|
---|
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] |
Text
- ~.._ -_ - .- -. .- . . - - - - - . . . . - . . - .--
Osmmonwealth lifiwn Comguny tiraidwood Generating Station Routeal, llox 84 liraces ille. II. (in 1073)619 Tel8144 M 2801 1
October 8,1996 l ,
l United States Nuclear Regulatory Commission ]
Attention: Document Control Desk !
Washington, D.C. 20555-0001
Subject:
Revision 4 of the Inservice Inspection Plan 1 Braidwood Nuclear Power Station, Units 1 and 2 j Facility Operating Licenses NPF-72 and NPF-77 l NRC Docket Nos. 50-456 and 50-457 l
References:
- 1. Robert A. Capra (USNRC) letter to D. L. Farrar (Comed), Safety Evaluation of the Inservice Inspection Program Relief Requests Nos. NR-20, NR-21, NR-22 for Braidwood Station Units I and 2 (TAC Nos. M 92120, M92121) dated September 1, 1995.
Ladies and Gentlemen Commonwealth Edison Company's (Comed's) Braidwood Nuclear Power Station, Units I and 2 (Braidwood), performs inservice inspections (ISI) in accordance with Section XI of the 1983 Edition of the American Society of Mechanical Engineers Boiler and Pressure 4 Vessel Code through the Summer 1983 Addenda (ASME Code), as required by Title 10, Code of Federal Regulations, Part 50, Section 55a, Paragraph f, Subparagraph 3 [10 CFR 50.55a(f)(3)], except where alternatives have been authorized or relief has been requested and granted by the United States Nuclear Regulatory Commission (USNRC). j Revision 4 of the Braidwood ISI Program is provided in Enclosure 1. Attachment A provides a summary of all of the changes associated with this revision. These changes are briefly discussed below.
The ISI program is being revised to reflect changes in current plant configuration as a result of the Resistance Temperature Detector (RTD) modification. This modification has caused testing population and condition changes for both units by eliminating numerous welds. Revision 4 will also correct several minor typographical errors. Finally, this j revision will also incorporate existing, approved relief requests, and will submit new relief l requests. A brief discussion of the new relief requests associated with this revision of the l ISI program is included below:
t 9/
't 9610240014 961000 Ac0 ,
PDR ADOCK 05000456 G PDR
- A l'nicom Company w_.
USNRC Document Control Desk October 8,1995
- 1. NR-25 - Pressurizer Seismic Lugs: Subsection IWB, Table IWB-2500-1 Examination Category B-H, Item B8.20 requires surface or volumetric examinations ofintegrally welded attachments to the pressurizer.
- 2. NR Inaccessible Welds of Welded Attachments: Subsection IWC, Table IWC-2500-1, Examination Category C-C, Item C3.20 requires surface examinations ofintegrally welded attachments to piping.
- 3. NR Limited Exams of Reactor Vessel Welds: Subsection IWB, Examination Category B-D, Item B3.90 requires essentially a 100% volumetric examination of the region described in Figure IWB-2500-7 for reactor vessel nozzle-to-vessel welds.
- 4. NR Limited Exams Reactor Vessel Nozzle Inner Radius Sections: Subsection IWB, Table IWB-2500-1, Examination Category B-D, item B3.100 requires essentially a 100% volumetric examination of the inner radius region described in figure IWB-2500-7 for reactor vessel nozzle inner radius sections.
l i
- 5. NR Use of PDI/ Appendix VIII Y chniques on Reactor Vessel Shell Welds:
Subsection IWB, Table IWB-2500-1, Examination Category B-A, items Bl.11, Bl.21, Bl.30 require volumetric examinations be performed on selected reactor vessel welds. These volumetric examinations are to be performed in accordance with IWA-2232. IWA-2232 states that these inspections shall be conducted in accordance with Article 4 of Section V, as amended by section XI.
- 6. NR Use of Code Case 522: ASME section XI, Table IWC -2500-1, Examination Category C-H, requires the performance of a visual VT-2 examination during a system pressure test on Code Class 2 pressure retaining components. Note 7 of this table states: "The pressure boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function of the system is required." {
- 7. NR-31 Limited volumetric examination of reactor vessel circumferential shell weld: Sub Section IWB, Table IWB-2500-1, Examination Category B-A, Item Number Bl.ll requires a 100% volumetric examination of the reactor vessel circumferential shell welds as detailed in Figure IWB-2500-1.
