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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6741990-09-17017 September 1990 Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided ML20059K5081990-09-14014 September 1990 Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990 ML20064A3681990-08-24024 August 1990 Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA ML20064A3751990-08-24024 August 1990 Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept ML20059A3991990-08-15015 August 1990 Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program ML20058N0551990-08-0707 August 1990 Provides Supplemental Response to NRC Bulletin 88-008, Suppls 1 & 2.Surveillance Testing Performed Revealed No Leakage,Therefore,Charging Pump to Cold Leg Injection Lines Would Not Be Subjected to Excessive Thermal Stresses ML20056A3351990-08-0202 August 1990 Responds to NRC Bulletin 88-009 Requesting That Addressees Establish & Implement Insp Program to Periodically Confirm in-core Neutron Power Reactors.All Timble Tubes Used at Plant Inspected & 18 Recorded Evidence of Degradation ML20055J1221990-07-25025 July 1990 Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary ML20055J1261990-07-25025 July 1990 Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H0291990-07-17017 July 1990 Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990 ML20044A9621990-07-13013 July 1990 Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc ML20055G4631990-07-13013 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-456/90-08 & 50-457/90-08.Corrective Actions:Discrepancy Record for Cable Generated & Cable That Had Been Previously Approved for Use on Solenoid Obtained & Installed ML20044B1411990-07-12012 July 1990 Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request ML20044B2141990-07-11011 July 1990 Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification ML20044B2871990-07-0909 July 1990 Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original Submittal ML20044A7991990-06-29029 June 1990 Forwards Description of Change Re Design of Containment Hydrogen Monitoring Sys,Per 900517 Request.Util Proposing Alternative Design Ensuring Containment & Hydrogen Monitoring Sys Operability in Event of Power Loss ML20058K3521990-06-22022 June 1990 Requests Withdrawal of 900315 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Specs 3.8.1.1 & 4.8.1.1.2 to Clarify How Gradual Loading of Diesel Generator Applied to Minimize Mechanical Stress on Diesel ML20056A0361990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-456/90-10 & 50-457/90-11.Corrective Action:Valve 2CS021b Returned & Locked in Throttle Position & Out of Svc Form Bwap 330-1T4 Modified ML20043G5851990-06-0808 June 1990 Forwards Repts Re Valid & Invalid Test Failures Experienced on Diesel Generator (DG) 1DG01KB,1 Valid Test Failure on DG 2DGO1KA & 2 Invalid Test Failures Experienced on DG 2AGO1KB ML20043D3141990-06-0101 June 1990 Forwards Rev 18 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043E3141990-05-31031 May 1990 Withdraws 880302 Application for Amend to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,changing Tech Spec 4.6.1.6.1.d to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin,Due to Insufficient Available Data ML20043F4731990-05-30030 May 1990 Forwards Suppl to 881130 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Changes Requested Per Generic Ltr 87-09,to Remove Unnecessary Restrictions on Operational Mode Changes & Prevent Plant Shutdowns ML20043B7771990-05-23023 May 1990 Forwards Endorsement 9 to Nelia & Maelu Certificates N-108 & M-108 & Endorsement 8 to Nelia & Maelu Certificates N-115 & M-115 ML20043A9161990-05-16016 May 1990 Provides Advanced Notification of Change That Will Be Made to Fire Protection Rept Pages 2.2-18 & 2.3-14 ML20043C2811990-05-15015 May 1990 Responds to NRC 900416 Ltr Re Violations Noted in Insp Repts 50-456/90-09 & 50-457/90-09.Corrective Actions:Gas Partitioners Tested Following Maint During Mar 1990 & Tailgate Training Session Will Be Held ML20042G7111990-05-0707 May 1990 