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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217H4661999-10-18018 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 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 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV 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 ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 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 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 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry 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 ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts 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 ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities 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 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified 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 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented 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 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 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 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept 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) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted 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 ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition 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 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20217A1551990-11-14014 November 1990 Forwards Safety Insp Rept 50-455/90-22 on 901002-1107. Violations Noted ML20217A4431990-11-14014 November 1990 Forwards Safety Insp Rept 50-455/90-21 on 900910-11,24-26 & 1107.No Violations Noted ML20062E0201990-11-0909 November 1990 Forwards Safety Insp Repts 50-373/90-21 & 50-374/90-22 on 900902-1020 & Notice of Violation ML20058G2941990-11-0505 November 1990 Advises That Written & Operating Operator & Senior Operator Licensing Exams Scheduled for Wk of 910204 & Requests Listed Ref Matls 60 Days Prior to Exam Date ML20058G3241990-11-0505 November 1990 Forwards Page 9 of Insp Repts 50-454/90-16 & 50-455/90-15. Page Erroneously Deleted from Original Rept ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20059N7431990-10-0404 October 1990 Confirms 901012 Mgt Meeting at Region III Ofc to Discuss Util Corporate & Site Engineering Organizations ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L4531990-09-14014 September 1990 Forwards Suppl to SER Re Results of Inservice Testing Program Changes Based on Review of 881221 & 890203 Submittals.Changes Acceptable ML20059L3051990-09-14014 September 1990 Forwards SER Re Util 900706 Request for Relief Concerning Inservice Testing Program.Relief Granted from Testing Requirements Which Would Impose Undue Hardship If Immediate Compliance Was Imposed ML20059E8091990-08-31031 August 1990 Forwards Safety Insp Repts 50-373/90-20 & 50-374/90-21 on 900820 & 22-24.Violation Noted But Not Cited ML20059E6391990-08-30030 August 1990 Forwards Safeguards Insp Repts 50-373/90-18 & 50-374/90-19 on 900813-17.Violations Noted,But Not Cited ML20059E1141990-08-30030 August 1990 Forwards Safety Insp Repts 50-454/90-16 & 50-455/90-15 on 900814-17.No Violations Noted ML20059N0291990-08-22022 August 1990 Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping ML20059B4271990-08-17017 August 1990 Forwards Safety Insp Repts 50-454/90-17 & 50-455/90-16 on 900701-0811.No Violations Noted IR 05000373/19900081990-08-16016 August 1990 Confirms 900821 Meeting in Glen Ellyn,Il to Discuss Findings in Insp Repts 50-373/90-08 & 50-374/90-09.Util Should Include Status of Radwaste Tank Room Repair & Cleaning Project Addressed in Insp Repts 50-373/90-13 & 50-374/90-14 ML20059A2401990-08-14014 August 1990 Advises That Operator & Senior Operator Licensing Exams Scheduled for Wk of 901203.Preliminary License Applications Should Be Submitted at Least 30 Days Before First Exam Dates in Order to Review Training & Experience of Candidates ML20059A5921990-08-14014 August 1990 Advises That 900806 Rev 34 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20058L9911990-08-0606 August 1990 Forwards SERs of Responses & Associated Science Application Intl Corp 900614 Technical Evaluation Rept SAIC-89/1640 Re Station Blackout.Revised Response Addressing Areas of Nonconformance Should Be Submitted within 60 Days ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20056A8611990-07-31031 July 1990 Forwards Safety Insp Repts 50-373/90-14 & 50-374/90-15 on 900603-0717.No Violations Noted ML20055J1521990-07-20020 July 1990 Forwards Final SALP Repts 50-454/90-01 & 50-455/90-01 for Nov 1989 - Mar 1990 ML20055G6661990-07-18018 July 1990 Confirms 900802 Enforcement Conference in Region III Ofc to Discuss Ofc of Investigations & Regional Findings Re Lack of Control of Operability Determinations Involving Emergency Diesel Generators at Plant.Listed Items to Be Discussed ML20055G3301990-07-17017 July 1990 Forwards Safety Insp Repts 50-454/90-14 & 50-455/90-13 on 900513-0630.No Violations Noted ML20055G2951990-07-13013 July 1990 Advises That SALP 9 Presentation Time Changed Due to Commissioner Carr Visit on 900723 ML20055E2171990-07-0202 July 1990 Forwards