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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20210E0501999-07-22022 July 1999 Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20209H5171999-07-15015 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129 ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20209F6931999-07-13013 July 1999 Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196J4711999-06-30030 June 1999 Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2 ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206R4561999-05-12012 May 1999 Provides Notification That Ws Jakielski,License SOP-30168-3, Is Being Reassigned & No Longer Requires Use of NRC License, IAW 10CFR50.74 ML20206K7081999-05-0707 May 1999 Forwards 10CFR50.46(a)(3) Rept Re Significant Change in Calculated Pct.Loca Analyses for Both GE Fuel & Siemens Power Corp Fuel Demonstrates Results within All of Acceptance Criteria Set Forth in 10CFR50.46 05000373/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal1999-05-0707 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal ML20206K1861999-04-30030 April 1999 Informs That in Comed Submitted Annual Exposure Rept for Personnel Receiving Greater than 0 Mrem/Yr Rather than 100 Mrem/Yr.Updated Rept Limiting Data to Personnel Receiving Greater than 100 Mrem/Yr,Attached ML20206F0931999-04-30030 April 1999 Forwards LaSalle County Nuclear Power Station,Units 1 & 2 Effluent & Waste Disposal Semi-Annual Rept for 1998. LaSalle County Station Tech Specs Recently Revised to Reduce Periodicity of 10CFR50.36a ML20206R0751999-04-30030 April 1999 Forwards License Renewal Applications & Certification of Medical Examinations for LaSalle County Station Personnel Whose Licenses Expire in Nov.Personnel Listed.Without Encls ML20206D5921999-04-28028 April 1999 Forwards Annual Environ Operating Rept for 1998 for Environ Protection Plan, for LaSalle County Station,Units 1 & 2. Rept Includes Info Required by Listed Subsections of App B to Licenses NPF-11 & NPF-18 ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205L8161999-04-0808 April 1999 Advises NRC of Util Review & Approval of Cycle 8 Reload Under Provisions of 10CFR50.59 & Transmit COLR for Upcoming Cycle Consistent with GL 88-16.Reload Licensing Analyses Performed for Cycle 8 Utilize NRC-approved Methodologies ML20205J9451999-04-0505 April 1999 Submits Petition Per 10CFR2.206 Requesting That LaSalle County Nuclear Plant Be Immediately Shut Down & OL Suspended or Modified Until Such Time That Facility Design & Licensing Bases Are Properly Updated ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207J9841999-03-0505 March 1999 Informs That Effective 990212,KC Dorwick Has Resigned & No Longer Requires Use of NRC License for LaSalle County Station ML20207C7251999-03-0101 March 1999 Forwards Annual Rept for LaSalle County Station, for Period of 980101-981231.App E to Rept Provides Info on All Personnel Receiving Exposures of More than 0 Mrem/Yr Rather than 100 Mrem/Yr Requirement of TS 6.6.A.2 ML20207F9581999-03-0101 March 1999 Requests That Initial License Examination Currently Scheduled for Weeks of May 15 & 22,2000 Be Changed to Weeks of Nov 13 & 20,2000.Class Size Is Projected to Be Twelve RO & SRO Candidates ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207C8401999-02-25025 February 1999 Forwards Rev 60 of Comed LSCS Security Plan,Iaw 10CFR50.4(b) (4).Rev Eliminates Requirement for Annual change-out of Vital & PA Keys & Locks & re-configuration of PA Fence Around North Access Facility.Rev Withheld ML20207A9361999-02-24024 February 1999 Forwards Rev 4 to Restart Plan,To Reflect Review,Oversight & Approval Process Necessary to Restart Unit 2.Review & Affirmation Process Will Focus on Station Capability to Support Safe Dual Unit Operations 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H5321990-09-11011 September 1990 Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers ML20059H4271990-09-0707 September 1990 Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831 ML20059G0941990-09-0505 September 1990 Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp ML20059C6891990-08-30030 August 1990 Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary ML20056B4061990-08-21021 August 1990 Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements