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Category:CORRESPONDENCE-LETTERS
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 ML20217P6171999-10-21021 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) 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 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 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 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 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 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 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 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 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 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
[Table view] Category:INCOMING CORRESPONDENCE
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) 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 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 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 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 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 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
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/ s ' Commonwealth Edison f 14 1400 Opus Plice f ,\ Downers Grove, tiiinois 60515 January 7,1994 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission -
Washington, D. C. 20555 Document Contml Desk
Subject:
Supplemental Infomiation Regarding the September 2,1993, Technical Specification Amendment Pertaining to the Electrical Power System, D. C. Sources Byron Station Units I and 2 NPF-37/66; NRC Docket Nos. 50-454/455 Braidwood Station Units 1 and 2 -
NPF-73/77; NRC Docket Nos. 50-456/457 ;
References:
- 1) D. Saccomando letter to Dr. Murley dated September 2,1993, transmitting pmposed revision to Braidwood and Bymn Stations Technical Specifications Pertaining to the Electrical Power System, D.C. Sources t
- 2) Teleconference between Commonwealth Edison Company (CECO) and the Nuclear Regulatory Commission (NRC) on December 22,1993, regarding the proposed Technical Specification pertaining to the Electrical Power System, D.C. Sources Commonwealth Edison Company (CECO) is providing this supplemental information to NRR to n vise portions of Section D,4,(Impact of Changes), of Attachment "A",(Description and Safety Analysis of Proposed Changes), in CECO's Technical Specification amendrnent submittal for the Class IE 125 volt Battery Replacement Modifications at Byron and Braidwood Stations. This supplement is .
intended to correct and clarify the discussion associated with our submittal and does not alter the proposed changes to the Technical Specification or Technical Specification Bases.
Section D.4 of the reference Technical Specification Amendment submittal discusses battery sizing. The submittal presently states, in part:
" . The AT&T battery sizing was then selected based on having sufficient capacity to energize the design basis DC loads for an operating unit with the IEEE-485 design margin of -
15% while maintaining the desired limited DC load of 100 amps for a shutdown unit. The sizing of the AT&T battery is conservative compared to the sizing of the Gould battery ;
because the cmsstie load limit of 63 amps for the Gould battery utilizes a portion of the IEEE-48515% design margin."
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\td l 9401240073 DR 94did7 .
ADOCK 05000454 PDR y
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. Dr. T.E. Murley - January 7,1994- :!
i CECO would like to replxe this paragraph with the following: ,
. The AT&T battery sizing was then selected based on having sufficient capacity to energize f the design basis DC loads for an operating unit while carrying the desimd limited DC load of 1 100 amps for a shutdown unit and still maintaining sufficient design margin for future load l growth. The remaining design margin in the AT&T battery is higher than that currently; available for the Gould battery, even though the 63 amp crosstie load has been increased to ,
100 amps " !
This revision is necessary because the actual design margin of 15% as referenced in Section :
D.4 has been revised to range from 4.7% to 10.8% depending on the station and electrical division l being considered.
CECO believes that the AT&T batteries have been conservatively sized and pmdently .j designed. Attxhment 1 provides additional infonnation conceming battery sizing. As requested '
during the reference teleconference call, we are also providing a discussion of the events leading up .;
to this supplemental response and portions of the appropriate calculations which support the design of l the new batteries at minimum allowable tenninal voltages of 105 V and 107.88 V. (See Attachments i 2,3 and 4 respectively)
.t Once again, this supplement is intended to correct and clarify the discussion associated with - !
our submittal and does not alter the proposed changes to the Technical Specification, its bases or the associated significant hazards discussion. Commonwealth Edison arologizes for any inconvenience :
that was caused by amending Attachment "A" CECO has reviewec the submitted amendment, the j battery design related to this modification and the calculations and considers them to be complete and j finalized. We are confident at this time that there are no outstanding isses. We are currently .i ieviewing the events involved in the preparation of this amendment to identify any actions which j would pmelude a similar recurrence.
i Please address any further comments or questions regarding this matter to this office.
Sin rely, M~h pcwwk Denise M. Sace ando Nuclear Licensing Administrator l Attachments l t
cc: R.' Assa, Braidwood Pmject Manager - NRR .l H. Peterson, Senior Resident Inspector - Byron l 4
S.. Dupont, Senior Resident Inspector - Braidwood l
. J. Martin, Regional Administrator - Region 111 !
