C7251999-03-0101 March 1999 Forwards Annual Rept for LaSalle County Station, for Period of 980101-981231.App E to Rept Provides Info on All Personnel Receiving Exposures of More than 0 Mrem/Yr Rather than 100 Mrem/Yr Requirement of TS 6.6.A.2 ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207C8401999-02-25025 February 1999 Forwards Rev 60 of Comed LSCS Security Plan,Iaw 10CFR50.4(b) (4).Rev Eliminates Requirement for Annual change-out of Vital & PA Keys & Locks & re-configuration of PA Fence Around North Access Facility.Rev Withheld ML20207A9361999-02-24024 February 1999 Forwards Rev 4 to Restart Plan,To Reflect Review,Oversight & Approval Process Necessary to Restart Unit 2.Review & Affirmation Process Will Focus on Station Capability to Support Safe Dual Unit Operations 1999-09-30
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- f Commonwealth IMiv>n Company j.I
- l2Salle Gencrating Station 2601 North 21st Road
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- j. Tel HI43574,761 j '
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~i February 27,1996 i
j United States Nuclear Regulatory Commission
! Attention: DocumentControlDesk j Washington, D.C. 20555 4
j
Subject:
LaSalle County Station, Units 1 and 2 j Supplemental Response to Electrical Distribution System 1
Functional inspection (EDSFI) Reports 50373/91019 and 50
. 374/91019 l Deviation 373/91019-05D and 374/9101H5D on Degraded
{ Voltage Setpoint Methodology i Deviation 373/91019-05D and 374/9101906 on 4160 Volt l
< Degraded Voltage >
)
Request for Schedule Extension NRC Docicet Nos. 50-373 and 50-374 i
i
References:
- 1. T. J. Kovach letter to USNRC dated January 16,1992, l transmitting response to NRC Inspection Reports 50 373/91019 and 50 374/91019 regarding the Electncal Distribution System Functional inspection (EDSFI) EDSFl report.
- 2. T. J. Kovach letter to USNRC dated April 30,1992, transmitting supplemental response to the subject unresolved item. j i
- 3. T. O. Martin (USNRC) letter to LO. DelGeorge dated March 12,1993, transmitt'ng ; inspection Report Nos. 50-373/93002 and 50 374/93002.
- 4. M. B. Depuydt (CECO) letter dated June 22,1993, to T.E.
Murley (USNRC) transmitting supplemental response to the subject unresolved item.
- 5. G. G. Bones (Comed) letter dated January 27,1994, to T.E. Murley (USNRC) transmitting supplemental response 110049 to the subject unrosoived item.
9603110613 960227 PDR ADOCK 05000373 G PDR j / ]l A Unicom Company j
- 1 In reference 5 LaSalle County Station provided a '::44:=> and status of the degraded voltage modsfications that were required to resolve the subject EDSFl Unresolved item. In this letter LaSalle County Station also committed to complete the 120 VAC distribution circuit modifications on each unit prior to startup following the respective seventh refueling outage and to complete the remaining 480 VAC equ'pment modifications on each unit during the respective sixth refueling outage.
In addition, LaSalle County Station committed in reference 1 to complete tne corrective actions required to resolve the deviation on the degraded voltage setpoint methodology per the same schedule as the degraded voltage moddications. As indicated in our original response, the " permanent" degraded voltage setpoint con not be implemented until the degraded voltage "hardwars" modifications are implemented.
The purpose of this letteris to:
- 1. Revise the commitment date for completion of the Unit 1 distnbution circuit modifications to the same commitment date as the Unit 2 distribution circuit modifications, and clarify the list of 120 VAC distnbution circuits with voltage concems.
- 2. Provide a status of the degraded voltage modifications for the 480 VAC equipment.
- 3. Revise each unit's commitment date for completing the degraded voltage setpoint change to the first refueling outage following the approval of the Technical Specification amendment for revising the trip setpoint and allowable value.
The statur of the degraded voltage design changes and the justification for the schedule changes are provided in the following attachments:
- 1. Attachment A summarizes the scope of work, status, and schedule of the 120 VAC distribution circuit modifications. In summary, the modifications for both Units 1 and 2 are scheduled to be completed during or prior to the Unit 2 seventh refueling outage.
- 2. Attachment B provides the status of the 480 VAC equipment modifications. In the previous correspondence (ref. 5) LaSalle County Station reported that all degraded voltage modifications required for the motor control circuits and 480 VAC equipment had been completed except for two (2) 480 VAC equipment changes. As noted in this attachment, the remaining modsfications were completed on schedule.
