Letter Sequence Other |
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MONTHYEARML20100R6481996-03-0505 March 1996 Forwards Braidwood Station Unit 1 SG Interim Plugging Criteria 90 Day Rept & Summarizes Insp Results & Evaluations Project stage: Other 1996-03-05
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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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Commonwealth Edison
! Braedwood Nuclear Power Station k%s _u ) Route #1, Box 84 BraceviNo. lilinois 60407 Telephone 815/458-2801 March 5,1995' .
BW/96-0033 Document Control Desk -
Nuclear Regulatory Commission ,
. Washington, D.C. 20555
Subject:
Braidwood Station Unit 1 l Steam Generator Interim Plugging Criteria 90 Day Repoit NPF-72; NRC Docket No. 50-456
References:
- 1. November 9,1995 letter from M. D. Lynch, Office of Nuclear Reactor Regulation to D. L. Farrar, Issuance of Amendments (TAC NOS.
l M91671, M91672, M91673 AND M91674) 1
- 2. September 1,1995 letter from Denise M. Saccomando to U.S. Nuclear j Regulatory Commission, Supplement to Application for Amendment to l Facility Operating Licenses: Byron Nuclear Power Station, Units 1 and 2, NPF-37/66: NRC Docket Nos. 50-454/455, and Braidwood Nuclear j Power Station, Units 1 and 2, NPF-72/77: NRC Docket Nos. 50-456/457 I l
- 3. September 20,1995 letter from Harold D. Pontious, Jr. to the Office of Nuclear Reactor Regulation, Teleconference between Commonwealth Edison Company and the Nuclear Regulatory Commission dated
. September 13,1995, Regarding the Increase in the Interim Plugging '
Criteria for Byron Unit 1 and Braidwood Unit 1, NRC Docket Numbers-50-454 and 50-456.
- 4. NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking.
- 5. November 13,1995 letter from T. J. Tulon to U.S. Nuclear Regulatory :
Commission, Comed Braidwood Station Unit 1 Fifth Refuel Outage Steam Generator Inservice Inspection Report, Docket No. STN 50-456 Reference 4 requires the results of the Steam Generator (SG) tube eddy current inspection j be issued to the staff within 90 days following restart. In Reference 3, Braidwood Station committed to issue the final results of the Steam Generator Internals Inspection Program within 90 days following restart. Restart from the Braidwood Unit I fifth refuel outage (AlR05) was on December 9,1995.
9603120481 950305
.h8 I i
Pursuant to these requirements, Comed is submitting the enclosed reports from the Braidwood Unit 1 AIROS steam generator inspection.
A summary of the inspection results and evaluations required by References 1,2, and 4 is as follows:
- 1. The bounding Probability of Burst (POB) for the End-of-Cycle 6 (EOC-6) was found to be in the 1 A SG. The 1 A SG POB is less than lx102. The bounding SG changed from the previous evaluations due to the contribution of the Hot Leg indications becoming negligible due to implementatic i of Tube Support Plate (TSP) locking as required by a 3.0 volt Interim Plugging Criteria (IPC).
- 2. The bounding Main Steam Line Break (MSLR) leak rate was found to be in the IC SG. The IC SG MSLB leak rate is less than the 26.8 gpm limit.
- 3. No circumferential crack-like indications were detected at the tube support plate intersections. Circumferential crack-like indications were detected in the tube roll transition region at the top of the tubesheet. None of the circumferential crack-like indications and none of the axial crack-like indications in the tube roll transition region were in tubes that were expanded at the Tube Support Plates.
- 4. No Primary Water Stress Corrosion Cracking (PWSCC) was detected at TSP intersections.
- 5. No indications were found to extend beyond the confines of the tube support plates.
- 6. No corrosion induced dents were identified in tubes adjacent to the tube intersections that were expanded at the Tube Support Plates.
- 7. A 0.610 inch bobbin coil probe was used to inspect all TSP intersections except one.
This one was in the 1C SG Row 28 Column 10 at the IOC TSP (Cold Leg). This TSP intersection had a large dent that has been present since initial startup, therefore, this indication was determined not to be a corrosion induced dent. This intersection is not adjacent to an expanded tube. IPC was not appled to this TSP intersection.
