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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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Commonwealth Edison One First Nationa! Plaza. Chicago, Ifinois Address Reply to: Post Office Box 767 Chicago. Illinois 60690 January 31, 1985 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Braidwood Station Units 1 and 2 Response to Inspection Reports Nos.
50-456/84-21 and 50-457/84-20 NRC Docket Nos. 50-456 and 50-457 Referennce (a): R. F. Warnick letter to Cordell Reed dated November 20, 1984
Dear Mr. Keppler:
This letter is in response to the inspection conducted by Messrs. L. G. McGregor and R. D. Schulz on September 4 through October 5, 1984, of construction activities at Braidwood Station.
Reference (a) indicated that certain activities appeared to be in noncompliance with NRC requirements. Our response to these items is provided in the enclosure to this letter. As noted in Reference (a),
no response to the Notice of Violation Item 3 was required. However, we are submitting a response in order to clarify our position'on this issue. The delay in providing this response was discussed with Messrs. R. F. Warnick and P. R. Pelke of your office on December 17, 1984, and January 16, 1985, respectively.
Should you or your staff have any questions regarding this matter please contact this office.
Very truly yours
=& W" Dennis L. Farrar Director of Nuclear Licensing Enclosure cc: NRC Resident Inspector FEB 51985 8506140507 850131 l PDR ADOCK 05000456 s g G PDR 558/
c ENCLOSURE COMMONWEALTH EDISON COMPANY 50-456/84-21 AND 50-457/84-20 ITEM 456/84-21-01 AND 457/84-20-01
__ ITEM 456/84-21-02 AND 457/84-20-02 ITEM OF NONCOMPLIANCE
- 1. 10 CFR 50, Appendix B, Criterion IX, states in part: " Measures shall be established to assure that special processes, including welding . . . are controlled and accomplished . . . in accordance with applicable codes, standards, specifications, criteria, and other special requirements."
Commonwealth Edison Company FSAR, Volume 7, and Sargent and Lundy Structural Steel Specifications, F/0-2735, Structural Steel and F/L-2722, General Structures Work, commit to AWS Dl.1, 1975, Structural Welding Code.
AWS D1.1, Structural Welding Code, states in.part, in Section 3.10: " Welded joints shall not be painted until after the work has been completed and accepted". Section 6.5.1 of AWS Dl.1 states: "The Inspector shall make certain that the size, length, and location of all welds conform to the requirements of this code and to the detail drawings, that no specified welds are omitted,
. and that no unspecified welds have been added without approval."
Section 6.5.5 states in part that the Inspector shall examine the work to make certain that it meets the requirements of Section 3, Workmanship and Section 8.15, Quality of Welds. Section 8.15.1, Visual Inspection, states in part: "All welds shall be visually l inspected."
Contrary to the above:
- a. One hundred and twenty safety-related structural steel fillet welds were painted prior to acceptance of the l
work and the welds were subsequently visually inspected for acceptance, with 79 accepted in the painted condition. The welds are identified in visual j inspection reports 709VW, 711VW, 713VW, 716VW, and 717VW.
- b. Visual weld inspections which identify acceptable workmanship, size, length, location of welds, and that no unspecified welds were added, were not performed on i safety-related full penetration welds completed under
- the jurisdiction of Structural Specifications F/L-2735 and F/L-2722 prior to May 1, 1984. The welds were
- accepted based on other methods of nondestructive i examination, but were not accepted in accordance with l
the requirements of Section 8.15, Quality of Welds, Visual Inspection.
t
p-e
. ITEM 456/84-21-01 AND 457/84-20-01 ITEM 456/84-21-02 AND 457/84-20-02 RESPONSE PART la'
. Commonwealth Edison agrees that certain structural steel fillet
- ~
iwelds were painted prior to acceptance of work.
CORRECTIVE ACTION-TAKEN'AND-RESULTS ACHIEVED' PART la At1the time of the-original inspection by the NRC and the identification of this area as an unresolved item (456/84-08-03; 457/84-08-03) the Independent Testing Lab. initiated NCR No. 191 to disposition the. inspections performed through paint. A 100%
review of the affected records was performed. Only Visual Weld Reports 709, 711,.713, 716, and 717 encompassing the 122 welds
- were identified as being performed through paint. ..The paint was removed and.a reinspection was performed. This inspection determined that 23 of the 122. welds reinspected required repair.