Office of Nuclear Facility Safety - IDNS l i
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F t=
.i Attachment 1 The reduction of the design margin will not have a detrimental effect on the design of the plant. The design margin, also known as capacity margin, of 10%-15% is recommended by IEEE Std. 485 as a prudent design practice when sizing a new battery. It is intended to allow for unforeseen additions to the DC system and less than optimum operating conditions of the battery due to imptuper mainte-nance, recent discharge, or ambient temperatures lower than anticipated, or both. IEEE Std. 485 is !
applicable to generating stations and substations in both the nuclear and non-nuclear industries. While i these variables are present in the electric industry as a whole, the administrative and design controls present at Byron and Braidwood Nuclear Stations preclude their occurrence. ;
The aging factor used in the Byrun and Braidwood List ISH cell battery design is very conservative !
and could have been used to pmvide additional inargin. The Byron and Braidwood Technical ,
Specifications require the battery is capable of delivering 80% of mted capacity when subjected to a - 'l performance discharge test every 60 months. In addition. IEEE Std. 450,(Recommended Practice for :
Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations), recommends that a battery be mplaced when its actual capacity drops to 80% of its >
nominal rating. Therefore, the battesy's rated caprity should be at least 125% of the load expected at the end of its service life. This increase is nonnally referred to as the 1.25 aging factor in battesy ;
sizing calculations. Since receiving the discharge data to an end voltage of 1.86 VPC from AT&T, ;
CECO has perfonned battery sizing calculations that demonstrate that the List ISH cells will meet the ,
design requircraents of the DC systems with a minimum allowable batteiy tenninal voltage of 107.88 VDC (See Attachment 3). An aging factor of 1.25 was maintained as well as the minimum electm- ;
lyte temperature of 60 degrees F. Maintaining an aging factor of 1.25 for the List ISH cells is ;
considered very conservative. This aging fxtor is intended to account for the loss of capacity experi- ;
enced by typical lead acid (lead calcium and lead antimony) storage cells over time. Based on the :
results of AT&T accelerated life testing, the capacity of AT&T Round cells has been demonstrated to l inemase with age. This is a result of the design of the round cell (plate configuration, stacking of the' plates horizontally, and pure lead plates versus plates constmeted of lead calcium or lead antimony i alloys). The 1.25 aging factor for the List ISil cell was included in the sizing calculations to maintain i compliance with the Byron and Braidwood Technical Specifications which state that the battery is ;
capable of delivering 80% of rated capacity when subjected to a perfonnance discharge test every 60 !
months and the battery replacement recommendations of IEEE Std. 450. By incorporating an aging ;
fxtor of 1.25 into the Bymn and Braidwood Class IE 125 volt List ISH cell battery sizing calcula- >
tions, the batteries will have 25% additional capacity fmm what is mquired to meet the DBA loads. -
IEEE P485 Draft, presently at the IEEE Standards Boani for approval, addresses the issue of aging i factors in sizing different types of lead acid storage batteries. This revision to IEEE Std. 485 states that them are exceptions conceming the use of an aging factor of 1.25 when sizing a lead acid battery. ,
Depending on the cell design (e.g. Plante cells) an aging factor of L0 may be used pmvided the cell capacity is capable of remaining at or above 100% of the manufacturer's rating throughout the service :
life of the battery and that the battery be replaced when its capacity drops below 100% of the manufacturer's rating.
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Attxhment 1 (Continued)
In conclusion, a decrease in the design margin to lesr than 15% is the result of increasing the minimum allowable battery tenninal voltage. The use of the 10%-15% design margin in sizing a new battery installation is not a Technical Specification requirement rather it is a recommended practice based on IEEE Std. 485. CECO administrative controls preclude the variables that require the use of a design margin from occurring. Thus, maintaining a 15% design margin throughout the life of the battery is not required. CECO believes that the remaining design margin is sufficient for future load additions and that the proposed increase in minimum allowable battery tenninal voltage can be considered a load addition that utilized pan of the original 15% design margin that was available when the minimum allowable battery temiinal voltage was at 105 VDC. In addition CECO has maintained an aging factor of 1.25 as opposed to an aging factor of 1.0 thereby pruviding additional capacity margin. By raising the minimum allowable battery temiinal voltage from 105 volts to 107.88 volts, CECO has been pruactive in resolving the voltage drop conce-m of the instmment power inveners and at the same time has increased the operating reliability of the inveners during a DBA.