- 8. The Upper Voltage Repair Limit only applies to the Cold Leg indications. The Upper Voltage Repair Limit was 1.99 volts. There were no Cold Leg indications greater than the Upper Voltage Repair Limit. There was only one Cold Leg indication greater than 1 volt, but it was not cor. firmed by a Rotating Pancake Coil probe.
- 9. No tubes were removed from the Steam Generators, therefore, no metallurgical results of pulled tubes are available.
l Attachment A to this letter contains the results of the Steam Generator Internals Inspection. No indications detrimental to the integrity of the load path necessary to support the 3.0 volt IPC were identified.-
Attachment B to this letter contains the 90 day Steam Generator tube eddy current !
! inspection report for Braidwood Unit 1.
Please direct any questions regarding this submittal to Doug Huston, Braidwood Licensing i Supervisor, (815) 458-2801, extension 2511.
1
, Very truly yours, T. J. Tulon Station Manager
- Braidwood Station
. TJT/LA\gry IMandadminh960033. doc ]i Attachments cc: Senior Resident Inspector - Braidwood Braidwood Project Manager, NRR ;
Regional Administrator-RIII l d
T 1
i J
Attachment A Braidwood Unit-1 l- Steam Generator Internals Inspection Program Results l
March 1996 l
1 l
l l
1 1
l l
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Steam Generator Internals Inspection Program Results During the Braidwood Unit I fifth refuel outage (AlR05) a 3.0 volt Interim Plugging Criteria (IPC) was impicmented for predominately axially oriented indications at the hot-leg Tube Support Plates (TSP). In order to implement an IPC with a voltage limit greater than the Generic Letter 95-051.0 volt IPC, Comed had to demonstrate that the indications in the Steam Generator (SG) tubes would remain within the bounds of the TSP's during a Main Steam Line Break (MSLB) accident. During a MSLB accident, the TSP's will move. Comed demonstrated that the TSP movement could be limited by taking credit for the existing structural supports inside the SG along with adding supports by converting SG tubes to additional stayrods. In order to take credit for the existing structural supports inside the SG, inspections were performed to demonstrate that these load path carrying supports have not degraded during plant operation (plant life is at 5.522 Effective Full Power Years).
Two types of inspections were performed; eddy current and visual. The eddy current inspections were performed to demonstrate the integrity of the TSPs. An eddy current examination specially developed to identify cracks in the TSPs was performed in areas susceptible to cracking and in the area of the Patch Plate Seams. Eddy current examinations also verified the presence of the TSP at all tube / TSP intersections.
A majority of the visual inspections was performed in the l A SG, although some inspections were performed in all Unit 1 SGs. A representative sample of the load +ath carrying components was inspected. These load carrying components included the TSP Vertical Support Bars, the TSP Wedges, and the Vertical Stayrods including the Spacer between the TSPs and the nut at the top of the Stayrod. In addition to this, the SG Tube Bundle Wrapper was verified to not have moved off its support structure. A summary of each inspection is given below.
Eddy Current Insoections Inspection Near the Anti-Rotation Devices EPRI developed a SG tube eddy current inspection method that could be used to investigate the integrity of the TSP. The eddy current method used a bobbin coil eddy current probe pulled through the SG tube at a maximum speed of 12 inches per second.
This is slower than the present speed of 24 inches per second used to inspect the SG tubing. Fifty SG tubes around each of the three Anti-Rotation Devices were inspected by this method. This satisfies one of the acceptance criteria. No operation induced degradation of the TSPs was identified. This satisfies one of the acceptance criteria, The eddy current method used to demonstrate the integrity of the TSPs was used on the fulllength of the SG tube. Therefore, although the 3.0 Volt IPC only applies to the hot-leg SG tubing, the integrity of the cold-leg TSPs was demonstrated.
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Inspection Near the Patch Plate Seam The 12 inch per second eddy current method mentioned above was also used to inspect the TSP at the Patch Plate Seams. Five tubes on each side of the seam were inspected j in the 1 A SG. No degradation was identified.