ML20059B8961990-08-14014 August 1990 Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed ML20059D1731990-08-10010 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels ML20058N2971990-08-0606 August 1990 Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21) ML20064A5491990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation ML20056A7031990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H7661990-07-24024 July 1990 Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20055G2011990-07-13013 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for LaSalle County Unit 1.Outage/Reduction 16 Corrected ML20055F1831990-07-0909 July 1990 Provides Status Rept on Breaker Replacements in Response to NRC Bulletin 88-010.Breaker Replacements for Plants Scheduled to Be Completed by 901031 ML20044B1751990-07-0909 July 1990 Responds to NRC Request for Addl Info Re Util 890726 Proposed Amend to Tech Specs to Allow Continued Operation for Period of 12 H W/Main Steam Tunnel High Ambient Temp & High Ventilation Sys Differential Trips Bypassed ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D1921990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues ML20055J2021990-06-26026 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-06 & 50-374/90-06.Corrective Actions:Perimeter Zone Repairs Commenced on Schedule & Completely Functional & Out of Compensatory Measures on 900614 ML20044A5071990-06-22022 June 1990 Forwards Revised Response to Station Blackout Rule for Plant.During Blackout Event,Plant Can Utilize RCIC Sys or HPCS to Provide Required Reactor Vessel Inventory Makeup ML20043E8651990-06-0707 June 1990 Forwards Relief Request RV-57 for Emergency Fuel Pool Makeup Crosstive Vent Valve 1(2)E12-F097.Expedious Review of Request Requested Because Valve 1(2)E12-F097 Inoperable & Will Remain So Until NRC Approval Received ML20043D3221990-06-0101 June 1990 Forwards Rev 33 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C8241990-06-0101 June 1990 Advises of Intentions to Review & Approve Cycle 4 Reload,Per 10CFR50.59 & Forwards Rev 1 to LAP-1200-16, Core Operating Limits Repts for LaSalle County Station Unit 2,Reload 3, Cycle 4, Per Generic Ltr 88-16 ML20043B6581990-05-25025 May 1990 Requests Schedular Extension of Two Human Engineering Deficiencies Re CRT Displays W/Current Ramtek Sys & Approval to Leave Seven Human Engineering Discrepancies Accepted as Is. ML20043B7921990-05-23023 May 1990 Forwards Endorsements 14 to Nelia Policy N-71 & Maelu Policy M-71 & Endorsements 12 to Nelia & Maelu Policies N-83 & M-83,respectively ML20042E8841990-04-30030 April 1990 Responds to Generic Ltr 89-04 Re Weaknesses of Inservice Testing Programs.Plant Has Implemented Rev 2 of Inservice Testing Program Submitted by Util 891002 & 24 Ltrs.No Equipment Mods Required as Result of Generic Ltr ML20042F3591990-04-29029 April 1990 Provides Suppl Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Precaution Added to Operating Procedures Which Allows ECCS Pump to Be Secured & Restarted as Necessary to Preclude Running Pumps at Min Flow ML20042F0341990-04-23023 April 1990 Forwards Part 3 to 1989 Operating Rept,Containing Results of Radiological Environ & Meteorological Monitoring Programs. W/O Encl ML20064A6281990-03-30030 March 1990 Submits Supplemental Response to Insp Repts 50-373/86-04 & 50-374/86-04 Re Fire Detection Concerns,Per NRC 900214 Request.Proposed Administrative Controls & Training Will Eliminate Concerns That Assure Protection of Personnel ML20055E1461990-03-29029 March 1990 Provides Supplemental Response to Re Violations Noted in Insp Repts 50-373/89-18 & 50-374/89-18 on 890724- 0825.Corrective Actions:Plant Performs Safety Evaluation for Mods Not Designed by Corporate Nuclear Engineering Dept ML20012C6991990-03-15015 March 1990 Forwards Corrected Tech Spec Page to 881129 Application for Amend to Licenses NPF-11 & NPF-18,removing Specific Load Profiles for Each Dc Battery ML20012B6541990-02-26026 February 1990 Forwards LaSalle County Station Unit 1 Third Refueling Outage ASME Section XI Summary Rept, for Fall 1989 Inservice Insps Performed.Conditions Observed & Corrective Measures Taken Also Contained in Rept ML20006E7421990-02-0909 February 1990 Responds to NRC 900110 Ltr Re Violations Noted in Insp Repts 50-373/89-23 & 50-374/89-22.Corrective