By utilizing the excess capacity of the new Class lE 125 volt batteries, CECO will have provided both a technically and economically acceptable solution to this concem. CECO has fully demonstrated that the List ISil cell is properly sized with ample capacity margin for the Class IE 125 VDC applications at Byron and Braidwood Stations and meets the intent of IEEE Std. 485.
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1 Attachment 2 f i
The Byron and Braidwood Class IE 125 volt batteries are presently scheduled to be replaced with AT&T List IS11 Round Cell batteries,(referred to as the List ISH cell in this response). Each battery !'
will consist of 58 cells and have a guaranteed minimum rating of 1760 ampere-hours at the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> discharge rate to an end voltage of 1.75 volts per cell, (VPC). The nominal specific gravity of the cells is 1300. The List ISH cell is the largest ampere-hour capacity mund cell available. ,
During the conceptual design stage of the battery replacement project, the design basis for the new l batteries was detennined to be the ability to supply the design basis accident (DBA) loads of the DC i system plus 100 amps of cmsstie load to the other unit without load shedding while maintaining a minimum battery tenninal voltage of 105 V,(1.81 VPC). Initial battery sizing calculations were - i peifonned following the recommendations of IEEE Std. 485 using a minimum electmlyte temperature l of 60 degrees F, a design margin of 15% and an aging factor of 1.25. This would assure that battery j capacity would be 15% greater than that required to supply the DBA and crosstie loads while main-taining the battery voltage above 105 VDC assuming the battery capacity has dropped to an end-of-life value of 80% of the manufacturers guaranteed minimum rating, and the average electrolyte .
temperatum of the battery was at the 60 degrees F Technical Specification Limit. :
'l Concurrent with the design pmcess of the battery mplacement project, CECO identified i. voltage dmp concem regarding the 7.5 KVA instmment power inverters during pmparation for the Bymn and .
j Braidwood EDSFIs. The inveners are specified to operate at a minimum input voltage of 105 VDC. ;
During full load operation, a 2.6 volt drop exists between the battery and the DC input of the invener, i Therefore,107.6 volts is required at the battery in order to ensure proper operation of the inveners :
during a DBA. A voltage dmp calculation completed in May of 1993 demonstrated the voltage of the .
existing batteries would not drop below this 107.6 VDC limit. .'l i
Because this concem did not surface until after completion of initial battery sizing calculations and award of the contract for the replacement batteries, the CECO specification for the replacement batteries required ampere-hour capacity to meet the design requirements of the DC system with a ~!
minimum battery tenninal voltage of 105 VDC. Once the voltage dmp concem was identified, CECO (
considered several altematives to resolve this issue. These included, testing of the inverters to deter- _;
mine if the inveners would maintain pmper output voltage mgulation at DC input voltages less than J
105 VDC; increasing the size of the feeder cable from the distribution bus to the invener to reduce the voltage dmp; and reviewing the DC system loads to eliminate conservatism in the pmsent design. :
Recognizing these altematives may not yield results in the time frame required to support the ;
installation of new batteries, CECO also pursued obtaining the data needed to complete the design l calculations with a 107.6 VDC minimum voltage. ..
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Attxhment 2 (Continued)
In order to accomplish this, cell discharge currents to an end voltage of 1.86 VPC (107.6 volts + 58 '
cells) was required. This data would be used to detennine if the List ISH cells had the required L
capacity to meet the design requirements of the DC systems with an end voltage of 107.88 VDC, (1.86 VPC X 58 cells). It was discovered that AT&T did not have published discharge data to an end .
voltage of 1.86 VPC but agreed to perfonn discharge tests on the List ISH cell in order to detennine cell discharge characteristics to an end voltage of 1.86 VPC. The approved data was provided to CECO in November of 1993. Subsequently, this data was incorporated into design calculations to determine the effect of raising the minimum allowable battery tenninal voltage At this time it was
,. discovered that by raising the minimum allowable battery tenninal voltage to 107.88 VPC, part of the l design margin was sacrificed.
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