Comed respectfully requests USNRC review and approval of Relief Requests NR-25, NR-26, NR-27, NR-28, NR-29, NR-30 and NR-31 no later than January 31,1997, such oicisvp)98063 doc m
USNRC Document Control Desk October 8,1995 these requirements can be implemented during the upcoming Unit I and Unit 2,1997 outages. These outages represent the last outages in the first ISI interval for Braidwood Station.
Please address any comments or questions regarding this matter to Mr. Douglas Huston, at (815)458-2801 extension 2511.
Very truly yours,
/ , ,
Y
' / .stanley o.
Site Vice Presi ent -
Braidwood Nuclear Station 1
Attachments (2)
Enclosures (2) cc: B. Beach, Regional Administrator - RIII l R. A. Assa, Braidwood Project Manager - NRR C. Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS 1
ottsvp)96053 doc
k j
i i
d Summary of Changes for Revision 4 of the Inservice Inspection Plan:
There are three basic reasons for revising the Inservice Inspection (ISI) Plan. The first is to reflect current plant configuration. Due to the RTD modification for both Units, populations and conditions have changed. The RTD modification has eliminated numerous welds and the Section 5 tables are being updated to reflect the new population. The second reason is to f address minor typo's. Several minor typos will be corrected. The third reason is to incorporate existing and new Relief Requests into the ISI Program Plan. The ISI Plan tables and sections were updated to reflect NR-23 (RHR Heat Exchanger) and NR-24 (Pressurizer Surge Nozzle) Relief Request submittals which have already been approved. Also, Braidwood is submitting new Relief Requests, NR-25 (Pressurizer Seismic Lugs), NR-26 (Inaccessible Welds of Welded Attachments), NR-27 (Limited Exams of Reactor Vessel Welds), NR-28 (Limited Exams Reactor Vessel Nozzle Inner Radius Sections), NR-29 (Use of PDI/ Appendix VIII techniques on Reactor Vessel Shell Welds), NR-30 (Use of Code Case 522) and NR-31
.i (Limited Exam of Reactor Vessel Shell Welds) for NRC review. A description of the changes )
is provided below: l
- 1) Cover page revised to reflect revision status, i.e. Revision 4.
l
- 2) Revision Summary sheet revised, page (i). Each page revision status is reflected on this summary sheet. ,
- 3) Some pages in Section 3 have been revised or added. Changes to the relief request section are summarized below:
a) Within this section, page 3-3 was revised to reflect the inclusion of relief requests NR-23, NR-24, NR-25, NR-26, NR-27, NR-28, NR-29, NR-30 and NR-31.
b) Typo on NR-7, page 3-13, was corrected. Weld IRC-162 was corrected to 1RC-16-2.
c) Page 3-38, " Approval Status" was updated to reflect the current status of the relief request.
d) Page 3-40, " Approval Status" was updated to reflect the current status of the relief request. i e) Typo on NR-22, page 3-41, was corrected. The description section misplaced the word " pressure", and was corrected to read " Alternate Rules for 10 Year Hydrostatic Pressure Testing for Class 3 Systems". Also, on page 3-42 Page1
" Approval Status" was updated to reflect the current status of the relief request.
f) Relief Request NR-23, " Alternate Examination of Nozzle to Vessel Welds -
Residual Heat Removal Heat Exchangers", pages 3-43 to 3-47 are being incorporated into the ISI Plan, g) Relief Request NR-24, " Pressurizer Surge Nozzle to Vessel Weld and Pressurizer Surge Nozzle Inner Radius Section", pages 3-48 to 3-56 are being incorporated into the ISI Plan.
h) Relief Request NR-25, " Alternate Rules for the Inservice Inspection of the Pressurizer Seismic Lug Welds", pages 3-57 to 3-63 are submitted for NRC review and are being incorporated into the ISI Plan.
i) Relief Request NR-26, " Alternate Rules for the Inservice Inspection of Inaccessible Welds on Welded Attachments", pages 3-64 to 3-71 are submitted for NRC review and are being incorporated into the ISI Plan. !
j) Relief Request NR-27, " Alternate Rules for the Inservice Inspection of Reactor Vessel Nozzle to Vessel Welds", pages 3-72 to 3-74 are submitted for NRC review and are being incorporated into the ISI Plan. !
