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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] |
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. n. ~ , .
l e C:mm:nwnith Edison !
. -i 1400 Opus Place l Downers Grove. Illinois 60515 i
i August 4,1993 ,
Dr. Thomas E. Murley Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
LaSalle County Station Units 1 and 2 <
In-Service Inspection Program Submittal of Relief Requests RI-24,-25,-26,-27 and-28 Docket Nos. 50-373 and 50-374
Dear Dr. Murley:
LaSalle County Station performs pressure tests in accordance with ASME Section XI,1980 Edition, Winter 1980 addenda. The enclosed relief requests address section IWD-5223. IWA-5211, IWB-5221, IWA-4400, IWA-5241 i and IWD-5223 for various ;ppbcation of pressure tests. Alternative testing is i proposed for each of the se-tiens as described in the attachments to this letter.
IWD-5223 requires Class 3 systems be subjected to elevated pressure hydrostatic tests. Relief Request RI-24 requests to change this to function or in-service tests.
IWA-5211 and IWB-5221 requires Class 1 systems be subjected to an ,
Operating Pressure Test after disassembly and reassembly of mechanical 1 connections. Relief Requests RI-25 seeks to change this test to 920 psig during start-up for un-isolable Class 1 connections in the drywell. '
IWA-4400 requires that an elevated pressure hydrostatic test be performed after welded repairs or replacements. . Relief Request RI-26 seeks to change this to a nominal operating pressure test for Class 1 and 2 systems. l r
l 9308100122 930eo4 P ,
Ii gDR ADOCK-05000373 fj 1 ,
PDR jgj ;
?
, 4 l
Dr. Thomas E. Afurley August 4,1993 IWA-5241 requires the VT-2 examination ofinaccessible components to consist of an examination of the surrounding area (floor and surface under the l components) for evidence ofleakage. Relief Request RI-27 proposes an alternate method of monitoring the radiation levels in the tube side of the RHR Heat Exchanger in lieu of an exam under the Heat Exchanger. i IWD-5223 requires a 90% of the pipe submergence head of water pneumatic pressure test on safety and relief valve piping discharging into the - i suppression pool. Relief Request RI-28 requests relief from performing this test -i due to the hardships in set-up and performance. The results of the tests are not l meaningful since the design pressure is 600 psi and actual test pressure would be .
3-5 psi. !
These relief requests would alter only the type of pressure tests reauired by ash 1E Section XI. This submittal provides methods for alternate monitoring to assure the piping systems have maintained their structural ,
integrity. These alternative testing methods do not introduce any new failure modes.
- Relief Requests RI-24, RI-25, RI-26, RI-27' and RI-28 are applicable to ' i both Units 1 and 2. Commonwealth Edison requests approval of this relief .i request to support the planning and preparation phases of the proposed ;
alternative tests. It is requested that the proposed relief requests be approved by i October 4,1993. In addition, it is requested that the relief extend through the !
remainder of the first 10 year Inspection Interval, which will be completed after ;
each Unit's sixth refueling outage.
Please contact this office should further information be required. ;
Respectfully, j
/
Y ,
eter L. Piet i Nuclear Licensing Administrator ;
Attachments: Relief Requests RI-24, RI-25, RI-26, RI-27, and RI-28 for ,
LaSalle County Station ec: J.B. A1artin, Regional Administrator-RIII ;
J.L. Kennedy, Project Afanager-NRR ;
D. Hills, Senior Resident Inspector-LSCS ,
Office of Nuclear Safety-IDNS .
.i l
REUEF REQUEST NUIVEER RI-24 (Page 1 of 2)
GQNERNENT_ IDENTIFICATION Code Class: 3
Reference:
Table IWD-2500-1, and IWD-5223(a)
Examination Category: D-A, D-B, and DC ltem numbers: D1.10, D2.10, and D3.10
Description:
Altemate Testing of Class 3 Systerns in Lieu of Ten-Year Hydrostatic Pressure Testing Component Numbers: Various CDDE REQUIREMENT ASME Section XI, Table IWD-2500-1 requires Class 3 pressure retaining components be exposed to VT-2 examinations while the systems are subjected to elevated pressure hydrostatic tests, at or near the end of each inspection interval.
ASME Section XI, IWD-5223(a) states that the system hydrostatic pressure shall be at least 1.10 times the system pressure Psv for systems with a design temperature of 200 F or less. It also states that the system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for over-pressure protection within the boundary to be tested (or, design pressure Pdif over-pressure protection is not provided).
BASIS FOR REUEF Elevated pressure tests are difficult to perform and often represent a true hardship.
