ML19339B240
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| ML19339B240 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 08/22/1980 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8011060560 | |
| Download: ML19339B240 (2) | |
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 ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,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 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 ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 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 ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed 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 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 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 ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required 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 BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 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 ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle 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 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy 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.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr 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 ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 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) BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted 1999-09-08 Category:INCOMING CORRESPONDENCE 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) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes 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 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed 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) BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 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 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle 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.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr 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 ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 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 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted 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 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 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) 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 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 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 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999 Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5 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 ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs 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 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 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 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 05000457/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed1999-05-21021 May 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed 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 ML20207E9831999-05-18018 May 1999 Forwards Copy of Commonwealth Edison Co EP Exercise Evaluation Objectives for 1999 Byron Station Annual EP Exercise,Which Will Be Conducted on 990825.Without Encl ML20206T3351999-05-17017 May 1999 Provides Written follow-up of Request for NOED Re Extension of Shutdown Requirement of TS Limiting Condition for Operation 3.0.3.Page 9 of 9 of Incoming Submittal Not Included ML20206N7861999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Braidwood Station. Rept Contains Info Associated with Stations Radiological Environ & Meteorological Monitoring Programs ML20206Q8521999-05-13013 May 1999 Submits Rept on Numbers of Tubes Plugged or Repaired During SG Inservice Insp Activities Conducted During Plant Seventh Refueling outage,A2R07,per TS 5.6.9 ML20206N8551999-05-11011 May 1999 Forwards 1998 Annual Radioactive Environ Operating Rept for Byron Station. Rept Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Site ML20210C7221999-05-0303 May 1999 Forwards Initial License Exam Matls for Review & Approval. Exam Scheduled for Wk of 990607 ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206U3351999-04-30030 April 1999 Forwards Evaluation of Matter Described in Re Byron Station.Concludes That Use of Overtime at Byron Station Was Controlled IAW Administrative Requirements & Mgt Expectations Established to Meet Overtime Requirement of TS 1999-09-08 Category:UTILITY TO NRC MONTHYEARML20059K6741990-09-17017 September 1990
[Table view]Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided ML20059K5081990-09-14014 September 1990 Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990 ML20059L6611990-09-10010 September 1990 Forwards Byron Station Units 1 & 2 Inservice Insp Program ML20064A3751990-08-24024 August 1990 Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept ML20064A3681990-08-24024 August 1990 Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA ML20064A0181990-08-16016 August 1990 Submits Supplemental Response to NRC Bulletin 88-008,Suppls 1 & 2.Surveillance Testing Revealed No Leakage,Therefore Charging Pump to Cold Leg Outage Injection Lines Would Not Be Subjected to Excessive Thermal Stresses ML20059A3991990-08-15015 August 1990 Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program ML20063Q1051990-08-10010 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2 