Actions:Ltr from Station Manager to All Dept Heads Was Issued on 891218, Discussing Personnel Performance Issues ML20005F5771990-01-0808 January 1990 Documents Guidance Given by P Shemanski Re Typos in Earlier Approved Amend to License NPF-11.Guidance Should Adhere to Wording of Unit 2 Tech Specs.Guidance Given on 900105 & Will Be Followed Until Correction Made at NRR Ofcs ML20011D9661989-12-22022 December 1989 Forwards Core Operating Limits Rept for LaSalle County Station Unit 1,Reload 3 (Cycle 4). Intention to Review & Approve Cycle 4 Reload Under Provisions of 10CFR50.59 Stated ML20005E1661989-12-22022 December 1989 Forwards Rev 32 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facilities.Rev Withheld (Ref 10CFR73.21) ML19332E4531989-11-29029 November 1989 Responds to Generic Ltr 89-21, Status of Implementation of USI Requirements. Response to USI A-48 Expected by 900319 ML19332C2461989-11-0808 November 1989 Provides Supplemental Response to Insp Repts 50-373/88-05 & 50-374/88-05 on 890302-10.Scheduled Completion Dates for Sample Panel Mods Changed from Third to Fourth Refueling Outages of Each Unit ML19325E5191989-10-31031 October 1989 Forwards Qualification Test Rept QTR87-018, Max Credible Fault Tests CM249-Q2 Carrier Modulator for Fermi 2 SPDS, in Response to NRC 890304 Request for Addl Info Re Facility Validyne Isolator CM-249 ML19325E3601989-10-26026 October 1989 Forwards Addl Info Re Application for Amend to Licenses NPF-11 & NPF-18,revising Tech Specs to Conform W/Diesel Generator Test Schedule Recommendations,Per Generic Ltr 84-15 ML19325E7921989-10-24024 October 1989 Submits Response to SALP 8 Board Repts 50-373/89-01 & 50-374/89-01.Expresses Appreciation for NRC Recognition of High Level of Performance in Area of Plant Operations, Emergency Preparedness & Security ML19325E0941989-10-24024 October 1989 Forwards Clarification to Summary of Changes Made in Rev 2 to Plant Inservice Testing Program ML19353A9051989-10-23023 October 1989 Responds to NRC 890921 Ltr Re Violations Noted in Insp Repts 50-373/89-19 & 50-374/89-19.Corrective Actions:Hose Connection That cross-connected Svc Air Sys W/Clean Condensate Sys Uncoupled & Secured ML17285A8081989-10-18018 October 1989 Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 70 ML19325D1931989-10-13013 October 1989 Forwards Quarterly Rept on Static-O-Ring Failures Third Quarter 1989,per IE Bulletin 86-002.Stated Switches Replaced ML19327B0431989-10-0505 October 1989 Responds to NRC 890821 Ltr Re Violations Noted in Insp Repts 50-373/89-15 & 50-374/89-15.Corrective actions:post-order for Assembly Revised to Provide Specific Guidance on Use of Siren & Loudspeaker on Mobile Vehicles During Assemblies ML19327A7491989-10-0202 October 1989 Forwards Rev 2 to Combined Units 1 & 2 Inservice Testing Program for Pumps & Valves. Implementation of Program Will Require Procedure Revs Expected to Be Completed by 900228 ML19325D3271989-10-0202 October 1989 Forwards Rept Re Findings & Conclusions of Investigation Re 890826 Scram ML20248D0881989-09-21021 September 1989 Forwards Rev 56 to QA Program Topical Rept CE-1-A ML20247Q6431989-09-21021 September 1989 Documents Relaxation of Commitment Re Disassembling & Insp of Sor Switches ML19327A7681989-09-18018 September 1989 Forwards Response to Allegations Re Potential Employment Discrimination.Encl Withheld (Ref 10CFR2.790(a)(7)) 1990-09-07
[Table view] |
Text
. .
,m
/ _ -X/ one Commonwrith Edison First National Plaza. Chicago. Ilhnois
(
Address Reply to: Post Othee Box 767 (gj- ~7 Chicago, flhnois 60690 September 23,S,E8fl N s o,
% - TlI/
52' HL . L ! i (ph' Mr. Harold R. Denton, Director f_2[ gg' Office of Nuclear Reactor Regulation -t 2, 1981a- -f U.S. Nuclear Regulatory Commission $ "'&Zgeo , [p Washington, DC 20555 '74 C Gu . , b'
Dear Mr. Denton:
/-4,]f- (\ ')
3 Commonwealth Edison Company anticipates receiving operating licenses for its LaSalle County Nuclear Power Station, Units 1 and 2, this fall and next year. The purpose of this letter is to request the Nuclear Regulatory Commission to issue each of these operating licenses for a full term of 40 years each, running from the date of the issuance of the licenses. The requested 40-year term would be consistent with the safety reviews conducted by the Energy Act and the NRC regulations.