Responds to NRC Questions Re leak-before-break Licensing Submittal for Stainless Steel Piping.Kerotest Valves in Rh Sys Will Be Replaced in Byron Unit 2 During Next Refueling Outage Scheduled to Begin on 900901 ML20042F6851990-05-0404 May 1990 Requests Resolution of Util 870429,880202 & 0921 & 890130 Submittals Re Containment Integrated Leak Rate Testing in Response to Insp Repts 50-454/86-35 & 50-455/86-22 by 900608 ML20042F6771990-05-0303 May 1990 Advises NRC of Util Plans Re Facility Cycle 2 Reload Core. Plant Cycle 2 Reload Design,Including Development of Core Operating Limits Has Been Generated by Util Using NRC Approved Methodology,Per WCAP-9272-P-A ML20042E9111990-04-25025 April 1990 Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. ML20042F2681990-04-18018 April 1990 Provides Supplemental Response to Violation Noted in Insp Repts 50-456/89-21 & 50-457/89-21 Re Safeguards Info.Util Request Extension of 891010 Commitment Re Reviews of Plants. List of Corrective Actions Will Be Submitted by 900601 ML20042F0241990-03-28028 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML20012D8671990-03-21021 March 1990 Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date ML20042G4641990-03-20020 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Repts 50-456/90-02 & 50-457/90-02.Corrective Actions:Existing safety-related Temporary Alterations Will Be Reviewed to Determine Which Alterations Include Installation of Parts ML20012D8711990-03-19019 March 1990 Forwards Corrected No Significant Hazards Consideration to 890814 Application for Amends to Licenses NPF-72 & NPF-77 ML20012C0861990-03-14014 March 1990 Forwards Response to Insp Repts 50-456/90-03 & 50-457/90-03 on 900122-26.Encl Withheld (Ref 10CFR73.21) ML20012E9221990-03-13013 March 1990 Forwards Final Version of Action Plan for post-accident Sample Sys QC Program,Per Insp Repts 50-456/90-05 & 50-457/90-05 ML20012C5471990-03-12012 March 1990 Provides Results of Completed Util Reviews & Addresses Addl Info Requested by NRC Re 890317 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Change Tech Spec 4.5.2,supplemented on 890825 & 890925-27 Meetings ML20012C5061990-03-12012 March 1990 Forwards Braidwood Nuclear Station Unit 1 Inservice Insp Summary Rept,Interval 1,Period 1,Outage 1. ML20011F6211990-02-21021 February 1990 Forwards Revised PHOENIX-P/ANC Benchmark Scope to Replace Existing Ark & 2D Codes Used to Perform Neutronic Analyses for PWR Reload Designs.Codes Expected to Be Used in Dec 1990 for Cycle 3 Design Calculations ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20055D4121990-01-29029 January 1990 Forwards Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,For Review ML19354E1741990-01-22022 January 1990 Provides Current Status of Ds Breaker Insps for Plant Following Completion of Recent Unit 1 Refueling Outage & Advises That Remaining Ds Breaker Insps Will Be Completed by End of Upcoming Unit 2 Refueling Outage ML20006D9621990-01-22022 January 1990 Forwards Info Re Invalid Test Failure Experienced on Diesel Generators 1DG01KA & 1DG01KB,per Reg Guide 1.108 ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20011E7391990-01-16016 January 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp Repts 50-456/89-28 & 50-457/89-27.Corrective Actions:Maint Work Request Procedure Will Be Revised to Clarify Testing Performed within Nuclear Work Request Package ML20006A1641990-01-11011 January 1990 Forwards Info Describing Initial Use of Rod Worth Measurement Using Rod Exchange Technique,Per Sser 2 (NUREG-1002) 1990-09-17
[Table view] |
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Addrees Reply to: Post Omce B 67'~ l A- Chicago,lihnoes 60690 0767 j i
.V December 18, 1989 !
Mr. A.B. Davis Regional Administrator US Nuclear Regulatory Commission
~ Region III 799 Roosevelt Road ]
Glen Ellyn, 11 60137 j 1
Subject:
Braidwood Station Units 1 & 2 Response to Inspection Report Nos. '
50-456/89026 & 50-457/89026 '
NRC Docket Nos. 50-456 and 50-457 References (a) W.D. Shafer letter to Cordell Reed dated November 17, 1989 Dear Mr. Davis t .