- 3. Attachment C contains the justification for revising the schedule of the degraded voltage setpoint change as indicated above. The schedule requires revision because the final change to the degraded voltage trip setting at the
- 4160 voit level requires further analysis of the final plant configuration with the planned modifications, and a Technical Specification change is required prior to implementation. Although the degraded voltage setpoint will not be
i 1
i implemented in a timeframe commensurate with the original commitment, modifications to plant equipment to ensure adequate voltage to safety equipment under degraded voltage conditions will be completed by the end of the Unit 2 seventh refuehng outage. In addition, the final degraded voltage setpoint has been prehminary determined to be approximately the sann value as the current compensatory setpoint for the degraded voltage relays.
Please direct any questions you may have concoming this matter to this office. i Respectfully, ex R. E. Querio Site Vice President LaSalle County Station Enclosure cc: H. J. Miller, NRC Region til Administrator P. G. Brochman, NRC Senior Resident inspector- LaSalle C. Matthews, IDNS Resident inspector - LaSalle F. Niziolek, IDNS Senior Reactor Analyst INPO - Records Center D. L Farrar, Nuclear Regulatory Services Manager i
~. - _ .. . . . . - - - . - . - . - - - - . - . - - - . . - .
4 I l
. ATTACHMENT A Supplemental Response To inspection Report 5 4 373/91019;50 374/91019 Unresolved item 373/9101906; 374/9101906
. 120 VAC Distribution Circuit Modifications Description of Modifications The corrective actions that have been initiated for the 120 VAC distribution circuits with inadequate voltage at the degraded voltage setpoint consist of one or more of the following plant changes:
- 1. Tap changes of the === Maw 480120/208V distribution transformers to increase the voltage on the secondary side.
- 2. Increase in the size of the power supply cable to decrease the voltage drop between the bus and load.
- 3. Addition of voltage regulatmg transformers to the circuits. .
The 120 VAC distribution circuits which require modification are identified below:
Unit 1:
- 1. MCC 135X-1, ekt #5 - Post Accident Primary Containment Momtoring
- 2. MCC 135X-3, ekt #15 - Leak Detection
- 3. MCC 136X-1, ekt #5 - Post Accident Primary Containment Monitoring
- 4. MCC 136X-1, ekt #19 - SBGT Flow Control Damper 1VG002
- 5. MCC 136X-1, ekt #36 - Control Room HVAC
- 6. MCC 136X-2, ekt #5 - Process Radiation l I
- 7. MCC 136X-2, ekt #17 - Switchgear Heat Removal
- 8. MCC 136X-2, ckt #25 - Nuclear Boiler Process instrumentation
- 9. MCC 136X-2, ckt #29 - Post Accident Containment Monitoring *
- 10. MCC 136X-2, ckt #30 - Post Accident Containment Monitoring *
- 11. MCC 136X-3, ekt #7 - Leak Detecten Unit 2:
- 1. MCC 235X-1, ckt #5 - Post Accident Containment Mon;teiing*
- 2. MCC 235X-2, ckt #18 - Containment Monitonng
1 l
l ATTACHMENT A Supplemental Response To inspection Report 50-373/91019;50-374/91019 Unresolved item 373/9101906; 374/91019-06 120 VAC Distribution Circuit Modifications
- 3. MCC 235X-3, ckt #15- Leak Detection l l
- 4. MCC 236X-1, ckt #5 - Post Accident Primary Containment Monitoring i
- 5. MCC 236X-1, ekt #13 - SBGT Flow Control Damper 2VG002 j
- 6. MCC 236X-1, ekt #36 - Control Room HVAC l
MCC 236X-2, ckt #9 - Post Accident Containment Monitonng*
- 7. )
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- 8. MCC 236X-2, ckt #32 - Containment Monitoring l
- 0. MCC 236X-3, ekt #19 - Leak Detection The four circusts marked with an asterisk, ", were added since the previous correcpondence (ref. 5). These circuits were not included in reference 5 because the original analysis determined that the malfunction of the components with insufficient voltage in these circuits would only result in the loss of an alarm or monitoring function; components which perform a safety related function were calculated to have adequate terminal voltages. While this analysis is still accurate, it was determined that the alarm or monitoring function performed by these circuits is required by Reg. Guide 1.97.
In addition, one circuit - MCC 235Y-1, ckt. #16, RH Service Water Cubicle Vent Dampers - was removed because a detailed review concluded that the components in this circuit fail safe. Therefore, the components in this circuit are not required to operate following the Design Basis Accident (DBA).
The 120 VAC distnbution circuits listed above were determined to have adequate voltage to perform their safety-related function following an accident under the compensatory measures taken by the station in response to the degraded voltage issue. These compensatory measures are described in detailin reference 1.