The NRC's past practice has been to issue an operating license for a term of 40 years, which is backdated to the issuance of the construction permit rather than starting with the issuance of the operating license itself. Because the time required for the construction of nuclear power plants has steadil.y increased over the past few years, the Commission's practice of backdating has resulted in the steady erosion of authorized operating periods for newer plants. (See Attachment 1). This practice of reducing the lifetime of operating licenses is apparently unintentional and aroitrary. It is not required for the safety of nuclear power plants, nor is it in keeping with the intent of the Atomic Energy Act.
For LaSalle County Nuclear Station, following the past practice of backdating operating license would result in an effective duration of only 32 years, a 20% reduction in the authorized operating life of the Station. This result is not compelled by tne NRC Staff's thorough safety and environmental review of the LaSalle units. The Staff did not base its reviews on a fixed number of years from the date of the construction permit.
Commonwealth Edison is unaware of any safety or environmental considerations which require limiting the effective duration of the LaSalle operating licenses to a period of less than 40 years.
Section 103(c) of the Atomic Energy Act of 1954, 42 U.S.C. 5 2133(c) (1976), authorizes the Nuclear Regulatory Commission to issue commercial operating licenses for a "specified period...but Dof 1
8110050362 810923 DR ADOCK 03000373 PDR
not exceeding 40 years."
however, was not dictated by a concernThe 40 year limitation in the statute ,
environmental study of the effects of continued operationfor safety or for the legislative history .
In fact, a close establish a 40 year limit.was economic considerations n revealswhich that it were beni dto the decision to Interestingly, the the Atomiclicenses.
operating Energy Act o f 1946 providedfirst proposal in April, 1954, to amend of 1946, (A Proposed Act to Amend the Atomic Enefor a 25 year l (Lomm. Joint Print Committee Anril 1954 _reorir on Atomic Energy rgy Act ted 83d Cong., 2d Sess. 21 Atomic Energy 0 0 t o f 1954, at 81 in Legislative History of the oetore tne Joint (1955).) However, in hearings _ held representative testified that of interested public utilitiesCommittee ,
, 1954, a on Atomic Energy E. H. Dixon, plant construction projects.the 25 year limitation would discourage ear power nucl (Hearings Before on (stabAtomic ment ofE.~~ Eneroy, H. Oixon) 83d Cong., 2d Sess. the203-31 (May 11, 1954)
Joint Committee Atomic of Eneray Ac t o f 1954, _reorinted in Legislative History of the this expanded testimony, at 1864-1665 (1955).)
(Oraft In the 25 year maximum on operatingo licenses Bill Form, tthe and Joint Com (May 21, 1954) Joint Committee Print, 40 years.
Ac t o f 19 54, reprinted in Leoislative History 83d Cong., 2d Sess. 41 at 29/
became law ~on February 17, (1955).) It was tnis latter proposalof the Atomic Energy (1954). 1954 Pub. L. No. whien fairly clear thatFrom the legislative history of Secti 703-1073, 58 Stat.
on 103(c), it seems 919 year licensing discouraged from term so that public utilitiesthe intent of Congress 0 was to p nuc'aur power stations onlytaking to on the costlywould burdensnot be of constructi ng invastments still had economic usefulnfind the ess. The licenses expire when their power plants are more expensive and fact that modern than older plants successful applicant and increases the justifitake longer to build and licens bene fi t the public it serves thecation for allowing a of the 40 year term originally intended byfull Con economic gress.
forth insure the a intent of the statute by prescribing on 103(c) carry pThe NRC regu full term of 40 years to an applicant rocedures which necessary In particular, safety 10 CFRand environmental requirements who meets the provides: 50.51 entitled "Ouration of of the Commission.
License,"
Each be license in specified will be issued for a years f rom the date the oflicense issuance.but in no case to exceed 40 fixed period of for the term requested by the n applica tfacility is involve ssue the license estimated useful determines that life of the facllity if theorCommission for the term requested....the estimated useful life is less than tha n
-2 not exceeding 40 years." The 40 year limitation in the statute, however, was not dictated by a concern for safety or for the environmental effects of continued operation. In fact, a close study of the legislative history to Section 103(c) reveals that it was economic considerations which were behind the decision te establish a 40 year limit.
