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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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/ "j%'3y Q one rnu Nancnal Plaza Chr.ago. jn.nois Add'ess Reply to. Post Othcc Box 767
'(
Chicago, lilinois 60690 September 7, 1978 Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Braidwood Station Units 1 a'nd 2 Response to IE Inspection. Report Nos. 50-456/78-06 and 50-457/78-06 NRC Docket Nos. 50-456 and 50-457 Reference (a) : R. F. Heishman letter to Byron Lee, Jr.
dated August 7, 1978 l NRC Docket Nos. 50-456 and 50-457 l
Dear Mr. Keppler:
The following is in response to an inspection conducted-by Messrs. C. M. Erb, K. D. Ward and E. J. Gallagher l
of your office on June 13-15, 1978 of activities at Braidwood '
Station. FN. Heishman's letter, Reference (a), indicated that certain of our activities appeared to be in noncompliance with NRC requirements. The attachment to this letter discusses these items and, based on the additional information presented, requests your consideration in changing the first two items from infractions to observations. The attachment also requests that the third item of apparent noncompliance be placed in abeyance until Commonwealth Edison Company receives a response on the code inquiry which Commonwealth Edison has submitted to the American Society of Mechanical Engineers (ASME) Committee.
Please address any additional questions that you might have to this office.
Very truly yours,
( '
d[.b.du u(
ccL /Cordell Reed
-} { j 00jr 00 G/. . Assistant Vice-President attachment . 't ECO c
. - . -~ . .
, Common.wcalth Edison- SRC.Dochet Nos. 150--456/457-ATTACRMENT r .
LITEM A.1 i
Contrary to 10 CFR 50,. Appendix B, Criterion XII, the Braidwood Station PSAR, Chapter-17, and the Commonwealth Edison QA Manual, Quality Requirement QR-12, on June 13-15, 1978, the inspector determined that Pittsburgh Testing Laboratory (PTL) was using. standard sieves for acceptance of materials affecting quality, such as aggregate and soils gradation tests, that did not' meet the requirements of ASTM E-ll, " Standard Specification for Wire-Cloth Sieves used for Testing Purposes", in that the #8,
- 50, and #100 sieves had " punctures or other obvious defects in !
i the cloth". Furthermore, the PTL procedure QC-cal-3, Tools, Gauges,'and Instrument Control did not-include,these or any of the standard -sieves in the inspection and calibration frequency or control requirements.
RESPONSE
The apparent noncompliance involved the use of defective and "uncalibrate'd" sieves. The guidance which our testing laboratory is and has been using for. testing is the appropriate ASTM standards. Many standards relating to this area exist. By various ASTM. standards (C-136, 134, etc.) , Commonucalth Edison is l recuired to use . sieves manuf actured in accordance with ASTM E-ll.
ASTM.E-ll in tu'rn clearly _ states with a footdate to the scope section that " complete instructions.and procedures on the use of test si' eves are contained in ASTM STP~447". This cascading of standards forms the basis for applying the guidance of ASTM STP 447 for instructions on the use of test sieves as discussed below.
The NRC inspector observed four "obviously" defective sieves (one #8, two #50's, and one #100). Two of the sieves, one
- 8 and one #50, did indeed have punctured screens at the time of the NRC Audit. . The PTL Lab Supervisor acknowledged the fact that the two screens were now defective but stated that the two sieves were not damaged the previous day when he inspected them prior to their use ' in accordance with PTL . Procedure QC-LT-1. Further,-
ASTM STPc447A as. referenced' in ASTM E-ll states in part " holes or breaks; are sometimes --indicated -by very noticeable irregularities -
in the end-point weighings". N,o such irregularities have been observed. : In view lof ~ this, Codmonwealth Edison' is very confident that_no defective or punctured. sieves were used to perform any stests! In addition,Edue to the nature of the equipment, the physical:
condition'of-all^ sieves is examined prior to each test to assure that:no~defectiveLsieves.are used.
- -. , , . . ~ - - - - , . ... .-, , -..,,,.c. -,
Commonwealth Edison URC Docket Nos. 50-456/457 The physical condition of the two punctured sieves would have been observed and found unacceptable by PTL technicians during their routine pre-test equipment inspection. Upon observance of the defective nature of the sieves, they would have been immediately removed from use and replaced, as was the case.
The fact that the NRC inspector examined the two sieves prior to our required inspection should not be used as a basis for questioning the quality of future inspections. Furthermore, since time had elapsed since the last test was performed with these sieves, the NRC inspect'or should not assume that the physical condition found when examined also existed during previous tests. Rather, the fact that the sieves had not been placed in a protected storage area is a more plausible explanation for the condition of the sieves when observed by the NRC inspector. As a result, a special storage rock has been constructed for protection of sieves.
The inspector also observed two' additional defective sieves (one #50 and , one #10,0) . However, the inspection report did not clearly indicate the form of the defects in these sieves.
