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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
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Commonn calth lihuni (;ompan) 1;t5alle Gcncrating M.Hion lull North 2Ist Road M.irseilles, i1. 613 i 1 9'%'
Tel H 15-3 5"' 6~61 i
June 4,1997 l
l United States Nuclear Regulatory Commission l Attention: Document Control Desk
! Washington, D.C. 20555
Subject:
Commonwealth Edison Company (Comed) Response to l Nuclear Regulatory Commission (NRC) Generic Letter
! (GL) 96-06, " ASSURANCE OF EQUIPMENT l OPERABILITY AND CONTAINMENT INTEGRITY l DURING DESIGN-BASIS ACCIDENT CONDITIONS,"
l dated, September 30,1996.
LaSalle County Station, Units 1 and 2 Facility Operating License NPF-11 and NPF-18
. NRC Docket Nos. 50-373 and 50-374 l
References:
- 1. NRC Generic Letter 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS,"
dated, September 18,1996
- 2. John Hosmer Letter to U.S. NRC, Response to Generic Letter 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS,"
l dated, October 28,1996 i
- 3. John Hosmer Letter to U.S. NRC, Response to Generic Letter 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS," g dated, January 28,1997 -
[O'I d I 9706090139 970604 PDR ADOCK 05000373 h
1 l
- 4. John Hosmer Letter to U.S. NRC, Response to Generic Letter 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS," dated, May 2,1997 In the Reference 1 Letter the NRC staff notified all addressees about safety-significant issues that could affect containment integrity and equipment operability during accident conditions. In NRC Generic Letter 96-06 the l NRC staff required all addressees to submit within 30 days of the generic letter a written response indicating if the requested actions would be completed and submitted within the requested time period. Reference 2 transmitted Comed's 30 day response to the Generic Letter.
Reference 3 transmitted Comed's 120-day response summarizing our actions taken in response to the requested actions. In that letter Comed
! committed to provide additional details on implementing hardware changes at each of our sites. In ieference 4, LaSalle County Station restated that it would provide a detailed response by May 30,1997, which will describe the l analysis and any design changes required. On May 30,1997, we requested l
from the NRR Project Manager, an extension to our response submittal date to June 6,1997. This request was granted. These details for LaSalle County Station are provided in the attachment.
To the best of my knowledge and belief, the information contained herein is true and accurate.
l l If there are any questions or comments concerning this letter, please refer l them to Perry Barnes, Regalatory Assurance Supervisor, at (815) 357-6761, extension 2383.
! Respectfully,
)
l W. T. Subalusky Site Vice President LaSalle County Sta Enclosure l
cc: A. B. Beach, NRC Region Ill Administrator
- M. P. Huber, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle F. Niziolek, Office of Nuclear Facility Safety - IDNS R. Capra, Director of Directorate Ill-2, NRR B. Wetzel, Project Manager, NRR
r l
l l Le'.5alle County Station NRC Dockets 50-373 and 50-374 Response to NRC Generic Letter 96-06
" Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions", dated September 30,1996 Nuclear Regulatory Commission (NRC) Request:
l "Within 120 days of the date of this generic letter, addressees are requested to l submit a written summary report stating actions taken in response to the requested i l actions noted below, conclusions that were reached relative to susceptibility for l waterhammer and two-phase flow in the containment air cooler cooling water system and overpressurization of piping that penetrates containment, the basis for continued operability of affected systems and components as applicable, and ,
l corrective actions that were implemented or are planned to be implemented. If systems were found to be susceptible to the conditions that are discussed in this l generic letter, identify the systems affected and describe the specific circumstances l involved. " l l
NRC Requested Actions:
Addressees are required to determine:
(1) if cooling water systems serving the containment air coolers are susceptible to either waterhammer or two-phase flow conditions during either a loss-of-i coolant accident (LOCA) or a main steamline break (MSLB); and l
(2) ifisolated water-filled piping systems that penetrate the containment are l l susceptible to thermally induced overpressurization that could lead to a 1
breech of containment integrity via bypass leakage.
l 1
I s
Page 1 of 7
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l l
. . i l
( Response to item 1:
l The response to item 1 was previously provided in Comed's letter dated i January 28,1997 from John Hosmer to the U.S. NRC.
