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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) 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 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 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 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 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 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 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 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) 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 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 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 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 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 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 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) 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 IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams 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 ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle 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 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 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-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 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 ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative 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 ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration 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 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 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 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 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 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 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-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 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 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 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 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 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 ML20206E3991999-04-29029 April 1999 Forwards 1998 Annual Environ Operating Rept & Listed Attachments Included in Rept.Without Encls ML20206C7901999-04-23023 April 1999 Provides Suppl Info Re Use of W Dynamic Rod Worth Measurement Technique,As Requested During 990413 Telcon.Rev Bars in right-hand Margin Identify Changes from Info Submitted by ML20206B3941999-04-21021 April 1999 Forwards Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors, for Byron & Braidwood Stations.Updated Info Re PCT for Limiting Small Break & Large Break LOCA Analysis Evaluations & Detailed Description of Errors ML20205S9621999-04-20020 April 1999 Responds to 981203 RAI Telcon Re SG Tube Rupture Analysis for Byron Station,Unit 2 & Braidwood Station,Unit 2.Addl Info & Subsequent Resolution of Issues Discussed During 990211 Telcon Are Documented in Encl ML20206B0821999-04-20020 April 1999 Requests to Reschedule Breaker Maint Insp for Either Wk of 990607 or One of Last Two Wks in Jul 1999,in Order to Better Accommodate Insp Activity ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20206B0251999-04-14014 April 1999 Forwards Reg Guide 1.16 Rept for Number of Personnel & Person-Rem by Work Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions ML20205K3581999-04-0606 April 1999 Submits Request to Reschedule Breaker Maint Insp for Braidwood Nuclear Power Station for Either Wk of 990607 or One of Last Two Wks in Jul 1999 ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20210C7181999-03-30030 March 1999 Forwards Integrated Exam Outline Which Plant Submitting for Review,Comment & Approval for Initial License Exam Scheduled for Wk of 990607 ML20205E6401999-03-26026 March 1999 Forwards Proprietary Ltr Re Notification of Corrected Dose Rept for One Individual,Per 1997 Annual Dose Repts for All Comed Nuclear Power Facilities,Submitted 970430.Proprietary Info Withheld ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207J4321999-03-0808 March 1999 Forwards Braidwood Station ISI Outage Rept for A1R07, Per Requirements of ASME Section Xi,Article IWA-6200 ML20205C6861999-03-0404 March 1999 Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219 1999-09-08
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' ~ J 1400 0 pus Place k ("11 Downers Grove, Illinois 60515 l
April 15, 1994 Mr. William Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Braidwood Station Units 1 and 2 Additional Information on Environmental Qualification of Okonite Tape Splices at Braidwood Station NRC Docket Nos. 50-456 and 50-457
Reference:
Teleconference between Commonwealth Edison Company (CECO) and the Nuclear Regulatory Commission (NRC) dated March 3, 1994, Regarding Additional Information Concerning Okonite Tape Splices As discussed during the reference teleconference between the Nuclear Regulatory Commission (NRC) and the Commonwealth Edison Company (CECO), CECO agreed to submit the attached information in response to the questions on splicing technique continuity at Braidwood Station.
Attachment 1, a letter from Okonite Company dated March 31, 1978, provides the basic splicing detail utilized at Braidwood Station. This detail is shown on Okonite drawing D-11547 which provides instructions for splicing 12/c#14 600V Okonite cable.
Commonwealth Edison's position in 1978 was to restrict the number of splices allowed during construction. This position is delineated in Sargent and Lundy letter dated December 11, 1978 (Attachment 2). In instances where control or instrumentation cables were " pulled short,"
the cables were terminated on terminal blocks and a new cable was installed from this terminal point to the end equipment. This position was reaffirmed, in a letter to the Braidwood site via Sargent and Lundy letter dated October 10, 1983 (see Attachment 3).