Some of the difficulties associated with elevated pressure testing include the following-
- Hydrostatic testing often requires complicated or abnormal valve line-ups in order to properly fill, vent and isolate the components requiring testing.
- Relief valves with set-points lower than the hydrostatic test pressure must be gagged or removed and have blind flanges installed. Bis process requires draining and refilling the system.
- Valves that are not normally used for isolation (e.g., normally open pump discharge valves) are often required to provide pressure- isolation for an elevated pressure hydrostatic test. These valves frequently require tirne consurring seat maintenance in order to allow for pressurization.
. REUEF REQUEST NUNBER RI-24 (Page 2 of 2)
IMSIS FOREEUEE (Continued)
- The radiation exposure required to perform a hydrostatic pressure test is high (in comparison to an operational pressure test) due to the large amount of time required to prepare the system for testing (i.e. installing relief valve gags, installing blind flanges, perforrnir.g appropriate valve line-ups, etc).
He difficulties encountered in performing a hydrostatic pressure test are prohibitive when weighed against the benefits. Industry experience shows that most through wall leakage is detected during system operation as opposed to during elevated pressure tests such as the ten-year hydrostatic tests.
Little benefit is gained from the added challenge to the piping system provided by an elevated pressure hydrostatic test (when compared to an operational pressure test).
The piping stress experienced during a hydrostatic test does not include the significant stresses associated with the thermal growth and dynamic loading associated with design basis events.
These arguments are supported by the adoption of Code Case N498, "Altemate Rules for 10 Year Hydrostatic Pressure Testing for Class 1 and 2 Systems,Section XI, Division 1" This relief request is a natural extension of that Code Case.
Based on the above LaSalle County Station requests relief from the ASME Section XI requirements for performing the ten-year elevated pressure hydrostatic tests on class 3 systems.
PROPOSED ALTERNATE EXAMNATION ,
A VT-2 examination will be performed durir either a system functional test or during a system inservice test, in accordance with me requirements of IWA-5213 (b) and (c) respectively, at or near the end of the inspection interval, prior to reactor startup.
AEELLCAEILE_I]ME PERIOQ ,
Relief is requested for the first ten-year interval of the System Pressure Testing Program at LaSalle County Station Unit 1 and 2.
1
REUEF REQUEST NUNEER: RI-25 i (Page 1 of 2) :
i GQNPONENTIDENTIFICATION 1 Code Class: 1 1
References:
IWA-5211(a) !
IWB-5221(a) !
Examination Category: B-P ltem Numbers: B15.10 to B15.71.
Description:
System Leakage Test Pressure for the Disassembly and .l Reassembly of Class 1 Mechanical Connections. 1 Component Numbers: Various
. GODE REQUIRENENTS :
r IWA-5211(a) requires a system leakage test to be conducted following the opening !
and re-closing of a component in the system after pressurization to nominal operating j pressure. !
i IWB-5221(a) states that the system leakage test shall be conducted at a test pressure i not less than the nominal operating pressure associated with 100% rated reactor !
power. j i
BASIS FORREllEE .!
The norrinal opuating pressure associated with 100% rated reactor power is 1,020 psig. Near the end of each refueling outage, a system pressure test of all Clar.s 1
. pressure retaining components is conducted at 1,020 psig.
Subsequent to the system pressure test conducted during a refueling outage, or during !
forced maintenance outages which can occur during an operating cycle, it may
- become necessary to disassernble and reassemble Class 1 mechanical connections that are located in the drymil and cannot be isolated from the reactor vessel. For- r these situations, the performance of a Class 1. system leakage test at 1,020 psig - l would have a significant impact on the unit's critical path outage time and personnel j exposure.
r The normal Class 1 system pressure test, which is performed with the vessel flooded i up, requires numerous equipment outages (e.g.,- 380 valves must be taken out-of- j service). Performance of the equipment outages, coupled with the performance of the i system leakage test, takes approximately 5 days (3 shifts per day) with a total l personnel exposure of approximately 2.5 Man-Rent !
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REUEF REQUEST NUNBER: RI-25 ,
(Page 2 of 2)
BASLS FOR REUEF (Continued)
Pdormance of a system leakage test during normal startup is possible, however, the test can not be perfonned at 1,020 psig. During unit startup, the Electro-Hydraulic Control System precludes a reactor pressure above 950 psig without significant increases in reactor power. In order to achieve a pressure of 1,020 psig, the reador would have to be at approximately 100% rated power. The radiation levels in the drywell at this power level are prohibitive, and prevent drywell entry by plant personnel.