Interestingly, the first proposal in April, 1954, to amend the Atomic Energy Act of 1946 provided for a 25 year limitation on operating licenses. (A Proposed Act to Amend the Ato.3!c Energy Act of 1946, Joint Committee on Atomic Energy, 83d Cong., 2d Sess. 21 (Comm. Print April 1954 reprinted in Legislative History of the Atomic Energy Act of 1954, at 81 (1955).) However, in hearings held before the Joint committee on Atomic Energy in Mcy, 1954, a representative of interested public utilities, E. H. Dixon, testified that the 25 year limitation would discourage nuclear power plant construction projects. (Hearings Before the Joint Committee on Atomic Energy, 83d Cong., 2d Sess. 203-31 (May 11, 1954)
(statement of E. H. Olxon) reorinted in Legislative History of the Atomic Energy Act of 1954, at 1864-1865 (1955).) Apparently because of this testimony, tne Joint Committee amended the proposed bill and expanded the 25 year maximum on operating licenses to 40 years.
(Draft In Bill Form, Joint Committee Print, 83d Cong., 2d Sess. 41 (May 21, 1954) reprinted in Legislative History of the Atomic Energy Act of 1954, at 297 (1955).) It was this latter proposal which became law on february 17, 1954. Pub. L. No. 703-1073, 68 Stat. 919 (1954). Fro:. che legislative history of Section 103(c), it seems fairly clear that the intent of Congress was to provide a full 40 year licensing term so that public utilities would not be discouraged from taking on the costly burdens of constructing nuclear power stations only to find the licenses expire when their investments still had economic usefulness. The fact that modern power plants are more expensive and take longer to build and license than older plants increases the justification for allowing a successful applicant and the public it serves the full economic benefit of the 40 year term originally intended by Congress.
The NRC regulations which implement Section 103(c) carry forth the intent of the statute by prescribing procedures which
'nsure a full term of 40 years to an applicant who meets the necessary safety and environmental requirements of the Commission.
In particular, 10 CFR 50.51 entitled " Duration of License,"
provides:
Each license will be issued for a fixed period of time to be specified in the license but in no case to exceed 40 years f rom the date of issuance. Where the operation of a facility is involved the Commission will issue tha license fur the term eequested by the applicant or for the estimated useful life of the facility if the Commission determines that the estimated useful life is less than than term requested....
l l
l This regulation clearly req" ires the NRC to grant Commonwealth Edison's request for 40 year operating licenses unless the useful life of LaSalle County Station is determined to be something less.
In addition, the language of Section 50.51 states that the license should run "from the date of issuance," not from a date prior to the issuance.
10CFRh50.56isnotinconsistentwith10CFR50.51.
Sectionh 50.56 refers to the " conversion" o f a construction permit to an operating license. But in NRC practice there has always been a clear distinction between a construction permit and an operating license. Construction permits and operating licenses have their own distinct terms and conditions, including different environmental monitoring requirements, different safety inspection schedules, and different ti...e limits. There is no more reason why the term of the construction permit should be reflected in the term of the operating license than there is that a particular monitoring program, appropriately developed for construc Pion activities, should be included in the operating license t :nical specifications.
Moreover, the rule governing duration of operating licenses is inund in 42 U.S.C. h2133, while the need for time limits for construction permits is derived from a completely different source. See 42 U.S.C.h2235. Therefore, there is no logical reason why
" conversion" of a construction permit into an operating license should require subtracting apples (t ne time for construction) from oranges (the time for operation).
A f air appreciation of the enormous ef fort which nas gone into the construction and licensing review of the LaSalle County Nuclear Station, and a careful reading of the Atomic Energy Act of 1954, the legislative history, and the regulations supports the view that, once construction is completed, there is really no reason why anything less than a full 40 year term should be granted.
Arbitrarily foreshortened license terms do not serve the best intersts of the NRC, the applicant or the public.1 Commonwealth Edison asks that the NRC Staff grant its request to have the operating licenses for the LaSalle County Station issued for full 40 year terms beginning with the dates of issuanci In the event the Staf f cannot support our position, we ask that :r request be forwarded to the Commission for its consideration and that we be given an opportLaity to address the Commission in support of our request. Commonwealth Edison would like to stress, however, that its principal concern lies in the timely licensing of the LaSalle County Station. We do not want this
request to result in any delay in this licensing process.
Sincerely, L. O. DelGeo rge Director of Nuclear Licensing cc: Martin Malsch Colleen Woodhead 1 The statute and regulations do provide for renewal of licenses upon expiration. 42 U.S.C 2133; 10 CFR 50.51. But re-licensing a nuclear power plant would be an enormous, uncertain undertaking which can not be regarded as a satisfactory answer to Commonwealth Edison's present request for the full-term, 40-year operating licenses to which it is entitled by law.