In August of 1983, note #76 was added to Sargent & Lundy drawing 6/20E-0-3390A Rev. AD (Attachment 4) and gave direction to tape butt splices similarily to Okonite instructions for taping pigtails splices on motor connections. Note #76 on drawing 6/20E-0-3390A Rev. AE (Attachment 5) was revised to give more specific details on splicing and included a referece to Okonite drawing D-11547 received in the March 1978 transmittal. This note has since appeared on drawings with only minor changes in content and a shift to a drawing series which was created to bring all notes which apply to a similar piece of equipment or installation activity (i.e., cable, conduit, etc.) to a common location. It now appears as note #10A on drawing 20E-0-3000N SH-2 Rev. H (Attachment 6) where it has resided since this drawing series was begun in 1985.
kt\nla\brdwd\okonitel Nbb05a 9404250197 940415 PDR ADOCK 05000456 Jfa k' P PDR 1 I t
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e i Mr. William Russell April 15, 1994 Additionally, attached is a copy of Byron /Braidwood FSAR Question 040.3 dated May 1979 (Attachment 7). These questions were asked and responded to during the original NRC review of the pre-licensing Byron /Braidwood FSAR. The response provides the manufacturer's names and types of cable to be used for power, control and instrumentation circuits at Byron and Braidwood. As indicated, Okonite is the specific vendor for power and control cable. This information was incorporated into the first revision of the FSAR but was originally provided to the NRC for review under that question number.
If you have any questions concerning this response please contact me at-(708) 663-6484.
I Sincerely, p
(,/ //'l < *< g w
Denise L-m
}M.{Saccomando Nuclear Licensing Administrator Attachments
- 1) Okonite letter from J. D. Fess to T. B. Thorsell dated March 31, 1978
, 2) Sargent & Lundy letter from B. G. Treece to J.T. Westermeier
! dated December 11, 1978
- 3) Sargent & Lundy letter from F. G. Gogliotti to R. Cosaro dated October 10, 1983
- 4) Sargent & Lundy drawing 6/20E-0-3390A Rev AD
- 5) Sargent & Lundy drawing 6/20E-0-3390A Rev AE
- 6) Sargent & Lundy drawing 6/20E-0-3000N SH-2 Rev H
- 7) Byron /Braidwood FSAR Question 040-3 l
I cc: R. Assa, Braidwood Project Manager'- NRR I S. Dupont, Senior Resident Inspector - Braidwood J. Martin, Regional Administrator - Region III Office of Nuclear Facility Safety - IDNS k:\nla\brdwd\okonitel L________.____ -
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3-i j ATTACHMENT 1 1
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'*G" "9"'""" 'rsosas O OKONITE 312-352-7200 b
COMPA NY 73 -
March 31, 1978
.T l'
41 Mr. T. B. Thorsell Sargent & Lundy 55 East Monroe Chicago, Illinois 60603
Subject:
Commonwealth Edison Company i
Byron and Braidwood Stations 600 Volt Control Cables Specification F/L 2823 l
Dear Mr. Thorsell:
! At the request of Mr. J. Dennehy we are attaching a drawing i and instructions for splicing of 12/C #14 control cable which l will be used on the subject project.
Please review and submit this data to the field unless there are any further questions.
Very truly yours, THE KONITE COMPANY
& h // w ohn D. Fess .
District Manager JDF/cmj Attach.
cc: Mr. J. J. Dennehy (attach.)
l l
I
i INSTRUCTIONS FOR A STRAICHT SPLICE FDR MULTI-CONDUCTOR, RUBBER INSULATED, OKOLON JACKETED NUCLEAR STATION C0tEROL CABLE Drawing No. D-11547 ite v , A
- 1. Study the drawing and instructions for design and dimensions of the splice and the step by step procedure.