A drywell entry to inspect for leakage can be performed 2 920 psig, which is associated with approximately 15% reactor power. Performance of the leakage test in this manner would have an insignificant impact on the ability to detect leakage from a reassembled mechanical connection. It would also significantly reduce the personnel exposure and critical path outage time required for the test.
Based on the above, LaSalle County Station requests relief from the ASME Section XI requirements for the system leakage test pressure when performing pressure testing of reassembled, unisolable Class 1 mechanical connections.
PROPOSED ALTERNATE PROVISLORS As an altemate examination, LaSalle County Station will perform a system leakage test 2 920 psig during unit startup when an unisolable Class 1 mechanical connection in the drywell has been disassembled and reassembled either 1) subsequent to !
performance of the system pressure test conducted near the end of each refueling l outage; or 2) during a forced maintenance outage in the course of an operating cycle.
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APPUCABLE 11ME PERIOD Relief is requested for the first ten-year interval of the System Pressure Testing )
Program for LaSalle Units 1 and 2. !
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a REUEF REQUEST NUNEER: RI-26 l (Page 1 of 3) !
_C_QLVPONENT IDENTIFICATION l i
Code Classes- 1 and 2 i
References:
IWA-4400(a) i IWA-4400(b) l IWA-5214 1 Examination Categories: B-P, C-H !
Item Numbers: B15.10 through B15.71 !
C7.10 through C7.41 >
Description:
Attemate Testing for ISI Class 1 and Class 2 j Repaired / Replaced Components. :
Component Numbers: All Class 1 and Class 2 pressure retaining components ;
subject to Hydrostatic Testing per IWA-4700. !
CODE REQUJBENENE IWA-4400(a) requires an elevated pressure hydrostatic test to be perforrned after l welded repair / replacement of classed components, except those exempted by IWA- ;
4400(b). ;
BASIS FOR REUEF Elevated pressure hydrostatic tests are difficult to perform and often represent a true hardship. Some of the difficulties associated with elevated pressure testing include the ,
following: !
- Hydrostatic testing often requires complicated or abnormal valve line-ups in . l order to properiy vent, fill and isolate the component requiring testing. l t
- Relief valves with set-points lower than the hydrostatic test pressure must be k gagged or removed and blind flanged. This process requires the draining and 1 refilling of the system. !
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- Valves that are not normally used for isolation (e.g., normally open pump -
discharge valves) are often required to provide pressure isolation for an ;
elevated pressure hydrostatic test. These valves frequently require time ;
consuming mat maintenance in order to allow for pressurization. j
- The radiation exposure required to perform a hydrostatic pressure test is high 3 (in comparison to operational pressure testing) due to the large amount of time :
required to prepare the volume for testing (i.e. installing relief valve gags,. :j performing appropriate valve line-ups, etc). i k:\pete\ relief \5 !
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REUEF REQUEST NUMBER RI-2fi (Page 2 of 3)
The difficulties encountered in performing a hydrostatic pressure test are prohibitive when weighed against the benefits. Industry experience, which is corroborated by LaSalle County Station's experience, shows that most through wall leakage is detected during system operation as opposed to during elevated pressure tests such as ten-year system hydrostatic tests.
Uttle benefit is gained from the added challenge to the piping system provided by an elevated pressure hydrostatic test (when compared to an operational test). The piping stress experienced during a hydrostatic test does not include the significant stresses affiliated with the thermal growth and dynamic loading associated with design basis events.
These arguments are also supported by the adoption of Code Case N-498, "Altemative Rules for 10 Year Hydrostatic Pressure Testing for Class 1 and 2 Systems,Section XI, Division 1" This relief request is a logical extension of that Code Case.
In addition to pressure tests, non-destructive examinations performed on repair / replacement welds and metal removal sites provide assurance of component integrity.
Based on the above, LaSalle County Station requests relief from the ASME Section XI requirements for performing elevated pressure hydrostatic tests on Class 1 and 2 repaired / replaced components.
PROPOSED AlJERNATE PROVISLONS NDE shall be performed in accordance with methods and acceptance criteria of the applicable Subsection of the 1992 Edition of Section Ill.
A VT-2 visual examination will be performed with the Class 1 or 2 repaired / replaced component pressurized to nominal operating pressure. This visual examination will be performed after nominal operating pressure has been held for the following times:
- Non-Insulated components shall be held at nominal operating pressure for 10 minutes prior to examination.
- Insulated components shall be held at nominal operating pressure for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ;
prior to examination.
REUEF REQUEST NUNEER: RI-26 (Page 3 of 3)
APPUCABUGMELEEBMXL Relief is requested for the first ten-year interval of the System Pressure Testing Program for LaSalle Units 1 and 2.