Reference (a) provided the results of the inspection conducted by Messrs. T.M. Tongue. T.E. Taylor, G.A. VanSickle, R.B. Landsman and Ms. D. ,
Calhoun on September 17, 1989. through October 3, 1989, of activities at :
Braidwood Station. Reference (a) indicated that certain activities appeared .
to be in violation of NRC requirements and that a response is required. The Conunonwealth Edison Company response to the' Notice of Violation is provided in ;
the Enclosure.
Commonwealth Edison believes that the circumstances surrounding the ;
. bases.for the Notice of Violation may warrant further discussion.
Commonwealth Edison is willing to meet with the NRC Staff to discuss these at ['
your convenience.
If you have any questions regarding this response, please direct them ;
to this office.
Very truly yours,
[w /
s no d- - ,
M T.J. Kovach Q@ Nuclear Licensing Manager M 4h e
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$$b cc Stephan Sands-NRR NRC Resident Inspector-Braidwood i NRC Document Control Desk DEC 211989
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ENCLOSURE r COMMONWEALTH EDISON COMPANY'S RESPONSE TO BRAIDWOOD STATION INSPECTION REPORT Nos. 456/89026 and 457/89026 ,
VIOLATION: .
Technical Specification 3.8.2.1 action statement c.(2) requires that, "With a DC bus inoperable or not energized on a shutdown unit (Mode 5 or 6), the af fected bus may be energized f rom the operating unit (Mode 1, 2, 3, or 4) opposite DC bus via the crosstie breakers af ter limiting the DC loads on the af fected DC bus; operation may then continue for up to seven days or open the '
crosstie breakers.
Contrary to the above, on September 15, 1989, the seven day time limitation was exceeded by about five hours.
The DC crosstie was closed on September 8, 1989, at 3:58 a.m., and reopened on September 15, 1989, at approximately 9:10 a.m. This was done to provide power to bus 111 on Unit 1 in Mode 5 (cold shutdown) f rom bus 211 on Unit 2 in Mode 1 (operations) above $1.
RESPONSE
Commonwealth Edison acknowledges that on September 15, 1989 the DC bus crosstle between the operating unit (Unit 2) and the shutdown unit (Unit 1) was closed in excess of seven days. In response to the Braidwood Resident Inspector's concern over the potential applicability of Technical Specification 3.8.2.1, Braidwood Station verbally agreed to observe a seven day time limit for the closure of the D.C. crosstie breakers. This seven day period was inadvertantly exceeded, by about five hours, due to a miscanmunication among station management personnel.
Commonwealth Edison acknowledges the Braidwood Resident Inspector's concerns in that the potential for a mis-interpretation of the subject Technical Specification exists. This mis-interpretation results from the current wording of the subject Specification. The wording in the LCO of the Technical Specification does not provide a clear mechanism to directly implement the action statement of the Technical Specification. Braidwood Station intends to continue to review alternatives to the current Technical Specification wording. If developnient of an acceptable alternative is achieved, a Technical Specification change request will be submitted. However, it is Commonwealth Edison's position that the DC crosstle configuration is allowable by the current Technical Specifications. The basis for this position may not have been clearly presented to the NRC Staff previously. As a result, new information may be included in this response that supports Commonwealth Edison's position that may have not been reviewed by the NRC Staff.
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lo * - 2 -
The DC crosstie configuration was issued in Ammendment 5, to the Braidwood I Station Technical Specifications, on January 27, 1938. On March 2, 1989, Braidwood Station wrote an interpetation of Amendment 5 based on the following references the Technical Specification itself, the Safety Evaluation Report issued with the amendment, and the technical information used to justify the change. Amendment 5 to the Braidwood Station Technical Specifications was issued to address two specific configurations. These configurations are addressed as, situation 1 and situation 2 in the licensee summary of the proposed change and the Safety Evaluation Report issuad with the change.