Requalification Exam Rept 50-454/OL-90-01 for Units 1 & 2 Administered During Wks of 900528 & 0604.Requests Response to Issue of Training & Evaluating Operators on Uncontrolled Depressurization of Steam Generators ML20055D8061990-06-29029 June 1990 Forwards Safety Insp Repts 50-373/90-11 & 50-374/90-11 on 900514-0613.No Violations Noted ML20055D0251990-06-28028 June 1990 Forwards Safety Insp Repts 50-454/90-15 & 50-455/90-14 on 900611-14.No Violations Noted ML20055D9721990-06-28028 June 1990 Forwards Mgt Meeting Repts 50-373/90-13 & 50-374/90-14 on 900530 & Notice of Violation.Meeting to Discuss Radiological Conditions Caused by Overflows in Radwaste Tank Rooms,Plans for Decontamination & Corrective Actions Taken ML20055E0701990-06-28028 June 1990 Forwards Safety Insp Repts 50-373/90-05 & 50-374/90-06 900605-08.No Violations Noted.One Exercise Weakness Identified ML20055E8791990-06-27027 June 1990 Forwards Notice of Withdrawal of 880302 Application for Amend to Change Tech Spec 4.6.1.6.1.d,to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin Not Reflected in Values Currently in Tech Specs,Per ML20055D2401990-06-27027 June 1990 Forwards Safety Insp Repts 50-373/90-12 & 50-374/90-13 on 900611-13.No Violations Noted.Exemption Granted from Conducting Type a Test During Each Refueling Outage Until Two Consecutive Tests Satisfy App J Acceptance Criteria ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C6341990-05-23023 May 1990 Advises That Revised Schedule to Perform Blackness Testing within 2 Yrs of Placing Racks in Svc & Every 5 Yrs Thereafter,Acceptable ML20055C5731990-05-16016 May 1990 Ack Receipt of 900430 Response to Allegation RIII-90-A-0011 Re Employee Fitness for Duty.Confirms That Results of fitness-for-duty Test Negative & Allegation Unsubstantiated ML20055C3821990-02-27027 February 1990 Requests Addl Info on Licensee Application for Amend Under Generic Ltr 87-09.Amend Based on Assumption That Remedial Measures Provide Sufficient Level of Protection to Permit Operational Mode Changes & Safe long-term Operation ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248D4981989-09-26026 September 1989 Accepts Scope & Objectives for Annual Emergency Preparedness Exercise Scheduled for 891206 & 07,submitted by ML20248A2191989-09-21021 September 1989 Forwards Safety Insp Repts 50-373/89-19 & 50-374/89-19 on 890725-0911 & Notice of Violation ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247N1901989-09-15015 September 1989 Confirms 890914 Discussion Between W Morgan & DE Jones Re Meeting on 891006 in Glen Ellyn,Il to Discuss Util Analysis of 890826 Scram ML20247K8861989-09-15015 September 1989 Forwards Safety Insp Repts 50-373/89-20 & 50-374/89-20 on 890808-31.No Violations Noted ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe IR 05000237/19890181989-09-0808 September 1989 Forwards Safety Insp Repts 50-237/89-18 & 50-249/89-17 on 890715-0828.No Violations Noted 1990-09-25
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased 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 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV 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 ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in 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 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts 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 ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities 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 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified 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 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 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented 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 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl 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 ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety 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) ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations 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 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 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 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B6031999-05-24024 May 1999 Ack Receipt of Which Transmitted Changes Identified as Rev 60 to LaSalle Nuclear Station Security Plan,Submitted Per Provisions of 10CFR50.54(p) ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20206U3641999-05-19019 May 1999 Confirms Plans to Conduct Routine Mgt Meeting on 990630 in Lisle,Il Re Recent Plant Performance & Lessons Learned from Unit 2 Restart ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 1999-09-08
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Text
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Insurance Administrator - W) '
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Coninonwealth Edison Company Post Office Box 767 r.hicago, IL 60690
Dear Mr. Oster:
Enclosed are six (6) copies of amendments modifying the location descriptions ,
for the Dresden, LaSalle and Byron Stations to conform to the locations incorporated in the facility forms for the respective plants. Please sign all of the copies and return one signed copy of each amendment to us.