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. I REUEF REQUEST NUNEER: RI-27 ,
(Page'1 of 1) l i
COlVPONENT IDENTIFICATION Code Class: 2 ,
Reference:
IWA-5241(b) !
Exanination Category: C-H i Item Numbers: C7.10, C7.11 !
Description:
Attemate Testing for Residual Heat Removal Heat !
Exchanger Tubes. !
Component Numbers: Unit 1: 1E12-B001A,1E12-B001B -l Unit 2: 2E12-B001A, 2E12-B001B 1 l
t COREEEQUlBENEliI IWA-5241(b) states that the VT-2 visual examination of inaccessible components shall ,
consist of an examination of the surrounding area, including floor areas or equipment ;
surfaces located underneath the components, for evidence of leakage. 1 B& SIS FOR RFIIEF 'l The tubing inside the Residual Heat Removal (RHR) Heat Exchanger is inaccessible. l A visual examiner cannot enter the RHR Heat Exchanger to perform an examination of ,
' the tubes or their surrounding areas during operational or hydrostatic pressure testing. !
t Based on the above, LaSalle County Station requests relief from the ASME Section XI requirements for perfoming a VT-2 visual examination of the RHR Heat Exchanger ;
tubing during hydrostatic and operational pressure tests. 1 i
EBRERSED ALTERNATE EXAMNATION j Monitoring of radiation levels in the tube side cooling water will be performed during '!'
the shell side pressure test as an attemate rnethod of verifying tube integrity. Levels within Technical Specification limits will be considered acceptable. l AEE1LCABuillNE.EEBlQQ -
l Relief is requested for the first ten-year interval of the System Pressure Testing ' i 1
Program for LaSalle Units 1 and 2.
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REUEF REQUEST NUNEIER Rl-28 I (Page 1 of 2) ,
CONPONENT IDENTIFICATION l Code Class: 3 !
Reference:
IVD5223(f) l Examination Category: D-B l Item numbers: D2.10 i
Description:
Exemption From Pressure Testing Piping Beyond the Last !
Safety Or Relief Valve Which Discharges into Re j Suppression Pool i Component Numbers: Various CODELBEQUlBENENI ASME Section XI 1980 Edition, Wnter 1980 Addenda, IWD-5223(f) states "For safety or relief valve piping which discharges into the containment pressure suppression pool, a pneumatic test (at a pressure of 90% of the pipe subnergence head of water) that ;
demonstrates leakage integrity shall be performed in lieu of system hydrostatic test."
BASIS FOR REUEF l LaSalle County Station has eighteen Main Steam Relief Valves with associated - !
discharge lines and vacuum breakers. The discharge lines run down through the -
drywell and discharge into the Suppression Pool.
Normal plant operation calls for these lines to be pressurized only during periodic lift tests which verify the set point of each Main Steam Relief Valve. All discharge piping ;
is contained inside the drywell. At the power level during these lift tests, the radiation :
levels in the drywell are prohibitive and prevent inspection personnel from entering the ,
drywell and performing VT-2 examinations during the Relief Valve functional testing.
The provisions of IVD5223(f) call for a pneumatic test at a test pressure of 90%
submergence head to be performed The design of the Main Steam Relief Valves and _;
associated discharge lines at LaSalle County Station does not allow for such a test to e be performed that would demonstrate leakage integrity. Per 10CFR50.55a section i (g)(4), Code Class components shall meet the requirements of ASME Section XI to extent practical within the limitations of design, geometry, and materials of construction of the components.
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REUEF REQUEST NUlVEER: RI-28 ,
(Page 2 of 2) -
SASIS FOR REUEF (Continued) l No test taps are currently available on these discharge lines to allow proper pressurization and depressurization of the system. The pressure associated with 90% i submergence head in these lines relates to approxirnately 3-5 psig, while the design 1 pressure of the discharge lines is 600 psi. The normal surveillance lift test is - t performed at a minimum vessel pressure of 600 psig and is thus the more challenging i test. Also at the low test pressure of the submergence head test, the vacuum '
breakers are not designed to provide a leak tight seal and would provide another leak path that would prevent verification of component integrity. .
Based on the above, LaSalle County Station requests relief from the 1980 Edition, t Wnter 1980 Addenda ASME Section XI requirements for conducting a VT-2 ;
examination under normal operating conditions and from the hydrostatic test requirements to perform a pneumatic test at 90% pipe submergence head once every !
inspection interval.
- PROPOSED ALTERNATE EXAMNAT10N No altemate examinations are proposed.
i APPUCABLE T11VE PEBLQQ Relief is requested for the first ten-year interval of the System Pressure Testing
- Program at LaSalle County Station Unit 1 and 2.
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