2538N
APPENDIX A O O NUCLEAR UNITS ARRAN D CilRONOLOGICALLY '
BY DATE OF OPERATING LICENSE SEP 23 ES EFFECTIVE LIFETIME NRC OF A 40-YEAR DOCKET COMPANY NUCLEAR UNIT DATE Oi' DATE OF C.P. O.L. OPERATING LICENSE NUMBER I
50-10 Commonwealth Edison Dresden - 1 5-04-56 9-28-59 36 yrs. 7 mos.
Co.
50-456 Yankee Atomic Yankee-Rowe 11-04-57 7-09-60 37 yrs. 4 mos.
Electric Company 50-213 Consolidated Edison Indian Pt - 1 5-04-56 3-26-62* 34 yrs. 1 mo.
Co. of N.Y.
50-133 Pacific Gas and Humboldt Bay 11-09-60 8-28-62 38 yrs. 2 mos.
Electric 50-155 Consumers Power Big Rock Point 5-31-60 8-30-62* 37 yrs. 9 mos.
Co.
50-206 Southern California San Onofre - 1 3-02-64 3-27-67 37 yrs.
Edison Co.
50-213 Connecticut Yankee Conn. Yankee 5-26-64 6-30-67 36 yrs. 9 mos.
Atomic Electric Co.
50-409 Dairyland Power Coop. La Grosse 3-29-63 7-03-67** 35 yrs. 9 mos.
50-219 Jersey Central Power Oyster Creek 12-15-64 4-09-69 35 yrs. 7 mos.
& Light 50-220 Niagara Mohawk Nine Mile pt - 1 4-12-65 8-22-69 35 yrs. 8 mos.
Power Corp.
- Date for provisional operating license.
- Date for provisional operating authorization.
NUCLEAR UNITS ARRA J CIIRONOLOGICALLY BY DATE OF OPERATING LICENSE i
EFFECTIVE LIFETIME J
NRC OF A 40-YEAR DOCKET COMPANY NUCLEAR UNIT DATE OF DATE OF C.P. O.L. OPERATING LICENSE NUMBER Ginna 4-25-66 9-19-69* 36 yrs. 1 mo.
50-244 Rochester Gas and Electric Corporation 1
Dresden - 2 1-10-66 12-22-69 36 yrs. 1 mo.
50-237 Commonwealth Edison Co.
4-13-67 7-31-70 36 yrs. 7 mos.
50-261 Carolina Power and Robinson - 2 Light Monticello 6-19-67 9-08-70 36 yrs. 7 mos.
50-263 Northern States Power Co.
i Point Beach - 1 7-19-67 10-05-70 36 yrs. 9 mos.
i 50-266 Wisconsin Electric I Power Millstone - 1 5-19-66 10-07-70 35 yrs. 7 mos.
50-245 Northeast Utilities Commonwealth Edison Dresden - 3 10-14-66 1-12-71 35 yrs.10 mos.
50-249 Co.
Comraonwealth Edison Quad Cities 1 2-15-67 10-01-71 35 yrs. 4 mos.
50-254 Co.
Commonwealth Edison Quad Cities 2 2-15-67 3-31-72 34 yrs.10 mos.
50-265 Co.
Wisconsin Electric Point Beach 2 7-25-68 5-25-72 36 yrs. 2 mos.
50-301 Power ODate for provisional operating license.
.. ..A-3 D. -
R NUCLEAR UNITS ARRANGED CllRONOLOGICALLY BY DATE OF OPERATING LICENSE . -
EFFECTIVE LIFETIME NRC DATE Op OF A 40-YEAR DOCKET COMPANY NUCLEAR UNIT DATE OF C.P. O.L. OPERATING LICENSE NUMBER Surrey - 1 6-25-68 5-25-72 36 yrs. 1 mo.
50-280 Virginia Electric and Power Pilgrim - 1 8-26-68 6-08-72 36 yrs. 1 mo.
50-293 Boston Edison Turkey Pt. -3 4-27-67 7-19-72 34 yrs. 9 mos.
50-250 Florida Power and Light Maine Yankee 10-21-68 9-15-72 36 yrs. 1 mo.
50-309 Maine Yankee Atomic Power Co.
