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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased 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
[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 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
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r ATTACHMENT 2 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE 9709250170 970919 ,
PDR ADOCK 05000454, P PDR p.
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Onnmonwrahh Nimn Company
, 1400 Opp 11xe
. Downen Grow, il 60515 5'01 September 19,1997 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk APPLICATION FOR WITHHOLDING PROPRIETARY iNFORMATION FROM PUBLIC DISCLOSURE
Subject:
Calculation # ES1150-1, Rev. O.
The proprietary information for which withholding is being requested is further identified in Commonwealth Edison Company in the enclosed Affidavit signed t,y the owner of the proprietary information. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Commonwealth Edison Company.
Correspondence with respect to the proprietary aspects of the application for withholding and should be addressed to the undersigned.
Very truly yours, M,Mwm John Hosmer Engineering Vice President k:nla tgtmd raidoc:10 A Unioim Conyuny '
Commonwealth Edison Company AFFIDAVIT I, Kenneth Kostal, being duly sworn, depose and state as follows:
(1) I am Executive Vice President of Sargent and Lundy (S&L) and have been delegated the function of reviewing the confidential commercial information described in paragraph (3) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) Department Heads, and Resource Leaders are responsible for classifying (or delegating the classification) of proprietary or confidential information. These
. persons are most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge.
(3) The information sought to be withheld was developed by S&L, pertaining directly to Analysis of Ampacity Derating for Thermo-Lag and Darmatt Fire Wraps performed by S&L. S&L is the owner of such confidential commercial information and the related reports. Specifically this information includes:
(a) Calculation # ES1150-1, Rev. 0 (4) In making this application for withholding of such confidential commercial information, S&L relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA),5 USC S 552(b)(4), and NRC Regulations 10 CFR 99 9.17(a)(4), and 2.790(a)(4) for " commercial or financial information obtained from a person and privileged or confidential"(Exemption 4). The confidential commercial information should be withheld from disclosure under 10 CFR 9 2.790 (b)(4) for the following reasons:
(a) The information marked Proprietary or Confidential and is of a sort customarily held in confidence by S&L. Access to such documents within S&L is limited on a "need to know" basis. Disclosures outside S&L are limited to regulatory bodies or licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements; Ontahimd rai doc:II
4 (c) The information sought to be withheld is being submitted to the NRC in confidence; and (d) The information is not available in public sources.
(5) The calculation in paragraph (3) is a confidential compilation of information related to Analysis of Ampacity Derating for Thermo-Lag and Darmatt Fire Wraps. This calculation was developed in response to S&L '
internal reviews. The development of this calculation was undertaken by S&L at considerable cost and has considerable financial value to others, (6) Public disclusure of the information sought to be withheld is likely to cause substantial harm to S&L's competitive position and foreclose or reduce the availability of profit-making opportunities for such information. S&L's competitive advantage will be lost if its competitors are able to use the results of S&L experience to avoid fruitless avenues, or to normalize or verify their own process, or to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
State of Illinois )
) ss:
County of Cook )
Kenneth Kostal, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.
Executed at Chicago, Illinois, this /8 day of /MME1997. ,
$N L Kenneth K'ostal Executive Vice President Subscribed and sworn before me this /89sday of bC 1997.
= :::. - =- WrA<A+ $. bR i N6tary Public, State of Illinois
- OFFICIAL SEAL" Olsela F.Denton h Notary Public. State of1111 nots -
g Ny CcWa @S?"_f_$3_,
k:nla 19bv4 rai. doc t 2
ATTACHMEh /1 RESPONSE TO RAI k nla hbwd rai.&c4
Question 2.1: It appears that Comed's base case comparisons are not applied on a consistent basis. In particular, the licensee is comparing a calculated clad case ampacity limit to a base casa ampacity derived on a different basis. The estimates of fire barrier Ampacity Derating Factor (ADF) should be based on self-consistent treatment of the clad and base line cases. In Inis case, it is considered critical to assess both the clad and base line ampacity limits using a self-consl< tent thermalmodel. If the thermalmodelis used to predict the clad ampacity limits, then a
!bermalmodel ty!!y consistent with the clad case analysis should also be used to assess the base line ampacity limits as weII. The licensee is requested to implement a thermal model for the analysis of the base line case ampacity that is fully consistent witt, the its clad case analysis, and to then base its final ampacity derating assessments on a comparison of the clad and base line thermalcnalysis results.