Response to item 2:
The potential for thermally-induced overpressurization exists when liquid-filled piping inside containment is isolated during a LOCA/MSLB. A review of all piping that !
penetrates containment was performed. This review identified the following systems as having liquid filled piping that may be susceptible to this phenonom:
t 1
l Low Pressure Core Spray i l High Pressure Core Spray Residual Heat Removal / Low Pressure Core injection Main Steam Drains Standby Liquid Control l Feedwater Residual Heat Removal / Shutdown Path Reactor Recirculation Loop Sampling Reactor Water Cleanup Reactor Core isolation Cooling Chilled Water Reactor Building Closed Cooling Water Reactor Recirculation Flow Control Valve Hydraulic Piping Residual Heat Removal Shutdown Cooling Control Rod Drive i 4
Currently both units at LaSalle County Station are shutdown. Unit 1 is in a forced outage and Unit 2 is in a refueling outage. Currently, there are no operability concerns due to thermally induced overpressurization, because primary containtnent integrity is not required under the current plants' modes. However, Operational Conditions 1,2, or 3 of Technical Specification 3.6.3 will not be entered until the design changes described below are implemented. Both Units are currently shutdown and have been
! shutdown since the issuance of the generic letter.
i Page 2 of 7 I
t . .
l A detailed screening was performed of the above systems to determine which systems l have containment valve arrangements that may be susceptible to thermal l overpressurization. Containment valve arrangements that utilize air operated, motor l operated, or solenoid operated inboard and outboard isolation valves were determined to be potential candidates. Check valves were excluded, because this type of valve would open and release the pressure increase prior to an overpressurization condition.
Containment valve configurations that utilized a manual valve on the inboard side of containment were excluded, because these valves are administratively controlled to be open during plant operation; therefore, the overpressurization condition would not occur. l Several penetrations were determined to be susceptible to the overpressurization conditions as discussed in the generic letter. The penetration descriptions are as follows and are applicable for Units 1 and 2:
Penetration Number Description M-25, M-26, M-27, M-28 Supply & Return Chilled Water piping for the Primary Containment Ventilation Heat Exchanger Coil l
M-16, M-17 Supply & Retum Reactor Building Closed Cooling Water Piping for the seals of the l Reactor Recin alation Pump l M-7 Residual Heat Removal (RHR) Piping shutdown cooling mode RHR Pump Suction Piping from Reactor Recirculation M-49, M 50 Reactor Recirculation Flow Control Valve Hydrau!!c 90ing I
M-30 Suction Fi: ig to the Reactor water Cleanup (RT) Recirculation Pumps M-36 Reactor Recirculation Sample Line Piping These penetrations generally have a containment isolation valve on each side of the containment wall which is either open or closed during normal plant operation and automatically closes on a containment isolation signal. These penetrations could be potentially heated during a LOCA or a MSLB inside containment, either of which would provide the containment isolation signal.
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. It has been shown via generic analysis performed for Comed Nuclear Plants that the ]
l piping stress design allowable will be exceeded and permanent strain may develop however, ultimate strength for the materials involved would not be exceeded, if no l
l changes to the piping systems were implemented. The piping would maintain its !
structural integrity. Pressure relief would occur through the weakest link, which was I
determined to be the valves in the system. Pressure relief would occur through the valve seat, packing, or body to flange gaskets. There are two valves used for primary )
containment. Either the inboard or outboard valve seat, packing, or body to flange gaskets will be the weak link and the other valve will maintain primary containment. .
Based on the above discussion the penetrations will continue to maintain pressure ;
under accident conditions and will remain operable. ;
An extensive review of the isolated piping sections that affect the containment integrity was performed and corrective actions are being determined. LaSalle intends to install physical changes such as drilling holes in the valve disc, adding a relief vane, or a '
rupture type disc chamber configuration in selected applications that provide overpressure protection prior to unit startup.
Overview Methodology l
A series of thermal transient analysis to determine the expansion rate of entrapped fluid I
was performed. The pipe segments to be analyzed penetrate the containment and are .
isolated during a Design Basis Accident. The postulated pipe breaks that were l considered in the analysis include the recirculation line break, a main steam Ine break, and a small bore high energy line break. The bounding temperature profile occurs from a high energy line break in the reactor recirculation piping. However, afier a period of time the smallline break becomes the bounding temperature. Therefore the temperature profile for the reactor recirculation break with a current LOOP and the ,
2 0.1 ft I quid line break were both analyzed to determine the worst case scenario. Once l a bounding containment profile was determined, the remainder of the analysis was divided into three sections: (1) the calculation of the outside heat transfer coefficient using the Uchida approximation, (2) the calculation of the inside heat transfer coefficient by free convection, and (3) the calculation of the volumetric expansion of the water resulting from the corresponding heat transfer rates.
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A' summary of each affected penetration is provided below:
Penetration M-36; Reactor Recirculation Sample Line Piping This penetration is bounded by the Recirculation System Sample Valves B33-F019 and B33-F020. Valve F019 is located inside containment and F020 is located outside containment. During normal plant operation, the isolation valves are open and the line has continuous flow. As a result the piping will be normally hot. These valves would be ,
expected to close due to a Group 1 isolation signal during a LOCA or MSLB; however, !
thermal pressurization of the isolated volume would not be expected due to its higher l initial temperature.
, if the line is isolated for any reason prior to a LOCA or MSLB, the containment isolation
- valves and piping between them will cool down and the isolated volume may be
! susceptible to thermally induced pressurization.