Status of Modifications The design drawings for all the 120 VAC distribution circuit modifications have been issued, the design packages for the modifications scheduled to be installed during the l present Unit i refueling outage have been approved, and the voltage regulating transformers have been delivered to the station. The seismic qualification of these transformers has also been completed. However, the environmental qualification of this equipment is incomplete because an essential component failed during the simulated design basis accident test. Additional testing of this component is being performed by the vendor to resolve this problem, and this testing is scheduled to be completed by April,1996.
ATTACHMENT A Supplemental Response To inspection Repod 50 373/91019;50-374/91019 Unresolved item 373/91019-06; 374/91019-06 ,
120 VAC Distribution Circuit Modifications Justification For Schedule Chance i l
The design changes for the circuits of both units are scheduled to be implemented prior to startup following the Unit 2 seventh refueling outage which is currently plarsed for fall,1996.
The commitment date for completing the Unit 2 design changes remains unchanged, but the date for completing the Unit 1 design changes is being revised from the end of the Unit i seventh refuehng outage to the end of the Unit 2 seventh refueling outage. ;
However, seven (7) of the Unit 1 circuits listed above are scheduled to be modified 1 during the seventh refueling outage on Unit 1. The remaining four design changes (Unit 1 items 1, 3, 5, and 6 above) are currently scheduled to be installed in the period following the refueling outage.
Until these corrective actions are completed, the compensatory measures that were taken for the degraded voltage issue will remain in effect. Thus, extending the schedule for completing the Unit 1 design changes wiu not decrease reliabahty or safety I of the facility.
ATTACHMENTB Supplemental Response To inspection Report 50-373/91019; 50-374/91019 Unresolved item 373/91019-06; 374/91019 06 i Status of 480 VAC Eauloment Modifications l As indicated in reference 5, the degraded voltage concoms for the 480 VAC equipment (motors, heaters, battery chargers, etc.), except for the motor operated valves (MOV),
were resolved by initiating modifications to revise the 4160/480V transformer taps for the ESF Divisions 1 and 2 unit substations on both units to boost the secondary voltage by approximately 2.5% These modifications were compbted wding to the committed schedule (reference 5). No tap changes are required for the ESF Division 3 transformers, and no other design changes are required.
l The modifications that were required to resolve MOV voltage concems have been !
completed and are identified under the GL 89-10 program. j l
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ATTACHMENT C Supplemental Response To inspection Report 50 373/91019;50-374/91019 Deviation 373/91019-05D and 374/91019-05D Lack of Dearaded Voltaos Setooint Methodoloav Backaround:
During the 1991 LaSalle Electrical Distribution System Functional inspection (EDSFI),
compensatory actions were taken to ensure adequate motor starting and running
- voltages, and adequate voltage for the 120 Vac contactors to pick up, during a degraded voltage condition. These compensatory actions included a revised setpoint for the degraded voltage relays.
Summanr Prehminary setpoint calculations which address aN known instrument errors have been completed and indacate that the required lower analytical limit is 3814V. The cahbration setpoint was calculated to be approximately 3875V. These setpoint r=la d% are based on the installation of now, more accurate, undervoltage relays in the degraded voltage circuits in order to decrease the total instrument enor and improve the rehabihty of these circuits. The undervoltage relays on both units have been replaced in accordance with compensatory actions taken for the degraded voltage issue, the degraded voltage relays are currently cabbrated to trip at 3885V. Upon completion of the corrective actions required to close Unresolved item 373/9101906 and 374/91019-06, the setpoint for these relays will be revised as allowed by the setpoint =la daHans.
In reference 1 LaSalle County Station indicated that the schedule for finalizing the setpoint calculations and revising the degraded voltage setpoint is the same schedule that was provided for resolving this Unresolved item. Since the setpoint change can not be implemented until the degraded voltage trip setpoint and allowable value cpecified in the Technical Specifications are revised, LaSalle County Station is revising this commitment in the first refuehng outage following the approval of the Technical Specification amendment for revising the degraded voltage trip setpoint and allowable values. LaSalle County Station will need to update the voltage analysis deperWing on the performance of the voltage regulating transformer during the environmental quahfication testing. LaSalle plans to complete this analysis and submit the Technical Spec #i uon amendment by the end of first quarter 1997.
As indicated above, the final degraded voltage setpoint is not expected to be greater than the existmg cahbration setpoint, and the 120 VAC distnbubon circuit design changes described in Attachment A win be implemented prior to end of the Unit 2 seventh refuehng outage.
UntN these corrective actions are completed, the conpensatory measures win remain in effect, and completion of these schons win allow this Deviation to be closed.
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