k) Relief Request NR-28, " Alternate Rules for the Inservice Inspection of Reactor i Vessel Nozzle Inner Radius Sections (IRS)", pages 3-75 to 3-78 are submitted for NRC review and are being incorporated into the ISI Plan.
i
- 1) Relief Request NR-29, " Alternate Rules for the Inservice Inspection of Reactor Vessel Circumferential Shell Welds, lower Head Circumferential Weld and Shell to Flange Weld", pages 3-79 to 3-80 are submitted for NRC review and are being incorporated into the ISI Plan.
m) Relief Request NR-30, " Alternate Rules to Table IWC-2500-1, Category C-H:
Pressure Testing of Containment Penetration Piping with Attached Nonclassed Piping", pages 3-81 to 3-82 are submitted for NRC review and are being incorporated into the ISI Plan.
n) Relief Request NR-31, " Limited Volumetric Examination of Reactor Vessel Circumferential Shell Weld", pages 3-83 to 3-86 are submitted for NRC review and are being incorporated into the ISI Plan.
l l
Page 2
W 4
- 4) Some pages in Section 4 have been revised or added. Changes to the Technical Approaches and Positions Section are summarized below:
i
, a) Within this section, page 4-2 is revised to reflect the addition of Note 18 (Code i
Case N-356) and Note 19 (Code Case N-460).
i
- b) Note 18 was added (Rev. 4 submittal) to allow the use of Code Case N-356.
i l c) Note 19 was added (Rev. 4 submittal) to allow the use of Code Case N-460.
- 5) Section 5 contains the ISI Plan Summary. This section contains information on Code
- Category, Item and total number of welds. This section was revised to reflect new e
weld populations due to plant modifications and references to Relief Requests NR-23, NR-24, NR-25, NR-26, NR-27, NR-28, NR-29 and NR-30.
a) Page 5-2, item numbers Bl.11, Bl.21 and Bl.30, were revised to reflect reference to NR-29 and/or NR-31.
i b) Page 5-5, item numbers B3.90, B3.100, B3.110 and B3.120, were revised to reflect reference to NR-24, NR-27 and NR-28.
i i
l c) Page 5-6 was revised to provide proper spacing between lines. No information
- was changed on this page. >
7
! d) Page 5-13, item number B7.50, was revised to reflect new component populations due to the Unit I and 2 RTD modification.
! e) Page 5-14, item number B7.70, was revised to reflect new component j populations due to the Unit I and 2 RTD modification.
i f) Page 5-15, item number B8.20, was revised to reflect new component
. populations and reference to NR-25.
! g) Page 5-16, item numbers B9.21, B9.32 and B9.40 was revised to reflect new component populations due to the Unit I and 2 RTD modification. Also, item j number B9.21 Exam Requirements was revised from "Vol and SUR" to "SUR" ,
to reflect proper code examination requirements, l
i Page 3
I h) Page 5-17, item number B10.10, was revised to reflect new component populations due to the Unit I aad 2 RTD modification. l i
i) Page 5-22, item number C2.21, Relief Request column was revised to correct a typo and change reference of "NR-20" to "NR-23".
j) Page 5-24, item number C3.20, Relief Request column was revised to reference "NR-26". Also, the " Remarks" column was corrected to reflect the proper :
number of components selected for inspection, Unit 1 from "26" to "37" and l Unit 2 from "33" to "37".
k) Page 5-26 had its page format corrected. Also, hem number C5.32, was revised to correct typo "3-41" to "3-Ul" and to ado "SUR" to Exam Requirements column.
- 1) Page 5-27, item numbers C7.30, C7.40, C7.70 and C7.80, were revised to ,
reference "NR-30".
l l
m) Page 5-28, item number Dl.20, was revised to correct component population of !
Unit I from "46" to "44" and " Remarks" column selected components from l
"35" to "33". Also, correct typo of "VT-3/4" in the Exam Requirements i column to "VT-3". l 1
n) Page 5-29, item number D3.20, was revised to correct component population from "1" to "0" and remove "VT-3/4" in the Exam Requirements column.
o) Page 5-30, Augmented High Energy Main Steam and Feedwater populations revised to correct component population on Unit I from "282" to "314" and on Unit 2 from "297" to "330".
i i
l j
Page 4