.Two. welds were found to be inaccessible for reinspection. One was documented and dispositioned on Commonwealth Edison Company NCR.No. 628 and the.other was documented on Commonwealth Edison Company NCR.No. 700.
CORRECTIVE' ACTION TAKEN T0 AVOID FURTHER NONCOMPLIANCE - PART la
'The review of the affected reports determined that inspection of structural welds."through paint" occurred during a one week period in,1980 and was limited to the five reports identified.
To' prevent: recurrence, the Independent Testing Lab has been directed to perform first line weld inspections only in the unpainted condition.
DATE OF FULL-COMPLIANCE -PART la Completion of repairs and reinspection of the subject welds is expected-by May 1, 1985.
i?
n s
ITEM 456/84-21-01 AND 457/84-20-01 ITEM 456/84-21-02 AND 457/84-20-02 RESPONSF - PART lb CECO agrees that in accordance with the requirements of AWS, a visual inspection of full penetration welds is required even if other NDE is specified.
However, in resolving this item, AWS Dl.1 does not preclude the Architect Engineer from performing an engineering evaluation of weld inspections. In addition, in the footnotes to Table 3.8-2 of the Byron /Braidwood FSAR, it is stated that clarification to, and deviations from portions of AWS Dl.1, " Structural Welding Code", are made based on engineering evaluations.
CORRECTIVE ACTION AND RESULTS ACHIEVED - PART lb
' Commonwealth Edison NCR 616 Revision 1 requested an evaluation of alternate NDE in lieu of visual examination as defined in AWS Dl.l. The Architect / Engineer has accepted the MT/PT examination results for the quality aspects of the separate AWS visual examination. The size, length, and location aspects will be evaluated as noted in Revision 2 of NCR 616.
CORR CTIVE ACTION TAKEN TO AVOID-FURTHER NONCOMPLIANCE - PART lb Specification F/L-2722 has been revised to more clearly identify the requirements for visual inspection of full and partial penetration groove welds. The structural steel installation contractor-procedure #55 has been revised to incorporate the i revised specification requirements for visual weld inspection.
DATE OF FULL COMPLIANCE - PART lb At this time, the date of full compliance cannot be determined pending final evaluation of NCR 616 Revision 1 and 2 and determination of the extent of the corrective action.
Evaluation of the acceptability of past practices is expected prior to January 1986. As of May 1, 1984, full penetration welds under Specification F/L 2722 are being visually inspected. No further field work is being performed under Specification F/L 2735. Current activities are in compliance.
r s
ENCLOSURE COMMONWEALTH EDISON COMPANY RESPONSE T0' INSPECTION REPORT 50-456/84-21 AND 50-457/84-20 ITEN 456/84-21-03 AND 457/84-20-03 ITEM OF NONCOMPLIANCE
- 2. 10'CFR 50, Appendix B, Criterion V, states in part that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, and shall be accomplished in accordance with these instructions, procedures, or drawings.
Piping Contractor Procedure, QAP-110, Reporting of Defects and Noncompliance, Revision 1, requires that a noncompliance of basic component or activity supplied to the owner of a licensed facility shall be reported to the owner by the Manager - Quality Acsurance under the requirements of 10 CFR 21.
Contrary to the above: On June 13, 1984, during receipt inspection an 8" S/120 SA-106 GR.B piece of pipe, heat No.
93739 -10 feet long, was found by the piping contractor's qualify control department to violate minimum wall
. requirements. This defect was not reported to the owner in accordance with 10 CFR 21.21 and Procedure QAP-110. The pipe furnished to the Braidwood facility, under the requirements of 10 CFR 21, was classified as ASME Boiler and Pressure Vessel Code, Section 3, Subsection NC, Class 2, Pressure Boundary Piping.
< RESPONSE Phillips Getschow Company performed a receiving inspection for one ten foot length of 8" S/120, .718" wall SA-106 Gr. B pipe.
Measurements for the end 2 feet of the pipe showed the wall dimension varied from .001 to .009 inches below the minimum wall requirement of .629 inches.
Phillips Getschow procedure QAP-110 requires Phillips Getschow Company to notify Commonwealth Edison of a suspected deviation or noncompliance, utilizing the Report of Noncompliance Form.