Palisades 3-14-67 10-00-72* 34 yrs. 5 mos.
50-255 Consumers Power Surrey - 2 6-25-68 1-29-73 35 yrs. 5 mos.
50-281 Virginia Electric and Power Oconee - 1 11-06-67 2-06-73 34 yrs. 9 mos.
50-269 Duke Power Co.
Oconee - 2 11-06-67 2-06-73 34 yrs. 9 mos.
50-270 Duke Power Co.
Vt. Yankee 12-11-67 2-28-73 34 yrs. 9 mos.
50-271 Vermont Yankee Zion - 1 12-26-68 4-06-73 35 yrs. 6 mos.
50-295 Commonwealth Edison 1 Co.
Turkey Pt. -4 4-27-67 4-10-73 34 yrs.
50-251 Florida Power and Light 50-285 Omaha Public Power Ft. Calhoun - 1 6-07-68 5-24-73 35 yrs.
District CDate for full power authorization, P.O.L. issued 3/24/71.
~
. A_4 NUCLEAR UNITS ARRAN[ > CIIRONOLOGICALLY
~
BY DATE OF OPERATING LICENSE l
NRC EFFECTIVE LIFETIME DOCKET COMPANY NUCLEAR UNIT DATE OF DATE OF OF A 40-YEAR NUMBER C,P. O.L. OPERATING LICENSE 50-259 Tennessee Valley Browns Ferry 1 5-10-67 6-26-73 34 yrs. 1 mo.
1, Authority 4
!30-277 Philadelphia Electric Peach Bottom 2 1-31-68 8-08-73 34 yrs. 5 mos.
Co.
50-282 Northern States Prairie Island 6-25-68 8-09-73 34 yrs.ll mos.
Power Co.30-247 Consolidated Edison Indian Point 2 10-14-66 9-28-73* 33 yrs. 1 mo.
Co. of N.Y.30-304 Commonwealth Edison Zion 2 12-26-68 11-14-73 35 yrs. 1 mo.
Co.
1 30-305 Wisconsin Public Kewaunee 8-06-68 12-21-73 34 yrs. 8 mos.
Service Corp.
l50-267 Public Service Co. of Fort St. Vrain 1 9-01-68 12-21-73 34 yrs. 9 mos.
Oklahoma l30-298 Nebraska Public Cooper 6-05-68 1-18-74 34 yrs. 5 mos.
Power District 50-331 Iowa Electric Light Arnold 6-22-70 2-22-74 36 yrs. 4 mos.
& Power Co.
,30-289 Metropolitan Edison Three Mile Island - 1 5-18-C8 4-19-74 34 yrs. 1 mo.
'Date for full power authorization, O.L. issued 10/19/71.
r NUCLEAR UNITS ARRANL > CHRONOLOGICALLY
. R .A-5 ~-. -
BY DATE OF OPERATING LICENSE NRC EFFECTIVE LIFETIME DOCKET COMPANY NUCLEAR UNIT DATE OF DATE OF OF A 40-YEAR NUMBER C.P. O.L. OPERATING LICENSE 50-313 Arkansas Power Ak. Nuclear 1 12-06-68 5-21-74 34 yrs. 6 mos.
& Light .
,50-260 Tennessee Valley Browns Ferry 2 5-10-67 6-28-74 s 32 yrs.ll mos.
Authority Duke Power Co. Oconee - 3 11-06-67 7-19-74 33 yrs. 4 mos.
{30-287 50-317 Baltimore Gas and Calvert Cliffs 1 7-07-69 7-31-74 34 yrs.ll mos.
Electric 50-321 Georgia Power Hatch - 1 9-30-69 8-06-74 35 yrs. 2 mos.
,30-312 Sacramento Municipal Rancho - Seco 1 10-11-68 8-16-74 34 yrs. 2 mos.
Utility District 50-333 Power Authority of James A. FitzpatricP 5-20-70 10-17-74 35 yrs. 7 mos.
State of N.Y.
'30-315 Indiana & Michigan Cook - 1 3-25-69 10-25-74 34 yrs. 5 mos.
j Electric Co.30-306 Northern States Prairie Island 2 6-25-68 10-29-74 33 yrs. 8 mos.
Power Co.
,30-324 Carolina Power and Brunswick - 2 2-07-70 12-27-74 35 yrs. 3 mos.
