ML20207L186
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| ML20207L186 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/13/1988 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| References | |
| EA-88-266, NUDOCS 8810170220 | |
| Download: ML20207L186 (2) | |
Similar Documents at Byron | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999
[Table view]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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl 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 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) ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps 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 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 ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed 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 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs 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 ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions 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 ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed 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 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 Category:NRC TO UTILITY MONTHYEARML20217A1551990-11-14014 November 1990
[Table view]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 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 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 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 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 ML20059E1141990-08-30030 August 1990 Forwards Safety Insp Repts 50-454/90-16 & 50-455/90-15 on 900814-17.No Violations Noted ML20059B4271990-08-17017 August 1990 Forwards Safety Insp Repts 50-454/90-17 & 50-455/90-16 on 900701-0811.No Violations Noted 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 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 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 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 ML20055D0251990-06-28028 June 1990 Forwards Safety Insp Repts 50-454/90-15 & 50-455/90-14 on 900611-14.No Violations Noted 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 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 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 ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20246M5921989-08-29029 August 1989 Forwards Safety Insp Repts 50-454/89-16 & 50-455/89-18 on 890701-0819 & Notice of Violation ML20246H8321989-08-28028 August 1989 Advises That plant-specific Reactor Coolant Pump Trip Setpoint Development,Per TMI Action Plan Item II.K.3.5 Acceptable,Based on NRC Approval of Westinghouse Owners Group Methodology Per Generic Ltr 85-12 ML20246L5111989-08-15015 August 1989 Advises That No Violations of NRC Requirements Identified in Review & Allegation RIII-88-A-0112 Considered Closed IR 05000455/19890061989-08-0909 August 1989 Advises That Violations 50-455/89-06-02 & 50-455/89-06-03 Reclassified as Severity Level V Based on 890522 & 0711 Addl Info & Minimal Safety Significance of Specific Example ML20248D5471989-08-0707 August 1989 Forwards SER Accepting Util 881130 Rept Entitled, Seismic Qualification of Byron Deep Wells & Addl Info Submitted on 890411,0427 & 0523.Related 890524 Amend Request Still Under Review ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20245E7601989-08-0303 August 1989 Notifies That Written & Oral Operator & Senior Operator Licensing Exams Scheduled for Wk of 891127.Encl Reference Matl Requested within 60 Days Prior to Exam Date ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20246L6731989-07-11011 July 1989 Forwards Safety Insp Repts 50-454/89-14 & 50-455/89-16 on 890518-0630.No Violations Noted.Open Item Noted Re Testing of Safety Injection Circuitry in Remote Shutdown Panel ML20246K9541989-07-10010 July 1989 Forwards Safety Insp Repts 50-454/89-15 & 50-455/89-17 on 890612-20.No Violations Noted ML20246L3251989-07-0707 July 1989 Ack Receipt of 890613 Submittal of Rev 3c to Emergency Plan, Including Partial Rev to Emergency Action Levels in Table Bya 5-1.Plan Considered Acceptable When Revised Page Bya 5-1.16 Received by Region III ML20246D7091989-07-0606 July 1989 Ack Receipt of Re Allegation Discussed in NRC Concerning Vital Area Door Not Being Checked at Required Frequency.Investigation Supports Conclusion That Allegation RIII-89-A-0055 Unsubstantiated ML20246B5991989-07-0505 July 1989 Ack Receipt of & Payment for Civil Penalty in Amount of $50,000 Proposed in NRC ML20246C2421989-06-28028 June 1989 Expresses Appreciation for Hosting Operational Safety Review Team (Osart) at Plant.Comments Would Be Welcomed