Commonwealth Edison agrees that Phillips Getschow did not report the deviation to Commonwealth Edison as required. Evaluation of the deviation is the responsibility of Commonwealth Edison.
When the nonconforming condition was identified, and contrary to their procedure, an evaluation was performed (although not ITEM 456/84-21-03 AND 457/84-20-03 documented)1byLPhillips Getschow Company.
Their evaluation determined this condition to be not reportable under the provisions of 10 CFR'Part 21 and they-did not notify Commonwealth Edison. Although Phillips Getschow Company did not properly notify Commonwealth Edison of this deviation, we would have been adequately informed by receipt of the Phillips Getschow. Company NCR had it been properly processed.
Phillips Getschow: Company NCR 1615 which documented the minimum wall violation, was initiated on 6/13/84, dispositioned to remove and_ scrap the nonconforming section 6/28/84, and closed on:7/25/84. Phillips Getschow Company did, however, fail to route'this NCR-through Commonwealth Edison Company for disposition concurrence. This failure to route the NCR to Commonwealth Edison Company for disposition concurrence was documented on Phillips Getschow Company NCR 2027 dated 9/4/84.
NCR's11615 and 2027 were reviewed-by Commonwealth Edison Company
' Project Construction Department on 9/13/84.- This included a review for reportability.
CORRECTIVE ACTION TAKEN AND-RESULTS ACHIEVED As a result of the concerns raised.by the NRC Inspector, Phillips Getschow Company issued a Report of Noncompliance to Commonwealth Edison Company in accordance with QAP-110.
Braidwood Project Field-Engineering performed a review for reportability under the provisions of 10 CFR Part 50.55(e).
.This review included a-check for reportability under 10 CFR Part
- 21. Based.on such a small sample, Commonwealth Edison Project Engineering Department was requested to perform an-evaluation pursuant.to 10 CFR Part 21 and the piping supplier was notified of the nonconforming condition. The Project Engineering Department evaluation determined the condition not to be reportable.
1 CORRECTIVE ACTION TAKEN TO AVOID FURTHER NONCOMPLIANCE Commonwealth Edison has discussed this item with-appropriate Phillips Getschow Company personnel to enhance awareness of the reporting requirements of procedure QAP-110 " Reporting of Defects and Noncompliance".
DATE OF FULL COMPLIANCE Full compliance has been achieved.
ENCLOSURE COMMONWEALTH EDISON COMPANY 50-456/84-21 AND 50-457/84-20 ITEM 456/84-21-07 AND 457/84-20-07 ITEM OF NONCOMPLIANCE
- 3. 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, states in part, " Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected".
The Braidwood FSAR, Amendment 43 and the Commonwealth Edison
' Company' Quality Assurance Manual commit to Regulatory Guide 1.116 , June 1976 which endorses ANSI N45 2.8, 1975, Supplementary Quality Assurance Requirements for Installation, Inspection and testing of Mechanical Equipment And Systems For The Construction Phase of Nuclear Power Plants.
ANSI N45 2.8, states in part in Section 3, Pre-Installation Verification, that inspections or checks shall be performed and include verifications such as removal of packaging, conditioning, and cleaning. Section 4, Control During Installation Process, states in part that inspections of the work' areas and the work in progress shall be performed for mechanical items and shall include cleanliness inspections and inspections to assure that items will not be contaminated as a result of adjacent construction activities.
ANSI N45 2.8. states in part in Section 2.4, Cleaning, that cleaning shall be performed in accordance with ANSI N45 2.1, 1973.
ANSI N45 2.1 states in part in Section 2, General Requirements, that the work and quality assurance requirements for the cleaning of items and systems to be incorporated in the Nuclear Power Plant and control of cleanliness thereof shall be established in order to (1) ensure the removal of any deleterious contaminants, (2) minimize recontamination of cleaning surfaces, and (3) minimize the cleaning required after installation. Section 4, Pre-Installation Cleanness, states in part that inspections, examinations, and tests as appropriate shall be performed immediately prior to installation to determine the cleanliness of the item.
i l
ITEM 456/84-21-07 AND 457/84-20-07
- ITEM OF NONCOMPLIANCE (cont'd)
Contrary to the'above, after:an NRC inspection (82-05)
. identified that the licensee failed to. implement a quality assurance program for.the erection of mechanical safety-related equipment,.the piping / mechanical equipment contractor identified numerous . pieces of mechanical. equipment
.that had been installed without quality control verification of internal cleanliness. Although these nonconforming
. conditions were reported to the-licensee, the licensee failed
'to adequately evaluate or take corrective. action. The common evaluation of these nonconforming conditions was to waive the cleanliness inspection and " flush it clean". Quality control inspections ofEinternal cleanliness had not been formulated during the installation process to assure the absence of corrosion, pitting and contaminants including foreign objects that may affect the safe and reliable operation of safety-related equipment.