- 2. Determine the number of steps in the splice and the approximate number of conductors I to be jointed at each step and the overall length (L) of the completc.d splice from !
the following table: I l NUMBER OF CONDUCIORS NINBER OF NUMBER OF JOINIS OVERALL LENCIH IN CABLE STEPS PER STEP (L) 2- 3 1 3 10 4- 7 2 4 12 8 - 14 2 7 12 15 - 21 3 7 14 22 - 28 4 7 16 29 - 37 5 8 18 l
- 3. Form and rack the cables into their final position and cut the ends so that the cables overlap for the distance of (L) minu s (4) inches .
4 Remove the cable jacket from both cables for a distance of (L) minus (4) inches.
- 5. Remove the insulation belt and fillers to within (1) inch of the cable jacket on both cables.
6 Match one of the center conductors from both cables. Cut off the excess length from one or both conductors as necessary to locate the joint at the proper step in the splice, cutting the conductors so that they butt together. Remove the insulation for a distance of (1/2) the connector length from each conductor. Place the conductors in the connector being sure that they butt together in the center of the connector and compress the connector onto the conductors using the correct tool in accordance with the connector manufacturer's instructions.
7 Buff the surface of the insulation on each side of the connector for a distance of (1/2) inch. Wipe the buffed insulation surface with a cloth moistened with chlorothene or other suitable non-toxic, fast drying solvent and allow to dry. Apply a thin layer of Okonice cement to the buf fed surfaces and allow to dry until tacky.
- 8. . When dry, apply one half-lapped layer of Okonite T-95 insulating tape over the connector lapping onto the insulation on either side of the connector for (1/2) inch.
9 Apply one half-lapped layer of Okonite No. 35 jacketing tape over the applied Okonite T-95 insulating tape.
. Repeat the above procedure on all the remaining conductors working from the center conductor outward and staggering the joints so as to keep the overall diameter of the splice as small as possiole.
Drawing No. D-11547 key. t. Page %
- 11. Buff the surface of the insulation belt with Aloxite cloth. Wipe the buffed surface with a cloth moistened with chlorothene or other suitable non-toxic, fast drying solvent and allow to dry.
- 12. Uhen dry, apply a thin film of Okonite cement to the buffed insulation belt surface and allow to dry until tacky. ,
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- 13. Apply one half-lapped Icyer of Okonite No. 35 jacketing tape, with minimum tension l necessary so that it conforms to the contour of the splice. Apply the tape over the bundled conductor splices up to the edge of the cable jacket ca each cable.
14 Buff the surface of the cable jacket for approximately (2) inches on each cable. Wipe the buffed cable jacket surfaces with a cloth moistened with chlorothene or other suitable non-toxic, fast drying solvent and allow to dry.
- 15. When dry, apply a thin film of Okonite cement to the buffed cable jacket surfaces and allow to dry until tacky.
- 16. Apply a minimum of (2) half-lapped layers of Okonite No. 35 jacketing tape, with minimum tension necessary so that it conforms to the contour of the splice. Apply the tape over the complete splice area and lap onto the cable jacket for approximately j (2) inches.
I THE OKONITE COMPANY
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September 8,1983 Revised - Marrh 15, 1984 i
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OKDIIN CAR _ T.E JACKET REAIR PIG 2[1RES hd ye -arres f:r- repairing The attached drawings illustrate the r+aOkolon cable jackets which ha j
h correct proopdure to follow is based on the severity of the damage. -
) Mrmination of the damage,is necessary to detemine Wtich ye--dire is applicable.
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I. DLRING INSTALIATI(W i No Repair Required (1) Abrasions, cuts, gouges or indentations not
{ exceeding 30% of the cable jacket.
$ . No Repair Required (2) Flattened cable in which the ratio of min-l
' inun di=ater to =ri== di-ater is not less than 90%.