1 Corrective Actions: j 1
A design change will be implemented to provide a pressure relieving device for this l l volume prior to startup. !
\ l l Penetration M-30; Suction Piping to the Reactor Water Cleanup (RT) Recirculation l Pumps )
The section of the RT piping that may be susceptible to thermally induced i pressurization due to post-LOCA or MSLB heat-up is the containment penetration '
piping located between valves G33-F001 and G33-F004. Valve F001 is located inside containment and Valve F004 is located outside containment. During normal plant i operation the isolation valves are open and the line has continuous flow. As a result
' l the piping will be normally hot. If the isolation valves close due to a LOCA or MSLB, the i temperature of the isolated line would not be expected to increase due to its higher I initial temperature; and therefore, will not be subject to thermally induced l pressurization. l l
l If the line is isolated for any reason prior to the LOCA or MSLB, the containment isolation valves and associated piping will be cooler and the isolated volume may be susceptible to thermally induced pressurization depending upon the duration of isolation.
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. Corrective Actions:
A design change will be implemented to provide a pressure relieving device for this volume. Installation of this change will be completed prior to unit startup.
Penetrations M-16 and M-17; Supply & Return to the Reactor Building Closed Cooling Water Piping for the Seals of the Reactor Recirculation Pump These penetrations have motor-operated gate valves inside and outside containment.
The section of the RBCCW piping that may be susceptible to thermally induced )
pressurization due to post-LOCA or MSLB heat-up is the containment penetration piping located between supply valves WR029 and WR179 and return valves WR040 and WR180. Valves WR029 and WR040 are located outside containment and Valves
, WR179 and WR180 are located inside containment. The temperature of the supply 1 and return lines are significantly lower than the maximum containment temperature during a DBA or MSLB. Therefore, a pressure relieving device is required for this volume.
Corrective Actions: I A design change will be implemented to provide a pressure relieving device for this volume. Installation of this change will be completed prior to unit startup.
Penetrations M-25, M-26, M-27, M-28; Supply & Return to the Chilled Water Piping ,
for the Primary Containment Ventilation Heat Exchanger Colls j The primary containment penetrations associated with the chilled water pumps have motor operated gate valves on the outboard side of containment and motor operated butterfly valves on the inboard side. These sections of chilled water piping are susceptible to thermally induced pressurization. The specific piping susceptible due to post-LOCA or MSLB heat-up is the containment penetration piping located between supply valves VP063A and VP113A and VP063B and VP113B and retum valves VP053A and VP114A and VP053B and VP1148. The temperature of the supply and retum lines are significantly lower than the maximum containment temperature during a
, LOCA or MSLB. Therefore, a pressure relieving device is required for this volume.
Corrective Actions:
A design change will be implemented to provide a pressure relieving device for this volume. Installation of this change will be completed prior to unit startup.
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I Penetration M-7; Residual Heat Removal (RHR) Piping for Shutdown Cooling l Mode RHR Pump Suction Piping from Reactor Recirculation This penetration is bounded by the motor operated gate valves E12-F009 and F008.
Valve E12-F009 is located inside containment and F008 is located outside containment.
During normal plant operation, the isolation valves are closed and have no flow. As a result the piping will be normally cold. This section of piping is susceptible to thermally induced pressurization since it is significantly lower than the maximum containment temperature during a LOCA or MSLB Therefore, a pressure relieving device is required for this volume.
Corrective Actions:
A design change will be implemented to provide a pressure relieving device for this volume. Installation of this change will be completed prior to unit startup.
Penetrations M-49, M-50; Reactor Recirculation Flow Control Valve B33-F060 Hydraulic Piping These penetrations are bounded by solenoid operated valves that are open during normal plant operation. The affected piping contains Frequel EHC fluid. Frequel EHC is a synthetic phosphate ester fluid that looks and feels like a light mineral oil with good lubricating properties and excellent stability. This fluid is not to be confused with petroleum based hydraulic fluid. The fluid is fire resistant and can contain as much as 20% water during operation. Frequel consists cf 15 - 25% triphenyl phosphate,40 -
50% butylated triphenyl phosphate mixture, and 40 - 50 % trixylenyl phosphate. The ,
possible presence of as much as 20% water c:t/ersely affects the volumetric expansion j of this material. In determining the thermal relief rate for the isolated piping, the i volumetric expansion of pure water was used because of maximum expansion. !
The maximum operating temperature of the fluid per design in the affected piping is 150 F. This temperature is significantly lower than the maximum containment temperature a LOCA or MSLB. Therefore, a pressure relieving device is required for this volume.
Corrective Actions:
A design change is required to provide a pressure relieving device for this voiume.
However, it is not appropriate to relieve Frequel EHC insida the drywell. The appropriate fix for these penetrations has not been determined; but, will be impiemented prior to unit startup.
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