Situation 1 addresses the inoperability of a battery charger alone with both units operating in modes 1, 2, 3. or 4. In this situation action statement c.(1) of specification 3.8.2.1 will allow the DC crosstie breakers to be closed for the purpose of supplying DC power to the affected units battery and loads. In this configuration, both batteries are connected to their respective DC bus with a single battery charger supplying DC power. The j capacity of a single charger is sufficient to supply both units in this configuration. In the event of single failure and simultaneous accident with ;
loss of offsite power, all equipment fed from the DC busses would be powered ;
from a fully charged operable battery capable of meeting its analyzed load 1 profile, without having to impose crosstie limitations. j Situation 2 addresses the inoperability of a battery charger and its associated battery on a shutdown unit (modes 5 or 6). In this situation action statement c.(2) of specification 3.8.2.1 will allow the DC crosstie l breakers to be closed for the purpose of supplying DC power to the affected l units loads. In this configuration the DC loads must be limited to less than ;
or equal to 63 amps to assure that the single remaining battery would have adequate capacity to supply power to the operating unit in the event of a ,
single failure and simultaneous accident with loss of offsite power.
On September 8, 1989 Braidwood Station Unit I was in mode 6 with Unit 2 operating at approximately 95% power. Battery 111 was fully operable and connected to its bus, the Unit 1 charger 111 was removed from service for maintenance, the Unit 2 battery 211 and charger were both fully operable and connected to their respective bus, and the crosstie between Unit 1 DC bus 111 and 211 was closed. This manipulation occurred at 0358 on September 8, 1989.
In this configuration, Unit I was in full compliance with the applicable Technical Specification requirements (i.e., Tech Spec 3.8.2.2) of.one fully OPERABLE division of DC power (Division 12), without reliance on the croustie l provisions. Unit 2 had the required number of OPERABLE DC buses, batteries, l and chargers as stated in Tech Spec 3.8.2.1. Again, this condition was achieved without benefit of the crosstie provision. Braidwood was not in a condition that required entry into Action Statement c.2 because DC Bus 111 was intact, unfaulted, and energized from its own battery. At no time was the DC bus inoperable or in a de-energized condition for the shutdown Unit (Unit 1).
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The use of the crosstie breaker in this instance had the net effect of !
maintair.ing full, dual-train availability of DC controla and indications for Unit I without unnecessarily degrading the Division 11 battery. The configuration was within the design envelope of the DC system as described in Sections 8.1.1 and 8.3.2.1.1 of the Byron /Braidwood UFSAR (See Attachment A).
The battery charger with a rated output of 400A is designed and sized to i accomodate the additional loading imposed by the closure of the crosstie ;
breakers. These Class 1E breakers offer redundant electrical isolation capability, and are coordinated with the the DC bus main breaker to ensure that the crosstie will open before the battery is isolated in the event of a -
fault.
The unit in operation, Unit 2, was not rendered vulnerable to any ,
single-failure considerations by this configuration, so the ability of the system to mitigate a design basis event was not impacted. Based on the above information Braidwood Station believed that there was no time restriction required in this configuration because (1) there were two fully charged !
batteries associated with each unit, and (2) the configuration was one not specifically addressed by the Technical Specifications.
t It must be recognized that this configuration will be required during refuel outages to maximize the availability of main control room controls and indications during the performance of required DC charger and battery testing.
The duration of such events may differ from outage to outage based on testing and equipment repairs. As such, the latitude to crosstle DC buses with one unit in operation and the second unit shutdown will be required.
l l
l Because Unit 1 was in mode 6 with one fully OPERABLE train of DC power and in .
full compliance with Technical Specification 3.8.2.2, Commonwealth Edison requests that this violation be withdrawn for Unit 1. Based on the above discussion, Commonwealth Edison respectfully requests that the NRC re-review the facts as presented. Commonwealth Edison believes that Technical Specification 3.8.2.1 was not violated and that the configuration of the DC crosstie which Braidwood Station utilized was in compliance with the description in the Byron /Braidwood UFSAR. Commonealth Edison believes that this issue warrents further discussion and as such, Commonwealth Edison would like to meet with the NRC Staff prior to the NRC Staff's final disposition of l this violation.