Light
n ,- q A -6, NUCLEAR UNITS ARRANG CHRONOLOGICALLY BY DATE OF OPERATING LICENSE NRC EFFECTIVE LIFETIME DOCKET COMPANY NUCLEAR UNIT DATE OF DATE OF OF A 40-YEAR NUMBER C.P. O.L. OPERATING LICENSE
' 0-336 Northeast Utilities Millstone - 2 12-11-70 8-01-75 35 yrs. 4 mos.
t 0-344 Portland General Trojan 2-08-71 11-21-75 35 yrs. 3 mos.
l Electric Co.
i 0-286 Power Authority of Indian Pt. -3 8-13-69 12-12-75 33 yrs. 3 mos.
State of N.Y.
1 0-334 Duquesue Light Co. Beaver Valley - 1 6-26-70 1-30-76 34 yrs. 5 mos.
0-335 Florida Power & Light St. Lucie - 1 7-01-70 3-01-76 34 yrs. 6 mos.
- 0-296 Tennessee Valley Browns Ferry 3 7-31-68 7-02-76 32 yrs. 1 mo.
Authority 0-318 Baltimore Gas & Calvert Cliffs 2 7-07-69 8-13-76 32 yrs.ll mos.
Electric 0-325 Carolina Power Brunswick - 1 2-07-70 9-08-76 33 yrs. 5 mos.
& Light 0-302 Florida Power Co. Crystal River 3 9-25-68 12-03-76 31 yrs.10 mos.
0-272 Public Service Salem - 1 9-25-68 4-06-77* 31 yrs. 7 mos, i Electric & Gas Co.
! 0-346 Toledo Edison Co. Davis-Besse - 1 3-24-71 4-22-77 33 yrs.11 mos'.
0-348 Alabama Power Farley - 1 8-16-72 6-25-77 35 yrs. 2 mos.
Date for full power authorization, O.L. for 1% power issued 8/13/76.
, q .A-7 A .
NUCLEAR UNITS ARRANGED CIIRONOLOGICALLY DY DATE OF OPERATING LICENSE .
EFFECTIVE LIFETIME NRC DATE OF OF A 40-YEAR COMPANY NUCLEAR UNIT DATE OF DOCKET ~
C.P. O.L. OPERATING LICENSE NUMBER North Anna - 1 2-19-71 11-26-77 33 yrs. 3 mos.
50-338 Virginia Electric
& Power Co.
3-25-69 12-23-77 31 yrs. 3 mos.
'50-316 Indiana and Michigan Cook - 2 Electric Co.
11-04-69 2-08-78 32 yrs. 4 mos.
50-320 Metropolitan Edison Three, Mile Island - 2 Co.
12-27-72 6-13-78 34 yrs. 6 mos.
50-366 Georgia Power Co. Hatch - 2 12-06-72 7-18-78 34 yrs. 7 mos.
50-368 Arkansas Power & Arkansas Nuclear Light Co. One-2 -
2-19-71 10-11-80 30 yrs. 4 mos.
50-339 Virginia Electric & North Anna - 2 Power Co.
2-16-72 10-23-80 31 yrs. 4 mos.
50-364 Alabama Power Co. Farley - 2 5-27-70 10-23-80 29 yrs. 7 mos.
50-327 Tennessee Valley Sequoyah - 1 Authority 2-28-73 6-29-81* 31 yrs.10 mos.
50-369 Duke Power Co. McGuire - 1 Salem - 2 9-25-68 Expected 50-311 Public Service 81**
Electric & Gas o Date for full power authorization, O.L. issued on 4/18/80 for low power testing.
00Zero power O.L. issued 1/23/81.
.. A-8 b
NUCLEAR UNITS ARRANG CIIRONOLOGICALLY ,
BY DATE OF OPERATING LICENSE EFFECTIVE LIFETIME NRC OF A 40-YEAR DOCKET COMPANY NUCLEAR UNIT DATE OF DATE OF O.L. OPERATING LICENSE NUMBER _C.P.
50-361 Southern California San onofre - 2 10-18-73 Expected 81*
50-328 Tennessee Valley Sequoyah - 2 5-27-70 Expected Authority 81*
4
- O.L. 's have been Comntission Agenda items in 1981.
Source: Compiled frora NUREG-0652, Vol. 1, No. 1, Facilities License Application Record, Data as of 4/1/81, NRC (1981); Commercial Nuclear Power Plants, Ed. No. 13,
) NUS Corp. (1981); Actual Dockets of NRC; and, The Energy Daily (June 30, 1981).
_ _ _ _ _ _ ___ _