by Commission on Osart Insp ML20246E1871989-06-28028 June 1989 Advises That Changes to Security Plan Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20246P9211989-06-27027 June 1989 Requests That Util Fully Analyze Allegation RIII-88-A-0112 & Take Appropriate Actions to Resolve Issue ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20244D8131989-06-13013 June 1989 Forwards SER Accepting Util ATWS Mitigating Sys Actuation Circuitry Designs & Compliance W/Atws Rule (10CFR50.62). Conclusion Based on Certain Human Factors Engineering Reviews ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20244C4941989-06-0606 June 1989 Forwards Safety Insp Repts 50-454/89-10 & 50-455/89-12 on 890401-0517.No Violations Noted.Physical Inoperability of Diesel Generator 1A Discussed in Rept ML20244A5471989-06-0202 June 1989 Responds to Requesting Reconsideration of Violation 3 Noted in Insp Repts 50-454/89-09 & 50-455/89-06. Violation Considered Valid.Issue Re Design Requirements Not Meeting Seismic Qualifications Needs Further Attention ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied 1990-09-25 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M2871999-10-21021 October 1999
[Table view]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 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 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 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 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 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 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 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 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 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 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) 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 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 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 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 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 ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us ML20206N4791999-05-13013 May 1999 Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date ML20206J1981999-05-0505 May 1999 Forwards Exam Answer Key for Forms a & B,Grading Results for Facility & Copies of Individual Answer Sheets for Each Individual Taking Gfes of Written Operator Licensing Exam Administered by NRC on 990407.Without Encls ML20206E7021999-05-0303 May 1999 Advises That Info Contained in Document Entitled, Licensing Rept for Sf Rack Installation at Byron & Braidwood Stations, HI-982083,will Be Withheld from Public Disclosure Per 10CFR2.790 ML20206D0361999-04-28028 April 1999 Confirms Plans to Have Meeting on 990527 in Lisle,Illinois to Discuss Results of Ceco Evaluation on Potential Chilling Effect Concern within Working Environ & Use of Overtime within Operations Dept Organization at Byron Station ML20205Q2621999-04-14014 April 1999 Forwards Insp Repts 50-454/99-03 & 50-455/99-03 on 990217-0329.Five Violations Identified & Treated as Ncvs. Expresses Continued Concern with Configuration Control & Human Performance Errors at Byron Station ML20206U3261999-03-29029 March 1999 Forwards RAI Re 981208 Response & Suppls to NRC Re Use of Overtime in Byron Station Operations Dept.Response Requested within 30 Days of Date of Ltr ML20196K8821999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990201 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Plant Issues Matrix & Insp Plan Encl ML20205B4901999-03-26026 March 1999 Forwards SER Authorizing Util 981022 Relief Requests 12R-24, Rev 0,which Requests Deferral of Rv shell-to-flange Vessel Weld Exam to End of Second 10-year Insp Interval,Pursuant to 10CFR50.55a(a)(3)(ii) & 12R-34,rev 0 ML20204G3641999-03-19019 March 1999 Forwards Safety Evaluation & Technical Ltr Rept Re Second 10-yr Interval ISI Request for Relief 12R-11,rev 2.Licensee Proposed Alternative to code-required Pressure Test Authorized for Current Interval ML20204E2631999-03-18018 March 1999 Discusses Review of Ceco Evaluation of Chilling Effect on Byron Station Personnel.Identified Number of Questions Re Ceco Findings & C/As.Requests Further Evaluation of Chilling Effect at Byron Be Conducted & Response to Encl Questions ML20204D1971999-03-16016 March 1999 Discusses Review of Revision 4Q to Portions of Licensee Emergency Plan Site Annex ML20204B6721999-03-12012 March 1999 Forwards Copy of Preliminary Accident Sequence Precursor Analysis of Operational Condition Discovered at Plant on 980912 ML20207K1861999-03-11011 March 1999 Discusses Review of Rev 4P to Portions of Byron Power Station EP Site Annex.Based on Determinations That