CORRECTIVE ACTION TAKEN AND RESULTS ACilIEVED:
l Prior to exceeding seven days from the point of closing the DC crosstle breakers, Braidwood Station had conducted conversations with the resident inspectors on site outlining the stations position. It was agreed that the crosstie time frame would be limited to less than seven days until resolution could be reached.
Through a miscommunication error it was believed that the seven day time frame was to expire th morning of September 16, 1989. Upon notification by the Resident inspectors that the seven day time frame had been exceeded, Braidwood Station proceeded to supply temporary power to DC bus ill and open the crosstie breakers. This action was completed at 0910 on September 15, 1989.
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1
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1 CORRECTIVE ACTIONS TAKEN TO AVOID TURTHER VIOLATION: j Within the week following this event a conference call was conducted between Braidwood Station, Byron Station, and NRR. It was concluded from the call 1 that the Technical Specifications did not specifically address the situation, I the specification was ambiguous in nature, and that from a technical !
standpoint there is basis to pursue an amendment to the Technical l Specifications. Braidwood Station will attempt to develop an acceptable i alternative to the existing Technical Specification wording to govern the use of the D.C. crosstle treakers and, accordingly make an appropriate Technical Specification change request submittal. Until resolution of this matter is achieved, Braidwood Station will limit the use of the DC crosatie breakers, ,
when one unit is in operation (mode 1, 2, 3, or 4) and the other unit shutdown (mode 5, or 6) to less than or equal to 7' days.
To preclude the potential of a verbal commitment being missed, Braidwood Station will document these commitments using the existing Braidwood Station tracking system.
DATE OF FULL COMPLIANCE:
Braidwood Station believes it is currently in full compliance with Ammendent 5 of the Technical Specifications.
/sc1:0423T 13
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l-i ATTACHMENT A TO ENCLOSURE COPMONWEALTH EDISON COMPANY'S RESPONSE TO BRAIDWOOD STATION INSPECTION REPORT NOS. 456/89026 and 457/89026 f
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. B/8-UFSAR l t .
Each unit:is provided with a 250-Vdc system for use with essen- ;
tial non-safety-related auxiliaries as described in Subsection 8.3.2.1. [
Identification of Class 1E Loads ,
o Nuclear safety-related systems and components that require electrical power to perform their nuclear safety function are ;
defined as Class 1E loads. :
8.1.1 Indeoendence Between Redundant Standby (Onsitei Powgr Sources and Between Their Distribution System i An acceptable degree of independence between redundant standby i (onsite) power tources and between their distribution system is described in the following subsections. l
- a. Independent Load Assianment ,
i Each Class 1E Load (a-c or d-c) is assigned to an ESF Division 11 or 12 (21 or 22) load group. :
Assignment is determined by the nuclear safety I functional redundancy of the load. The loss of a single division does not prevent the performance of-the minimum safety functions required for a safe shutdown.
- b. Indeoendent Class 1E A-C Sources !
Each ESF division a-c loed group has a feed from two auxiliary transformers (offsite) and from one i diesel generator (onsite) as shown in Drawings 6E-0-4001 and 20E-0-4001, Section 1.7.
The diesel-generator circuit breaker will not close ,
automatically unless other source circuit breakers to that load group are open as shown in Drawings ;
~
6/20E-1-4030DG01 and 6/20E-1-4030DG02, Section 1.7.
- c. Indeoendence of Class it'D-C Sources ,
Each ESF division d-c 16ad group has a feed from one battery charger and one battery as shown in Drawings 6E-0-4001 and 20E-0-4001, Section 1.7. 1 The redundant d-c load groups cannot be connected to each other. The d-c battery-charger combination of one ESF division cannotEach be connected to another d-c load group of one ESF redundant division.
unit can be connected to the corresponding nonredun-dant d-c load group of the second unit and satisfy the design load.
8.1-8 l
t' . .
l B/8-UFSAR
- d. Indeoendence of Standby sources i
The diesel-generator circuit breaker will close to j its associated load group automatically only if the i other source circuit breakers to the load group are l open. !