Although based on observations while accompanying the inspector during his examination and subsequent visual examinations, Commonwealth Edison personnel concluded that the referenced
" defects" were as follows: .
- 1. The #50 sieve was discolored due to use of a zine-chloride solution to perform the ASTM-Cl23 test for lightweight pieces in aggregate. ASTM-C123 specifics the use of sieves manufactured in accordance with ASTM E-ll.
However, neither ASTM-Cl23 nor ASTM STP 447 warns, or even cautions against the normal discoloration of brass sieves when used with zinc-chloride.
Therefore, Commonwealth Edison has concluded that discoloration is an expected condition and not a defect.
- 2. The.only observable discontinuity on the #100 sieve was an area which had been repaired by soldering. ASTM STP 447A " Manual on Test Sieving Methods" establishes and allows for this type of repair by stating in part "small holes can be repaired by soldering".
I
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' .' Commonwealth Edison "NRC Docket 5os.150-456/457 q If;the discontinuities, as discussed above, were not 3 the cause of the apparent noncompliance, Commonwealth Edison 'l 7
would ' appreciate a prompt disclosure of their exact. nature. ]
if'the " defects" were as previously-described, l
However, C'ommonwealth Edison requests - that the NRC reconside r it s j j
findings since no physical requirements appear to have baen v iola,t e d . . In~ addition, ' Commonwealth Edison is concerned that - ,
the aesthetics of the sieves-in a field laboratory environment-may have had~an undue influence on the inspector's observations.
The discolored #50 sieve and the solder repaired #100 sieve along with the two previously menti'oned defective sieves were removed from use immediately after the inspection. However, based on the above considerations, there appears'to be no reason why. the
- 50 and #100 sieves cannot,be returned to service.
The secondary portion of the apparent noncompliance deals- with the lack of a program for calibrating sieves to j
. ASTM'E-ll. Pittsburgh Testing Laboratory '(PTL) does not include the calibration of sieves in' its calibration procedures, QC-CAL-3,.because no calibration of sieves is required. ' ASTM E-ll Standard Specification for Wire-Cloth Sieves for Testing Purposes is a manufacturing standard. ASTM STP 447A, " Manual on~ Test l Sieving Methods", states that " ASTM Specifications E-ll specify ]
.certain~ manufacturing tolerances". Upon receipt of the sieves l PTL verifies that certification to ASTM E-11 accompanies each sieve.
According to ASTM STP 447A "a test sieve should retain the accuracy of.its openings throughout the lifs of the sieve, I since ordinary wear is on the top of the knuckles of the wire l cloth and no' measurable wear occurs in the openings".
Furthermore,. ANSI N45.2, Section 13 dealing with calibration states "This requirement. (for calibration) is'not intended to bmply a need for special calibration and control measures on rulers, tape measures, levels and such other devices if normal oractices provide adeauate accuracy". Commonwealth Edison feels that sieves are covered by this category since ASTM E-ll requires a permane'nt label stating certification be affixed to'the sieve by the sieve manufacturer and since the-previous quote from' ASTM 447A clearly implies that this is the case!'
The fact that ASTM E,ll:is a manufacturing standard ~
is- additionally reinforced by the following. statement on sieve y
. ' skirts '" . . . the: bottom of the frame or sieve skirt shall' be- ,
so constructed:as to have an easy sliding fit in any. sieve".
~
- . Thel NRC ' Inspection 1 Report references the aforementioned statement
.and continues with'"The inspector-observed thatLnone of the sieves;being used met this requirement". The. sieves in use are
.- .,. _ __,_. . _w , _ _ _ . _ _ , , ,
Commonwealth Edison NRC Docket Nos. 50-456/457 t
certified to be manufactured (constructed) to fit easily together, however, it is inconceivable that the slight !
tolerance dimension of +.03 in, referenced in ASTM E-ll is intended for' verification of test sieves being used in a field laboratory. The ASTM standard for " Test Sieving Methods" does I not appear to be concerned with the fit of the sieve skirts as l it does not even deign to mention this fact when describing the l effects of wear on the accuracy of the sieves. l At the time of the inspection, ASTM STP 447A " Manual on Test Sieving Methods" was not used as a basis for the NRC inspector's determination. By various ASTM standards (C-136, 134, etc.) Commonwealth Edison is recuired to use sieves !
manufactured in accordance with ASTM E-ll which states " Complete instructions and procedures on the use of test sieves are con- l tained in ASTM STP 447". ASTM STP 447 in turn refers to E-ll f to "specify certain manufacturers tolerances". Commonwealth j Edison is concerned that the requirements applicable to h manuf acturing and manuf acturer 's responsibilities were in- l correctly imposed on sieves being used in its field testing i laboratories. Therefore, based on this additional information which identifies a more appropriate baseline for interpretation ]
of the inspector's field observations, Commonwealth Edison recuests that the NRC reexamine this apparent item of noncompliance and consider changing this infraction to an ,
observation.