COMMONWEALTH-EDISON COMPANY POSITION CLARIFICATION Although no r uponse to this Item of Noncompliance was required, Commonwealth Edison wishe's to clarify our position with respect to
-it.
o
!As stated in the Item of Noncompliance, during the mechanical equipment ~ retro-inspection resulting from NRC inspection 82-05, some pieces of equipment had no documentation showing-that
. l cleanliness inspections were performed during initial installation activities. -This lack of documentation does not imply cleanliness
-inspections were not performed at the time of initial installation
, l activities. Commonwealth Edison Company had sufficient confidence
~ in system cleanliness during initial ~ installation activities to
. warrant their disposition of waiving equipment disassembly and Lusing the piping system flushing program to demonstrate system
' cleanliness. Much of the equipment-has been flushed, and the
. flush'results indicate that the systems were clean. To date eleven (11) pieces of mechanical equipment on systems that had been' flushed have been opened.- The mechanical equipment was clean. The program established under Commonwealth Edison NCR-614 is a reverification to. add further confidence in internal equipment cleanliness.
' l n
h[
- ENCLOSURE COMMONWEALTH EDISON COMPANY RESPONSE TO INSPECTION REPORT 50-456/84-21-AND 50-457/84-20 ITEM 456/84-21-08 AND 457/84-20-08
- ITEMLOF-NbNCOMPLINCE 4.. 10 CFR 50, Appendix B, Criterion IX, requires measures to be established to assure that special. processes, including welding, heat treating and nondestructive testing, are controlled and accomplished by qualified personnel.using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other.special requirements.
ANSI N45.2 states in part: Qualification of personnel, procedures, and equipment shall comply with the requirements of applicable codes and standards. Documentation shall be maintained for currently
~
_ qualified personnel, processes, or equipment in accordance with the
-requirements of pertinent codes and standards. For special processes not1 covered by existing codes and standards, or where item quality requirements exceed the requirements of established codes or
' equipment standards,shall the necessary be defined.
qualifications of personnel, procedures, or
' Construction Specification.No.. L2797 NSSS Support Steel for Braidwood Station Unit 1 and 2. requires: material tests and
. reports, such as required in NF-2000 of ASME Code Section III, certified copies of Charpy Impact Tests and Lamination Tests, material 1 identified as specified in NF 2150 of' ASME Section III, records of welding which conform to ASME Section III Subsection NF i
' Article 4000, Fabrication, test.and inspections applicable to ASME Code Section-III.
g Braidwood Quality Assurance Manual, Section 9, Procedure 9-1, states in part: "The contractor is responsible for preparing and submitting ~his procedures for the control of special- processes for review and acceptance in accordance with Quality Procedure 5-1. He is also responsible to maintain records that identify qualified
. personnel'where qualification is required for special processes involved. . The site Quality Assurance Superintendent is responsible for assuring that records of qualified personnel are maintained by
, the on-site contractor for work performed for Commonwealth Edison
' Company. He is also responsible for assuring that inspections and records verifying special processes at designated inspection notifications points specified in procedures are performed. For welding, records of filler metal (not only weld rod) shall be kept ITEM 456/84-21-08 AND 457/84-20-08 ITEM OF NONCOMPLIANCE (cont'd) for material traceability to the welder perlorming the work or as otherwise provided by the ASME Code for such Code work. Also, the specifying of the weld procedure and weld material shall be performed by competent personnel not directly involved in the welding, i.e., the welder or his foreman shall not select the procedure or weld material. In addition, a quality control surveillance of in-process welding shall include inspection of fitup and of a portion of the welding".