1 When the diesel-generator circuit breaker is I closed, no other source breaker will close auto- i matica11y. Electrical interlocks ensure that no i means exist for connecting redundant load groups with each other. ;
Each of the redundant load groups is fed from only one diesel generator. No means are provided for transferring loads between the redundant diesel !
generators. l There is no direct tie provided that will allow the paralleling of the redundant diesel generator man- !
ually by an operator error during loss of offsite ,
power. l i
- e. Prime Mover Division 11 and 12 (21 and 22) diesel-generators are provided with only one prime mover for each ;
generator. .
Compliance with Regulatory Guide 1.6 is discussed in Appendix A.
8.1.2 Selection of Diesel-Generator Set Cacacity For Standby l Power Sucolies Diesel-generator sets are selected as the onsite standby power '
supply with sufficient capacity and margin to assure that acceptable fuel design limits and design conditions of the j reactor coolant pressure boundary are not exceeded, that the core is cooled, and that containment integrity and other vital l functions are maintained in postulated accidents. l The diesel gener'ator load rating for continuous duty is 5500 kW (6875 kVA, 0.8 power factor). .
The 2000-hour rating of each standby diesel generator is 5934 kW, and the 2-hour rating is 6050 kW.
Table 8.3-5 shows the maximum expected coincidental loads for ,
each of the diesel-generator sets, for LOCA conditions, and for '
safe shutdown conditions.
During preoperational testing, the predicted standby diesel generator loads for each ESF division is verified, as well as i the capability of the diesel generators to carry these loads.
8.1-9
- . - - ~ - - . - . _ - _ - - --. . -- . . -
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B/8-UFSAR
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s D-C Power System j 8.3.2
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8.3.2.1 Descrintion )
The d-c power' system provides d-c control and motive power for !
vital equipment during all normal as well as emergency conditions of the plant. The system is designed to meet the !
requirements of General Design Criteria (GDC) 17 and 18. !
Figures 8.3-1 and 8.3-2 show the single line diagrams of Units l 1 and 2 125-Vdc systems. j The d-c power system consists of the following subsystems
- a. Two non-Class 1E 250-Vdc systems (each with its own !
battery, battery charger, and associated equipment) !
which supply power to the generator air side seal !
oil pumps, turbine d-c emergency bearing oil pumps, steam generator feed pump turbine emergency bearing .
oil pumps, and plant computer for Unit 1 and Unit 2 i respectively. j
- b. One non-Class 1E 48-Voc system at the river screen house (with its own battery, battery charger, and ,
associated equipment) which supplies d-c control power to the river screen house switchgear.
- c. Two non-Class 1E 125-Voc systems at the switchyard .
r(lay house which supplies d-c control power to the 345-kV switchyard circuit breakers,
- d. One non-Class 1E 125-Vdc system which supplies !
power to the technical support center computer and ,
peripheral loads and the security computer. ;
l
- e. Four Class 1E 125-Vdc power systems which are described in the following sections.
i
- f. Two Class 1E 24-Voc systems which provide control j power and diesel engine starting capacity for the i diesel engine-driven auxiliary feedwater pumps, "
which are described in the following sections.
8.3.2.1.1 class 1E 125-Vdc Power Evstems Each. unit is provided with two sources of class 1E 125-Vdc power. They are electrically isolated and physically separated so that any failure involving one source cannot jeopardize the function of the other source.
The 125-Vdc batteries, racks, chargers, distribution panels, and battery room ventilation equipment are classified as Safety Category I and meet Byron /Braidwood seismic requirements.