ML20058N0551990-08-0707 August 1990 Provides Supplemental Response to NRC Bulletin 88-008, Suppls 1 & 2.Surveillance Testing Performed Revealed No Leakage,Therefore,Charging Pump to Cold Leg Injection Lines Would Not Be Subjected to Excessive Thermal Stresses ML20056A3351990-08-0202 August 1990 Responds to NRC Bulletin 88-009 Requesting That Addressees Establish & Implement Insp Program to Periodically Confirm in-core Neutron Power Reactors.All Timble Tubes Used at Plant Inspected & 18 Recorded Evidence of Degradation ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055J1221990-07-25025 July 1990 Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary ML20055J1261990-07-25025 July 1990 Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses ML20055H0291990-07-17017 July 1990 Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990 ML20055G3251990-07-16016 July 1990 Responds to SALP Board Repts 50-454/90-01 & 50-455/90-01 for Reporting Period Nov 1988 - Mar 1990.Effort Will Be Made to Continue High Level of Performance in Areas of Radiological Controls,Plant Operations,Emergency Preparedness & Security ML20044A9621990-07-13013 July 1990 Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc ML20055G4631990-07-13013 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-456/90-08 & 50-457/90-08.Corrective Actions:Discrepancy Record for Cable Generated & Cable That Had Been Previously Approved for Use on Solenoid Obtained & Installed ML20044B1411990-07-12012 July 1990 Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request ML20044B2141990-07-11011 July 1990 Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification ML20044B2081990-07-11011 July 1990 Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl ML20044A9521990-07-10010 July 1990 Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage ML20044B2871990-07-0909 July 1990 Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original Submittal ML20055D4811990-06-29029 June 1990 Discusses Revised Schedule for Implementation of Generic Ltr 89-04 Re Frequently Identified Weaknesses of Inservice Testing Programs.All Procedure Revs Have Either Been Approved or Drafted & in Onsite Review & Approval Process ML20044A7991990-06-29029 June 1990 Forwards Description of Change Re Design of Containment Hydrogen Monitoring Sys,Per 900517 Request.Util Proposing Alternative Design Ensuring Containment & Hydrogen Monitoring Sys Operability in Event of Power Loss ML20055D2951990-06-22022 June 1990 Discusses Results of 900529-0607 Requalification Exam.Based on Results of Exam,Station Removed/Prohibited Both Shift & Staff Teams & JPM Failure from License Duties.Shift Team Placed in Remediation Program from 900611-14 ML20058K3521990-06-22022 June 1990 Requests Withdrawal of 900315 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Specs 3.8.1.1 & 4.8.1.1.2 to Clarify How Gradual Loading of Diesel Generator Applied to Minimize Mechanical Stress on Diesel ML20056A0361990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-456/90-10 & 50-457/90-11.Corrective Action:Valve 2CS021b Returned & Locked in Throttle Position & Out of Svc Form Bwap 330-1T4 Modified ML20043G5851990-06-0808 June 1990 Forwards Repts Re Valid & Invalid Test Failures Experienced on Diesel Generator (DG) 1DG01KB,1 Valid Test Failure on DG 2DGO1KA & 2 Invalid Test Failures Experienced on DG 2AGO1KB ML20043D3141990-06-0101 June 1990 Forwards Rev 18 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043D3151990-06-0101 June 1990 Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043E3141990-05-31031 May 1990 Withdraws 880302 Application for Amend to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,changing Tech Spec 4.6.1.6.1.d to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin,Due to Insufficient Available Data ML20043F4731990-05-30030 May 1990 Forwards Suppl to 881130 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Changes Requested Per Generic Ltr 87-09,to Remove Unnecessary Restrictions on Operational Mode Changes & Prevent Plant Shutdowns ML20043C8641990-05-29029 May 1990 Forwards Rept of Local Leakage Rate Test Results for Third Refueling Outage.Leakage Rates of Six Valves Identified as Contributing to Failure of Max Pathway Limit ML20043B7771990-05-23023 May 1990 Forwards Endorsement 9 to Nelia & Maelu Certificates N-108 & M-108 & Endorsement 8 to Nelia & Maelu Certificates N-115 & M-115 ML20043B7691990-05-23023 May 1990 Forwards Endorsement 11 to Nelia & Maelu Certificates N-93 & M-93 & Endorsement 9 to Nelia & Maelu Certificates N-101 & M-101 ML20043A9161990-05-16016 May 1990 Provides Advanced Notification of Change That Will Be Made to Fire Protection Rept Pages 2.2-18 & 2.3-14 ML20043C2811990-05-15015 May 1990 Responds to NRC 900416 Ltr Re Violations Noted in Insp Repts 50-456/90-09 & 50-457/90-09.Corrective Actions:Gas Partitioners Tested Following Maint During Mar 1990 & Tailgate Training Session Will Be Held ML20043A6391990-05-11011 May 1990 Submits Revised Schedule for Implementation of Generic Ltr 89-04 Guidance.Rev to Procedures for Check Valve & Stroke Time Testing of power-operated Valves Will Be Completed by 900629 ML20043A2891990-05-10010 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for Byron Nuclear Power Station ML20042G7111990-05-0707 May 1990 Responds to NRC Questions Re leak-before-break Licensing Submittal for Stainless Steel Piping.Kerotest Valves in Rh Sys Will Be Replaced in Byron Unit 2 During Next Refueling Outage Scheduled to Begin on 900901 ML20042F6851990-05-0404 May 1990 Requests Resolution of Util 870429,880202 & 0921 & 890130 Submittals Re