Response: Consistent models have been applied to the base case open tray ampacity values and the base line ampacities for deriving the Ampacity Derating Factors (ADFs).
In Calculation BYR96-082 / BRW-96-194, Revision 0, ampacity factors were developed that were applied to the cable open tray ampacity values generated by the cable management program (SLICE) used at Byron and Braidwood, as discussed in reference 3. The resulting fire wrapped tray ampacities were compared to cable load currents to verify that cables are loaded within their ampacities. The SLICE program utilized the Stolpe/ICEA Model to generate the open tray ampacities for the cables at the routing points based on routing point depth of fill. The same Stolpe/ICEA Model was utilized in Calculation ESl150-1, Rev. O, which was used to provide the base line ampacities for deriving the ADFs. Therefore, consistency has been maintained between the thermal model used as a base line for developing the ADFs and the thermal model used to develop the open tray ampacities in the SLICE program, (to which the ADFs were applied to obtain the fire wrapped tray ampacity). Ensuring consistency between these two models is critical since it will ensure that the fire wrapped tray ampacity obtained by applyin0 the ADF to the Stolpe open tray ampacity is the same as the fire wrapped tray ampacity obtained by the fire wrappad tray thermal model. As discussed further in the response to Question 2.2, the methodology of Calculation ESl150-1, Revision 0 demonstrates that consistent approaches have been utilized.
The thermal model used to calculate fire wrapped tray ampacities was also based on and derived from the Stolpe model. The model used the same modeling assumptions for the cable mass in the tray, and the same general approach for radiation ar.d convection heat transfer. The model was expanded to contain the physical elements of the fire wrap material, and the heat transfer coefficients were refined to accommodate the new configurations described in reference 3. It is not necessary to implement an additional thermal model as requested, because the fire wrapped tmy model used is fundamentally consistent with the Stolpe model utilized for the base line and for the SLICE program.
Furthermore, the fire wrapped tray model was compared and verified against actual industry test results in Calculation BYR96-059 / G-70-96-092, enclosed with and discussed in reference 3. This verification provided assurance that the fire wrapped ampacities provided by the model are reliable as ampacity values, and not simply as relative values for deriving deratings. Therefore, the ADFs have been derived in a manner to ensure that when they are applied to the SLICE ampacities, the resulting ampacity is consistent with the validated fire wrapped tray thermal model.
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Question 2 2: The licensee has presented a table of heat intensity versus depth of fill values (Item 13 of page 13 of BYR96-082 /BRW 96194). This table is in apparent conflict with the heat intensity values cited by Stolpe and in the ICEA standard P-54-440. The cited values appear to modestly over state allowable heat intensity limits, and hence might lead to optimistic estimates of the cable ampacitylimits.
2.2.1 The licensee is requested to establish the basis for how this heat intensity table was developed and how it is applied in practice, and to reassess the ampacity limit calculations in light of this apparent discrepancy.
2.2.2 The licensee is also requested to provide the supporting calculation cited in BYR96-062 / BRW-96-194 as the basis for this table (i.e., Calculation ESl150-1, Revision 0).
Response: As requested, a copy of Calculation ESl150-1, Revision 0 is attached.
Calculation ESl150-1, Pevision 0 calculated the allowable heat intensity of a cable mass in cable tray, as was done by Stolpe and ICEA P 54-440 (NEMA WC 51). The tray represanted in the model is a solid bottom tray, which is the type of tray installed at Byron and Braidwood. As stated in the NRC staff review, there are two altemative definitions of depth of fill and two alternate definitions of the cable area that can be multiplied by the heat intensity to give the allowable cable heat generation. Each pair of definitions differs by a multiplier of (Pi)/4. Calculation ESl150-1 used the " square cable" definition of depth of fill, as is used in ICEA P-54-440. However, it used the "round cable" definition of the cable area to determine the allowable cable heat generation.
Calculation ESl150-1 gives a heat intensity of 2.095 W ft4 in.2 at a depth of fill of 2.473 inches and a heat intensity of 1.962 W ftd1n'* at a depth of fi!! of 2.594 inches.