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! Presence of the Tube / TSP Intersection
- ' The normal SG tube bobbin coil eddy current inspection verified the presence of each SG tube / TSP intersection. No missing intersections were identified. This satisfies one of the acceptance criteria.
Visual Insoection Vertical Support Bars i
l A total of 89 Vertical Support Bars (VSB) and 157 VSB welds were visually inspected -
j from the four Unit 1 SGs. Of the VSB welds visually inspected,24 were mechanically
- cleaned prior to inspection to ensure a VT-1 quality inspection. The remaining VSBs and VSB welds were inspected following a SG tube Bundle Flush which performed
~ limited cleaning. No corrosion or distortion of the VSBs was identified in the visual inspection. No indications in the VSB welds that wou!d prevent the VSB from j performing its load-path carrying function were identified. This satisfies the acceptance ,
1 criteria.
Stayrod Nuts
, The Stayrod is screwed into the tubesheet at one end, and bolted on top of the lith TSP
- at the other. To ensure the Stayrod has not unscrewed from the tubesheet and that the
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nut on top of the 1Ith TSP has not loosened, nine of the eleven Stayrod nuts were i visually inspected in the 1 A SG. The Stayrod nut is tack welded to the TSP in two j locations and tack welded to the Stayrod in one location. Ten of the eleven nuts are
- within the bundle. The other nut is in the tubelane. No mechanical cleaning of the i' welds could be performed to improve the inspection. The nuts and welds were found
! to be scaled with an iron coating typical of the coating seen on SG tubing. The visual l inspection verified the welds were present, that the nut was in contact with the lith TSP, and that the nut could not unscrew from the Stayrod. This satisfies the acceptance criteria.
Wedges 4
No credit was taken for the TSP Wedges to limit the movement of the TSP during a
- MSLB. Therefore, the inspection of the Wedges is not critical. If during other visual 4 inspections, a Wedge was observed, the presence of the Wedge and the prewnee of the j weld connecting the Wedge to the SG Tube Bundle Wrapper was documented. Five 5
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. TSP Wedges were observed while inspecting the top of the 1Ith TSP. Four of the
- welds connecting the Wedge to the Wrapper could be verified. The fifth weld could 1 not be verified since the weld was under an inspection port. The presence of 32 other
- Wedges was verified while inspecting the VSBs on the bottom of the Flow Distribution
- Baffle. ' Since the inspection was from the bottom of the Flow Distribution Baffle, the presence of the weld connecting the Wedge to the Wrapper could not be identified.
The inspection of these TSP Wedges satisfies the acceptance criteria.
L Wrapper Alignment i The SG Tube Bundle Wrapper is supported by the SG shell. The Wrapper provides j support for the TSPs. Therefore, it is important to verify the Wrapper is properly supported. To verify the Wrapper is properly supported, the Wrapper was verified to be aligned at the four inspection ports just above the tubesheet. Visual inspections and q the ability to install the SG Sludge Lancing equipment ensured no misalignment )
between the SG shell and the SG Tube Bundle Wrapper. This satisfies the acceptance J criteria. )
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- Stayrod Spacers Visual inspections of the Stayrod Spacers were performed between the 8th TSP and the 9th TSP. Seven of the eleven Stayrod Spacers were inspected. No degradation of the Stayrod Spacers was observed. This satisfies the acceptance criteria.
TSP Visual Inspection j Visual inspections of the 1Ith TSP were performed near each of the three Anti-Rotation l Devices and along the Patch Plate Seam in the 1 A SG. Visual inspections were performed five row deep within the SG tube bundle. No cracking of the TSP ligaments was observed. This satisfies the acceptance criteria.
Conclusion i
The structural integrity of the load-path carrying components inside the Braidwood Unit i SGs was demonstrated through eddy current inspections and visual inspections. No degradation of these components was identified. This supports the implementation of the 3.0 Volt hot-leg IPC for Braidwood Unit 1.
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1 Attachment B i
Braidwood Unit-1 i
Cycle 6 Interim Plugging Criteria 90 Day Report j l February 1996 1
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