8.3-43
4 ,
B/B-UFSAR f ;
The Class 1E 125-V battery systems supply power to Class 1E I
' loads without interruption during normal operations or DBA !
conditions. Each Class 1E 125-Vdc system consists of one
. battery, one main distribution bus with molded-case circuit !
breakers, one static battery charger, and local distribution :
L i panels. Redundancy and independence of components precludes l l the loss of both systems as a result of a single failure. For -
Unit 1, Battery 111 supplies ESF Division 11 load requirements; f Battery 112 supplies ESF Division 12 load requirements. There are no bus ties, or sharing of power supplies between redundant t trains. j Each Class 1E 125-V battery, battery charger, and distribution panel ascociated with one ESF division is located in a Seismic Category I room, physically separated from the redundant equip- ;
ment. Electrical separation is also maintained to ensure that a single failure in one train does not cause failure in the redundant train. There is no sharing between redundant Class ,
1E trains of equipment such as batteries, battery chargers, or J distribution panels. ,
Each Class 1E 125-Vdc system has the capacity to continuously ;
supply all the connected normal running load while maintaining its respective battery in a fully charged condition. Each ,
battery has a nominal rating of 1200 ampere-hours and is capable of carrying the various loads continuously, for the time periods indicated in Table 8.3-9, in the event of a total loss of onsite and offsite ac power. The batteries are sized :
in accordance with IEEE 485-1978. .
The primary sources of Class 1E d-c power system are the battery chargers. Every battery charger is rated to supply its associated d-c loads while fully recharging the battery. Each battery charger is fed from a 480-Vac ESF switchgear bus of the same division. This meets the recommendations of position C.1.b of Regulatory Guide 1.32.
One 400 ampere capacity static battery charger supplied by a ;
Class 1E MCC, is provided for each Class 1E 125-V battery system. Protection is incorporated in the battery chargers to preclude the ac supply source from becoming a load on the battery as a result of power feedback upon loss of ac input power. Backup protection is incorporated by an overvoltage relay mounted on the charger, which trips the charger supply and annunciates the tripped condition in the control room.
9 Each battery charger is capable of floating the battery on the bus or recharging a completely discharged battery while supplying the largest combined demands of the various steady-state loads under all plant operating conditions.
- The battery chargers do not have the capability of supplying the loads if the battery is disconnected. Figures 8.3-1 and 8.3-44
B/B-UFSAR 8.3-2 show that the battery chargers are automatically discon- .
nected when the batteries are disconnected. i The batteries are located in separate rooms. The rooms are i i
described in the Byron /Braidwood Fire Protection Report, Subsection 2.3.5 (Reference 1). All battery areas are venti-lated to prevent the accumulation.of gases produced during charging operationss Each Class 1E 125-V battery area is ;
provided with an independent safety-related ventilation system. A separate safety-related exhaust fan and duct is (
provided for each Class 1E battery area. The ventilation ,
system services the rooms housing the batteries and the battery :
chargers and distribution panels are der,cribed in Subsection 9.4.5.3. ,
i Each 125-Vdc system has its own independent instrumentation:
- a. d-c voltmeter at the MCB to measure.the voltage at the 125-Vdc distribution center bus; t b.
d-c voltmeter with a selector switch to measure the -
d-c output voltage of the battery charger and the bus voltage; .
- c. d-c ammeter to measure the d-c output current of the battery charger;
- d. d-c ammeter to measure the d-c current of the i battery; 1 e,
power failure alarm relay which indicates a loss of l a-c power to the battery charger (alarms at the main control room);
i
- f. charger d-c output failure alarm relay (alarms at the main control room); i
- g. charger low d-c voltage alarm relay (alarms at the main control room); ,
- h. charger high d-c voltage shutdown relay; l
- i. recording ground-detector voltmeter and alarm (alarms at the main control room); l i
3 breaker trip alarma on the battery and battery charger breakers and an alarm indicating that the bus tie breaker is closed (alarms at the main control room); and l
- k. 125-Vdc bus undervoltage alarm relay (alarms at the main control room). ,
[ 8.3-45 1
f6 . . i B/B-UFSAR i ,
p The following protection is provided against overcharging:
L a. A high-voltage shutdown relay opens the main supply L breaker to the charger when the d-c output voltage of the charger rises to approximately 15% over the 4 battery float voltage.
l
- b. A d-c voltmeter provides a visual check on battery voltage. No overvoltage alarms are provided.