Interpolating to obtain the heat intensity (HI) at a depth of fill of 2.5 inches:
(2~473 9~' 5) d HI = 2.095 + (2.473 - 2.594) x (1.962 - 2.095) = 2.065W l
The usameter of the 3/C, #6 AWG,600 V c6e used at Byron and Braidwood is 0.953 inches, so the appropriate cable arca (A) is:
2 2 A = f x 0.953 = 0.713in The cable resistance (CR) for #6 AWG 600 V cable:
CR = 0.0513 x 10~2O The calculated cable ampacity (l) is determined by:
i Hl x A
/= (Where 3 represents the number of conductors) 3xCR k:nl4 bybmt rai doc:6 l
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v 2.065 x 0.713 7 . = 30.93A 3 x (0.0513 x 10-2 )
The calculated value of 30.93 amperes is in agreement with the ampac ity va lue of 31.77 amperes calculated in the NRC staff review based on the ICEA standard, considering that the Comed ampacity is for a solid bottom cable tray and the ICEA ampacity is based on ladder type cable trays. It is expected that a solid bottom cable tray would result in a lower ampacity value. Therefore, the cited values do not over-state allowable heat intensity limits, and do not lead to optimistic estimates of the cable ampacity limits.
Question 2.3: The licensee cites in Item 2 on Page 12 of BYR96-082 /BRW-96-194 that the base line ampacity for a 3/C, #6 AWG, 600 V cable with a 2.S* depth of11llis 27.5 A. The basis for this value is not clear. SNL was unable to reproduce this limit using standard approaches to ampacity analysis given that the licensee has cited the ICEA definition as the basis for till depth calculations. The licensee is requested to describe, in detail, how this value was obtained, or attematively the subject caMulation should delete references to and reliance upon this value as the ' base line ampacity" for the cases examined.
Response: In addition to developing the Ampacity Derating Factors (ADFs),
Calculation BYR96-082 / BRW 96-194, Revision 0, determined a maximum cable tray depth of fill at which the ampacity of the cables in the fire wrapped tray would equal or exceed their maximum load current carrying capability. This approach was used as a screening process to identify cable tray routing points that require further ampacity evaluations. Evaluated cable tray routing points, with depths of fill that do not exceed this criterion, required no further analysis.
Included in the initial design of Byron and Braidwood was the development of a project ampacity table. The project ampacity table governed the selection of the cable sizes for the various power cables. The table was based on ICEA cable ampacity in an open l cable tray, deratad to account for cable tray covers. The significance of the project ampacity table amperage is that it represents the maximum load currents for the cables installed in the plant. The 27.5 A value for 3/C, #6 AWG,600 V cable is considered to be a representative value of cable ampacity for installations in the plant.
l The maximum depth of fill calculations determined a depth of fiP value of a wrapped tray where the ampacity of the cables would equal or exceed the amperage values
- given in the project ampacity table, used to select the cables at the time of design. in .
! ' this approach, the conductor temperature at all routing points with a depth of fill that is less than or equal to the project ampacity table value will be less than the rated temperature of the cable conductor. Therefore, no further analysis of these routing points was required. In this regard, the 27.5 A value was not used as a base line ampacity; instead it was used as a limiting value of full load current.
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In the calculation sections that develop the ADFs, the 27.5 A current value was also used as the amperage level at which the fire wrapped tray model was evaluated. It was the appropriate value to use since it represents the maximum expected cable full load condition for a cable of this size in the plant. In the methodology uss.iin these calculations, the 27.5 A value has not been relied upon to represent any industry standard or base line ampacity.
Question 2.4: Several references are made in BYR 96-082/BRW 96-194 to a 'SilTemp Sheet" but the fire barrier descriptions do not include a discussion of any such sheet used in the installation process. The licensee is requested to clarify if such a material is used in its fire barrier constructions.
Response: In the Mathcad 0 !culation BYR96-059 / G-70-96-092, enclosed with and discussed in reference ?, the cable tray from the industry test, used to validate the model included a SilTemp@ sheet in its construction. This SilTemp@ sheet value was
- maintained in the Ma'ncad file, as a part of the validation performed. In Calculation BYR-96-082/BRW-94194, which is also a Mathcad calculation, based on Calculation BYR96-059 / G-70-06-092, the SilTemp@ sheet was not included because this material is not installed in the Byron and Braidwood fire barrier constructions. The calculation sheet equations were modified to reflect the absence of the SilTemp@ layer. However, the text commentary referring to the SilTemp@ sheet remained in the calculation. This reference is not relevant and has no impact on the results of Calculation BYR96-059 /
G-70-96-092.
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