Changes Do Not Decrease Effectiveness of EP & Plan Continues to Meet Standards of 10CFR50.47(b),NRC Approval Not Required ML20207J5201999-03-10010 March 1999 Forwards Insp Repts 50-454/99-02 & 50-455/99-02 on 990105-0216.No Violations Noted.Expresses Concern Re Trend of Configuration Control & Human Performance Errors at Byron Station ML20203G7981999-02-11011 February 1999 Forwards Insp Repts 50-454/99-01 & 50-455/99-01 on 990119-22.No Violations Noted.Insp Involved Exam of Maint & Engineering Related Activities for Electrical Circuit Breakers ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203C9861999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 52 to Security Plan.No NRC Approval Required ML20202H9401999-02-0303 February 1999 Informs That Update of Set Number 58 of UFSAR Has Been Completed.Confirmation Sheet Providing Update Encl ML20199H8561999-01-19019 January 1999 Discusses Insp Repts 50-454/98-25 & 50-455/98-25 on 981124-990104 & Forwards Nov.Violation Identified Involving Unacceptable Preconditioning of Stroke Time Testing of AFW Pump Discharge Valves ML20199E8861999-01-15015 January 1999 Discusses Two Unresolved Security Items Identified in Sections S3.b1 & S3.b2 of Insp Repts 50-454/98-03 & 50-455/98-03,dtd 980211.One Item Re Adequacy of Alarm Sys Testing When Two Alarm Zones Were Returned to Svc ML20198N8261998-12-30030 December 1998 Forwards Insp Repts 50-454/98-24 & 50-455/98-24 on 981130- 1204.No Violations Noted.Purpose of Insp Was to Determine If Licensed Operator Requalification Training Activities Conducted IAW with NRC Requirements ML20198J0211998-12-18018 December 1998 Forwards Insp Repts 50-454/98-20 & 50-455/98-20 on 981006- 1123.No Violations Noted ML20198F4451998-12-17017 December 1998 Forwards Insp Repts 50-454/98-23 & 50-455/98-23 on 981116-14.No Violations Noted.Purpose of Insp Was to Verify Accuracy of Licensee Response to Region III Questions Re Grid Stability ML20206N4431998-12-10010 December 1998 Forwards Security Insp Repts 50-454/98-22 & 50-455/98-22 on 981116-20.No Violations noted.Challenge-testing of Some Detection Equipment Showed Some Vulnerabilities That Util Indicated Would Be Corrected 1999-09-08 |
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OCO OCT t i 1988 EA 88-266 Docket fio. 50-454 Docket tio. 50-455 i
Comonwealth Edison Corrpany i ATTN: Mr. Cordell Reed l
l Senior Vice President Post Of' ice Box 767 Chicago, IL 60690 Gentlemen:
This confirns our plans as discussed on October 11, 1988, between Mr. R. Chrzanowski of your staff and Mr. J. M. Hinds, Jr. of this office for the NRC to reet with representatives of Conmonwealth Edison Company on October 21, 1988, at 10:00 a.m. (CDT) at the NRC Regional Office in Glen Ellyn, Illinois.
This meeting is an enforcement conference to discuss the events surrounding the loss of one train of the residual heat removal system while lowering the water level in the reactor coolant systrm on September 19, 1908, at the Byron Station. At the enforcement conference, you should be prepared to discuss (1) the training provided to shift personnel on the use of tygon tube level indication of reactor vessel I (RV) water level and the hydraulic coupling between the refueling cavity l water and the water level inside the RV, with the upper intervals l installed, prior to fuel movement; (2) the lack of procedural specification !
to monitor the RV level using the tygon hose level indication system; i (3) the generic comunications between shift personnel involved in I lowering RV level; (4) the shift management and control employed to resolve the difference of opinion between the NSO and EA on the accuracy and validity of the tygon hose level indication compared with tha refueling cavity actual water level; and (5) the training provided to shif t personnel on NRC issued Generic letters related to the use of tygon hose for level indication systems.
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Conrnonw.ealth Edison Company 2 OCT I 31988 We appreciate your cooperation in this matter, and we will gladly discuss any questions you have concerning this meeting.
Sincerely, ORIGINAt. SIGNE0 SY I. l. f E'*H Edward G. Greenman, Director Division of Reactor Projects cc: T. J. Maiman, Vice President, PWR Operations H. Bliss, Nuclear Licensing Manager R. Pleniewicz, Station Manager DCD/DCB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Byron Resident Inspector, RIII Braidwood D. W. Cassel, Jr. , Esq.
Richard Hubbard J. W. McCaffrey, Chief, Public Utilities Division Diane Chavez DAARE/ SAFE L. Olshan, NRR LPM H. S. Taylor, Quality Assurance Division bec: J. Lieberman, OE L. Chandler, 0GC F. Miraglia, NRR 1
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