- D-5721 J
(3) Abrasions, cuts, gouges or indantations i exceeding 30% but not greater than 50% of the jacket thi h s.
j D-5731 1
(4) Abrasions, cuts, grouges or ind staties exceeding 50%
D-5715 (5) Jacket sectim(s) torn off the cable )'
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- AFTER CABLES ARE COMPIRELY INSTATfED AIO 1 RAINED 1 No Rgair Required ,
(1) Abrasisons, cuts, grtanges or irrientations i i
that are not greater than 50% of the jacket thicimass.
! D-5731 (2)
Abrasions, cuts, gauges or inde=<tations j excMing 50% of the jacket thickness D-5715 2 (3) Jacket section(s) torn off the cable 1
t h above procedures apply to 300V to 15kV cable except 1/C 5 and SW non-j i shieldad cable.
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! If repairs are required on Class IE nuclear generating statirm cable .
materials must be ordered through the Ramsey office.
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December 11, 1978 '
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'Proj.;Nos.
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Commonwealth Edison Company Byron /Braidwood Stations - Units 1 & 2 Cable Splices in Cable Trays
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ee a to Mr. J. T. Westermeier t0 i Project Engineer
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Commonwealth Edison Company ,
P. O. Box 767 3, Chicago, Illinois 60690 C'
- Attention: Mr. J. J. Dennehy 4
C i Gentlemen: . 7 At recent construction meetings at Byron, Edison (Construction) has requested permission to install cable splices in the cable pans on an "as-needed" basis. Edison (and S&L) Encineering personnel ~
- ' have respond,ed that cable splices should be installed only where ,
specifically called for on the S&L drawings and that any additional I ow cable splices proposed by Construction personnel will be reviewed !
. and approved or rejected on a case-by-case basi.
{t In response to Mr. J. J. Dennehy's question as to the basis (justi-a fication) for prohibiting cable splices in the cable pans, this !
. yg will confirm my December 8, 1978 conversation wherein I advised l Sis '
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Mr. Dennehy that Regulatory Position C.5 of NRC Regulatory Guide
) 1.75 (Revision 1, January, 1975, copy attached) states that
" Cable splices in raceways should be prohibited".
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"' . j{'y In addition to this NRC requirement, Section 5 of S&L Standard EA-122, Revised 7-28-78 (copy attached) allows cable splices to be made only at locations and in the cables specified on the '
Electrical Installation drawings. This revised S&L Standard will soon be issued to the Electrical Installation Contractor.
'3"E- Please advise if you require further informatien on this matter y, Yours very truly, M to B. G. Treece
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Senior Electrical Project Enginapr BGT:bmh In duplicate Enclosures Copics: f' i
J. C. LaVallee (1/l)
K. T. Kostal (1/l) {'
E. R. Crass (1/l) c' R. F. Carlton (1/l) 3 i
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October 30, 1933 Project !!os. 4683/4-00 Cerm.onwealth Edison Company Craidwood Station - Unito 1 & 2 <
Electrical Installation WorP.
S&L Specification L-2790 Ceco P.O. 231360 ,
lir. R. Cosaro Braiduccd Conctruction Superintendent .
Project Construction Decartr.cnt . .,
Cccmonwcalth :dicon Cc 1pany P. O. Box 81 Braceville, Illinois 60407 Attention: .'ir. C. A. Monacche }
Dear Mr. Cocaro j >
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'There are :.1any cir:.u.7. tances which rr en: ire tbo c:: tension of ,
previoncly pulled crbles durinJ el:etrical inct yll: tion. T,e:: c have beer: r any discu. cions re"ordin? t!.c d ec i.. :. ;. ec cplice cuch i cables or to 0; ter::inal blocks (in junction bcuc::) to extand ,
these ccbles. r.
4 I:cgarding power c ebics, it has been sa:. gent f. 'unly's position en >
this projcct that rcwcr cables should 50 solic '.: nly here --
abnolutely *::::c:*.,;.ry. Thertftre, pr:cr c bica '.11 rar.'ly .e ,
extendca cad will reauire new cabica n pulled i c a h a c ::; n :,ier.
is :ccacc ry.