Ira Dinitz Office of State Programs -
Enclosure:
As stated f
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50-237 IDinitz r/f 50-249 AMENDMENT TO INDEMNITY AGREEMENT B-10 AMENDMENT NO. 23 Effective OCT 15 28+ , Indemnity Agreement No. B-10 between Commonwealth' Edison Company and the Atomic Energy Commission, dated December 14, 1961, as amended, is hereby further amended as follows:
Item 4 of the Attachment to the Indemnity Agreement is deleted in its entirety and the following substituted therefor:
Item 4 - Location All of the premises including the land and all buildings and structures of Commonwealth Edison Company's Dresden Nuclear Station (including but not limited to Units 1, 2 and 3) within the plant-security fence and the switchyards adjacent to but not enclo;ed by the plant security fence, all located in Goose Lake Township, Grundy County, Illinois.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION u huk/// w!r Jerbme Saltzman, Assistant Ddrector State and Licensee Relations Office of State Programs Accepted , 1985 By COMMONWEALTH EDISON COMPANY r &m f emce, .LR P ,,LR 0,P k SLRI,,5man,,,, [,' , , , , , , , , , , , , , , , , , , , , , , , , , ,, , , , , , , , , , , , , , , , , , , , , , , , , , , , ,
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. Docket No. 50-454 AMENDMENT TO INDEMNITY AGREEMENT B-97 AMENDMENT NO. 4 Effective darch 1, 1985, Indemnity Agreement No. B-97, between Commonwealth Edison Company and the Nuclear Regulatory Commission, dated May 6, 1983, as amended, is hereby further amended as follows:
Item 4 of the Attachment to the indemnity agreements deleted in its entirtty and the following substituted therefor:
Item 4 - Location All of the premises including the land and all buildings and structures of Commonwealth Edison Company's Byron Nuclear Station (including but not limited to Units 1 and 2, the transmission and pipeline corridor to the Rock River and the switchyards of Units 1 and 2) within the area bounded by the plant fencing and the railroad spur line.on the northern perimeter. The site is located 2.2 miles east of the Rock River and 3.7 miles southeast of the City of Byron, Rockvale Township, Ogle County, Illinois.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Jerome Saltzman, Assistant Director State and Licensee Relations ~ .
Office of State Programs Accepted By' C0m0NWE4LT'l EDIS0h COMPANY fI ' P nc .e LKTOSP LR: SLR:0 i omc., ........Q..S
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. Ec ronu ais 00M NRCM 0HO OFFICIAL RECORD COPY bsom ,,u-mm
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Docket Nos. 50-373 50-374 AMENDMENT TO INDEMNITY AGREEMENT NO. B-84 AMENDMENT NO. 5 Effective January 1,-1985, Indemnity Agreement No. B-84, between Commonwealth Edison Company and the Nuclear Regulatory Commission, dated September 25,
- 1978, as amended, is hereby further amended as follows:
Item 4 of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefore:
Item 4 - Location All of the premises including the land and all buildings and structures of Commonwealth Edison Company's LaSalle County Station (including but not limited to Units 1 and 2) within the plant security fence and also including the discharge structure. The LaSalle County Station is located on County Highway No. 6 in Brookfield Township in the southeast corner of LaSalle County, (northeastern) Illinois, approximately 11 miles southeast of Ottawa, 11 miles northeast of Streator and 4 miles west of the Grundy. County
! border.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION s
- Jerome Saltzman, Assistant Director State and Licensee Relations Office of State Programs Accepted By COMMONWEALTH EDISON COMPANY
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