The tie between buses 111 and 211 and the tie between buses 112 i and 212 (d-c buses for Unit 1 and Unit 2) are each provided {
with two normally locked open, manually operated circuit !
breakers. The ties are provided so that the nonredundant d-c buses of Unit 1 and Unit 2 can be interconnected during mainte-nance and testing operations in the battery an6/or battery j charger associated with either bus 111 (211) or bus 112 (212).
No interlocks are provided since the interconnected buses are not redundant. However, procedural and administrative controls !
are used to limit the corrective load to an allowable amount !
(63 amps) based on not exceeding the battery capacity. Tie breaker closed alarms are provided.
The d-c power supplies are separate and independent for Unit 1 ;
and Unit 2. Each supply is of sufficient capacity to meet the loads normally connected to it in the event of-a loss of ;
offsite power. While it is possible to interconnect the Unit 1 and Unit 2 power supplies, they will remain disconnected except for the following circumstances: (1) when a 6-c power supply must be taken out of service for the purposes of maintenance and/or' testing, or (2) in the event of a failure of a d-c supply source.
The interconnection between each Unit's Class lE 125-Vdc sys-tems, via the crosstie, is limited by procedural and admini-strative controls. These controls ensure that combinations of maintenance and test operations will not preclude the systems .
capabilities to supply power to the ESF d-c loads. The cri- !
teria specifying the allowable combinations of maintenance and- ,
test operations are governed by the plant technical specifi-cation. Coordination between unit operations required during maintenance and testing are governpd by administrative -
controls. The provisions of administrative 1y controlled, ,
manually actuated, interconnections between the non-redundant Class 1E d-c buses affects (i.e., increase) the overall reliability and availability of the d-c systems for each unit in that it provides a means for manually providing power to a d-c bus at a time when it would otherwise have to be out-of-service (e.g., to perform a battery discharge test during a refueling outage, to replace a damaged cell, etc.).
During normal operation, the batteries are kept fully charged by the battery chargers. periodically, the voltage is raised for equalization of the charge on the individual battery cells.
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i Readings of the battery voltage level during the equalization l charge are recorded.
The instrumentation (and the related alarms) provides reliable- i supervision of the condition of the overall d-c system, but !
does not (by itself) provide adequate information on the condition of the battery (a component). The condition of the ,
battery is tested initially as noted in Chapter'14.0 and i periodically monitored and tested as noted in Technical Speci- i fication 3/4.8. The time schedule for performing inspections, '
measurements, and tests is established in accordance with the requirements of IEEE Standard 450-1975 (as modified by the .
proposed 1978 revision issued for comments on November 7, 1977) l and 308-1971. I The batteries will be periodically discharge tested in accor-dance with the recommendations of Regulatory Guide 1.129. t The d-c power system is designed and applied so that when l operated within its rating under specified environmental conditions and when maintained in accordance with an approved schedule (including replacements of components when necessary), ;
it will perform its functions for the 40-year life of the plant.
8.3.2.1.2 class 1E 24-Vdc AFW Pumn Diesel Batteries The d-c power' system for the diesel-driven auxiliary feedwater pump consists of two complete sets of 24-Vdc batteries, battery chargers, battery racks, cables, and necessary accessories.
The complete system is located in the room with the diesel-driven auxiliary feedwater pump.
The battery chargers are powered from two separate ESF motor control centers of the same division as the diesel-driven pump.
l
, Each battery has sufficient capacity to run the diesel through l' four cranking cycles of 5 seconds each before the cranking i L timer times out and an overcrank and fail to start alarm is !
initiated.
The battery chargers are of the full wave rectifier voltage regulated type with voltmeter, ammeter, and thermal cutout designed for continuous floating duty on the storage batteries. Chargers are for 120-V, 60 Hz, single-phase a-c power supply, and have an isolation transformer to ensure that the batteries are completely isolated from the a-c power system. Operation of the battery chargers is automatic and I includes regulation to maintain the output voltage substantially constant within the rated current range and independent of a-c supply voltage.
There is no separate ventilating system for the d-c power system. The diesel-driven auxiliary feedwater pump room 8.3-47
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