For control and is:ctr".-.cntation cc.:2' r; , we bal:.". thu une of ter::in ed :.1 , .'n in t.hc b .r. r . t r c -- :.c4 the C01:. n 3 r c i.:. c n s :
- 1. th : t rr:-! ti rns at tha ter '3 : 0 b icci .. tre cron for in-r.pr::t ic . , t....
. ing, .ina.m:a: .e Pt tc A. ic h . ;
require.:. ..rcugh tno '. 0 ye ; - :__ ci t': _ i .; .t.
- 2. The M:r.in 1 ;nr c:. n < eail . 1- r . :v i c e '.. if r ; :;ui- 6 d .:c te fa nign c: er i nc ta l .n'. : . . :.r :; cr n .
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Mr. R. Cosaro October 10, 1983 '
Commonwealth Edison Company Pago 2 '
- 3. Terminations at terminal blocks are more rollable and require loss installation time than a splico.
- 4. Both the installation of terminal blocks or a splico requires a the addition of a junction box.
- 5. For future modifications, the installation of a new cablo (
terminated at the terminal block will require ices time and be more reliable than the inutallation of a new cabic and splico.
In view of the above, we believe it to be in Commonwealth Edison :
Ccrapany's best int est to add terminal blocks where cabic extension f is required for control and instrumentation cables. ,;
I However, due to recent tost results on Marathon terminal blocks in boxes exposed to a LOCA environment, it is a requirement that, in such environments, safety-related low level instrumentation circuits -
shall not be terminated at terminal blocks provided and inntalled by the electrical contractor Theref ore, where cabic extension is required f or control circuits, terminal bicckr shoul.-I be unod. Whero extension of cables with low 0 -
level instrumentation circuits is required: 1) for safety-relatco circuits exposed to a LOCA or a Main Steam Line Dreak environment, r a splice must be used: 2) in all other cases, terminal blochn should- ',
be used. _
If you have any questions, please call me. -
Yours very truly, P. C. Gogliotti P. G. Gogliotti Electrical Project Engineer =
P CG : c'.nm In duplicate Copicn:
17 7. Casterneier D. G. Trcoco D. L. Le on e /'.l . C. Cleff R. J. Netzel s ou' 5 u >
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. B/8-FSAR AMENDMENT 20
.c MAY:1979 QUESTION 040.3
" Qualification of Safety-Related Cable "The Regula' tory staff is currently requesting, of all plants in OL review, information on the use of poly-ethylene type cable in safety systems. These type cables ,
were found-.to have degraded. considerably after many years of installed operation at'.the Savannah. fuel pro-cessing _ plant.
- " Identify all safety related cable used.in your design !
that has' polyethylene in its construction.. Provide the'following information for each type of cable l identified::
a) Type ~of cable by.name and Cat. No. ,
.b) ' Manufacturer.--
l c) Type.of polyethylene used.
- j. d) How is'the. polyethylene used.in the cable. con-struction, i.e., insulation,and/or jacket.
l e) Results of. environmental qualification tests l
performed."
I
RESPONSE
a,b) The safety-related~ cable purchased by Commonwealth l Edison Company for the balance-of-plant systems is.
of the.following design and manufacturer: .
' Power and' Control Cable:
Type of Cable. Cat. No. Manufacturer EPR/HYP. .Okolon- -Okonite -
Instrumentation Cable:
. Type of Cable Cat. No . . -' Manufacturer EPDM/HYP
- Samuel Moore j.
-c) 'Hypalon (Chlorosulfonated Polyethylene)-
'd) Jacket i
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B/B-FSAR AMENDMENT 20 MAY 1979 e) The cable as supplied by Okonite and Samuel Moore for the Byron /Braidwood Project has been qualified by each.of the respective manufacturer's to the fol-lowing standards:
- 1. IEEE 383-1974
- 2. IEEE 323-1974
- 3. IEEE 323-A-1975 l
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