Containment Integrated Leak Rate Testing in Response to Insp Repts 50-454/86-35 & 50-455/86-22 by 900608 ML20042F6771990-05-0303 May 1990 Advises NRC of Util Plans Re Facility Cycle 2 Reload Core. Plant Cycle 2 Reload Design,Including Development of Core Operating Limits Has Been Generated by Util Using NRC Approved Methodology,Per WCAP-9272-P-A ML20042G3591990-04-30030 April 1990 Forwards Errata to Radioactive Effluent Rept for Jul-Dec 1989,including Info Re Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor ML20042E9601990-04-30030 April 1990 Forwards Response to NRC 900327 Ltr Re Violations Noted in Insp Repts 50-454/90-09 & 50-455/90-08.Response Withheld (Ref 10CFR73.21) ML20055C5761990-04-30030 April 1990 Forwards Results of Investigation in Response to Allegation RIII-90-A-0011 Re Fitness for Duty.W/O Encl ML20042E9111990-04-25025 April 1990 Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. ML20042F2681990-04-18018 April 1990 Provides Supplemental Response to Violation Noted in Insp Repts 50-456/89-21 & 50-457/89-21 Re Safeguards Info.Util Request Extension of 891010 Commitment Re Reviews of Plants. List of Corrective Actions Will Be Submitted by 900601 ML20042F0241990-03-28028 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML20012D8671990-03-21021 March 1990 Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date ML20012E1081990-03-21021 March 1990 Forwards Calculations Verifying Operability of Facility Dc Battery 111 W/Only 57 of 58 Cells Functional & Onsite Review Notes,Per Request 1990-09-17 |
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1
[/ b' i Comm:nwe:lth Edison Ore First Nat:cnal Plaza Cmcap m.no s
- Accress Aeply to Post Oftce Bon 767 Chicago I!hnois 60690 August 22, 1980 Mr. James G. Keppler, Director Directorate of Inspection ano Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Byron Statico Units 1 and 2 Braidwood Station Units 1 and 2 Construction Re-work NRC Docket .v o s . 50-454, 50-455, 50-456, and 50-457 Reference (a): August 15. 1980 letter from G. Fiorelli to C. Reed transmitting IE Inspection Report Nos. 50-454/80-13, 50-455/80-12, 50-456/80-07, and 50-457/80-07.
Dear Mr. Keppler:
As indicated in Reference (a), a meeting was held between NRC Region III and Commonwealth Edison Company personnel to discuss NRC concerns regarding significant construction re-work at Byron and in part, at the Braidwood and LaSalle power plants. At this meeting Commonwealth Edison committed to perform an in-depth examination and evaluation of its design / engineering organization and function, and to provide a comprehensive evaluation of the conditions and circumstances which have led to certain areas of significant construction re-work at Byron Station. The scope of tnis examination and evaluation including current status follows.
SuDsequent to the aforementioned meeting, Commonwealth Edison began a two phase program to determine the extent of and causes for re ork on safety-related systems. The initial phase consisted of examining the Safety Injection (SI) System. O f tne 158 spools installed, 80 (51%) have been reworked.
the rework indicates that the reasons for rework Acan detailed review of be categorized into six general areas divided among these areas. with the amount of rework nearly equally The general areas are:
- 1) Field interference;
- 2) Design changes; 1
8011osoJGO Q
C;mm:nw ;lth Edi;:n i
Mr. James G. Keppler, Director August 22, 1980 Page 2
- 3) Field error;
- 4) Hanger lugs;
- 5) Convenience cuts; and
- 6) Other, such as instrument connections, faorication of piping in tne field, etc.
Of these general areas only two can ne attributed to design - design changes and field interference. Although field interference coul0 be related to field installation, for purposes of this evaluation all reworx due to field interference nas assumed to relate to design proolems. Thus, in summary about one-third or 17% of the rework associated with the SI system coulo De attributed to the design function.
In order to insure that a sufficient data base exists oefore drawing any conclusions regarding causes for rework, Commonwealth Edison intends to perform a similar examination of tne rework on two auditional systems - tne Component Cooling (CC) System and Reactor Coolant System (RCS). These two systems were chosen Decause the CC system, which has a large number of spools installed (364), has a significant rework rate, 66%; whereas the RCS system, which has a smaller number of spools installeo (91), has a lon rework rate, 14%. In addition, all three of these systems have a variety of piping including carbon and stainless steel.
Currently, Commonwealth Edison expects this examination and categorization to be completec within two or three months. Once the categorizations have been made, the second phase of this program will be inaugurated. This phase n'i l l involve two paralle2 efforts oy Engineering and Quality Assurance. Engineering will examine the reaors items associated nith cesign to ascertain their causes. The original drawings through all revisions will ce reviewed. The QA oepartment will verify, in parallel, that all the rework followed the appropriately required documentation through both the design control and design change phases.
Commonwealth Edison will review the results of Dotn phases of this review and will initiate appropriate changes, if deemed necessary.
Please address any questions that you may have concerning this matter to this office.
Very truly yours,
\
m_ Nsa ~ ~
Cordell Reed Vice President Nuclear Operations 6230A
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