Contrary to the above requirements, a newly designed reactor coolant pump lateral support anchorage was installed in Units 1 and 2 without records to establish the material heat number, Charpy impact tests, lamination tests, welder identification, weld procedure, weld filler material, in-process inspections and other quality related records.
RESPONSE
Commonwealth Edison agrees that the subject lateral support was installed without Charpy impact tests and that the welder identification could not be established by records. The other inspections / records identified by the inspector are not required because this installation is not within the established jurisdictional boundary of the ASME Code. The design change and subsequent field modification to the subject Reactor Coolant Pump Lateral Support was handled in accordance with the Commonwealth Edison Company Quality Assurance Manual and the applicable approved contractor procedures in effect at the time of the modification.
The interference problem between the box beam and the embedments was design in nature. The relationship between the box beam and the embedment at Braidwood is similar to that at Byron. As stated by the Inspector, a cope of the box beam was utilized at Byron to resolve the interference. When the interference was identified at Braidwood, a cope design similar to that used at Byron was established and could have been installed at Braidwood. An alternate design established on FCR L506 was elected to resolve the interference of the box beam and the lateral supp3rt at Braidwood Station for economic reasons.
Commonwealth Edison Company takes exception to the statement that the necessary records to support the design change are inadequate or nonexistent. When the interference was identified, a Field Change Request (L-506-Unit 1 and L-775-Unit 2) was initiated by Commonwealth Edison Company, in accordance with the Commonwealth Edison Company Quality Assurance Manual, to obtain the necessary design change prior to continuing installation activities. Upon approval of the FCR, the modification was assigned to the structural steel contractor for implementation.
p y .
50-456/84-21 AND 50-457/84-20 Commonwealth Edison Company contends the design meets the FSAR requirements and the design change was made in accordance with the approved Quality Assurance Program as summarized below:
- 1. The box beam which the brace connects to is sufficiently rigid relative to the brace to assume fixed support of the brace.
The calculations which support FCR L-506 show the stiffness of the box beam is 40 times that of the brace and thus total brace stiffness of the installed design is reduced by a negligible amount.
- 2. .The temperature differential between the brace and box beam will be smaller than that between the brace and the secondary shield wall because the concrete shield wall will heat up at a slower rate than the steel box beam. In either case the brace member need not be designed for faulted condition temperature effects per the ASME Code Section III Appendix F Article F1310.
3.- The records to support the design review and approval are contained in Sargent and Lundy Calculations for FCR L-506.
- 4. The subject change to the reactor coolant pump supports has no impact on FSAR Section 3.9.3.4.1.4 which describes the reactor coolant pump supports.
5.- For those portions of the brace detail within the ASME jurisdictional boundaries, the design is in accordance with the ASME Code.
The installation af the gusset plates was performed by Napolean Steel Contractor, Inc. under their approved Quality Program in accordance with Sargent and Lundy Specification L-2722. The reference to Specification L-2797 for installation is not applicable. Specification L-2797 is the specification for fabrication of the NSSS Supports performed by Teledyne Brown. The installation of the gussets was performed using safety related material by qualified welders'using approved welding procedures.
- The weld inspe~ctions were performed by Commonwealth Edison Company's Independent Inspection Agency.
f -
50-456/84-21 AND 50-457/84-20 CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED During the investigation of this item, Commonwealth Edison Company identified that A588 material procured and installed as the gusset plate did not have the testing required by FCR's L-506 and L-775. Subsequently, Commonwealth Edison Company NCR 661 was initiated to identify and resolve the apparent nonconforming condition. As a result of the NCR, Sargent and Lundy issued ECN 23836 deleting the additional testing requirements. The deletion of testing requirement is consistent with the Sargent & Lundy design specification for structural steel. NCR 661 is currently in routing for closure.
The welder has been identified and his qualifications verified.
Material certifications have been assembled. These records and the Independent Inspection Agency weld inspection records are available for NRC review.
CORRECTIVE ACTION TAKEN TO AVOID-FURTHER-NONCOMPLIANCE The contractor organization which installed this lateral support is no longer onsite. Current site contractor's welding procedures conform to applicable AWS Dl.1-1975, ANSI N45.2 and Commonwealth Edison Company Quality Assurance Manual Requirements.
DATE OF FULL COMPLIANCE Commonwealth Edison NCR 661 review and closure is expected to be complete by March 1, 1985.
9685N