ITEM A.2 .
I Contrary to 10 CFR 50, Appendix B, Criterion XIII, and the Commonwealth Edison QA Manual Quality Requirement OR-13 which requires cleaning and preservation of materials in accordance with work and insp'ection procedures to prevent damage and deterioration, on June 13-15, 1978 the inspector determined that the Unit 1 & 2 tendon bearing plates and trumplets were not being maintained in accordance with specification L-2721, Section 2-303(d). This states, "the interior surfaces on all trumplets and funnels shall be protected from corrosion prior 3 to tendon and greasing installation by coating and inside surface with a film of . . . the contractor shall maintain this ;
coating protection during the entire course of work until tendons are in place and grease is installed" (emphacis {
included in spec.) The inspector observed 162 vertical tendon l bearing plates and trumplets in both Units 1 and 2 noted ,
surface corrosion in every instance.
i
- l Commonwealth Edison ~ NRC Docket Nos. 50-456/457 l 5- ;
1
RESPONSE
Commonwea".th Edison disagrees with the finding that there was surface corrosion in every instance. The inspector was informed that the great majority of the surface rusting was actually a coating of rust particles which had been washed down from the vertical sheathing. This was confirmed in the presence of the inspector by scraping some of this rust coating off the bearing plates, revealing that the plate surface coating was still intact.
Based on this information, Commonwealth Edison requests that the NRC reexamine this apparent item of noncompliance and consider changing this infraction to an observaItion.
As a further measure of protection, immediately after this inspection the coating of rust particles was removed from the vertical tendon bearing plates and trumplets in both Units 1 and 2 and an additional protective grea'e s coating was applied to minimize corrosion potential. This grease coating will be maintained on the bearing plates and trumplets with no further maintenance being conducted until just prior to the tendon installation at which time the surfaces of the beering plates ,
will be cleaned. In addition, monthly surveillanges of the !
tendon tunnel will be performed by the contractor in order to maintian this grease coating and minimize any corrosion potential.
ITEM A.3 Contrary to 10 CFR 50, Appendix B, Criterion IX; the Lraidwood PSAR, Table 3.2-2, which lists ASME Section III as'the applicable code for class 1,'2 and 3 components and piping systems; the S&L Specification No. L/F 2739 which specifies safety related piping shall be in accordance with ASME Section III, 1974 Edition; and subarticle NB5100, ASME Section III, which states in part that radiographic examination shall be in accordance with ASME Section V, Article 2, the inspector observed during review of radiographs of three welds that an Iridium 192 source had been used on material less than 0.75 inches without a special procedure being prepared and proven satisfactory by actual demonstration as require $ by ASME Section V.
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4
, ,. Commonwealth Edison NRC Docket Sc3 50-456/457
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RESPONSE
ASME Section V, Article.2, 1974 Edition states in part "A special procedure shall be prepared and proved ,
satisfactory by actual demonstration of penetrameter resolution." l It is Commonwealth Edison Company's interpretation that an additional "special" procedure is not intended by the code.
when an existing procedure produces radiographs of acceptable sensitivity. It is Commonwealth Edison's contention that the procedure is p'roven satisf actory with each radiograph shot "by actual demonstration of penetrameter resolution."
In order to clarify this position, Commonwealth Edison has submitted a code inquiry to the appropriate committee of the American Society of Mechanical Engineers. A written reply is anticipated from the committee byithe end of October 1978.
Therefore, Commonwealth Edison Company requests that this item of apparent noncompliance be placed in abeyance until Commonwealth Edison receiver a response on this code inquiry.
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Commonwealth Edison
- ', y ] ow ras! Nax.nai Piara Crr.ago pno's Acc ess Reply lo Post O!!+ce Box 767
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Chicago. libnois 60690 Septem'oer 7, 1978 Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Braidwood Station Units 1 a'nd 2 Response to IE Inspection Report -
Nos. 50-456/78-06 and 50-457/78-06 NRC Docket Nos. 50-456 and 50-457 Reference (a) : R. F. Heishman letter to Byron Lee, Jr.
dated August 7, 1978 NRC Docket Nos. 50-456 and 50-457
Dear Mr. Keppler:
The following is in response to an inspection conducted by Messrs. C. M. Erb, K. D. Ward and E. J. Gallagher of your office on June 13-15, 1978 of activities.at Braidwood Station. Mr. Heishman's letter, Reference (a), indicated that certain of our activities appeared to be in noncompliance with NRC requirements. The attachment to this letter discusses these items and, based on the additional information presented, requests your consideration in changing the first two items from infractions to observntions. The attachment also requests that the third item of apparent noncompliance be placed in abeyance until Commonwealth Edison Company receives a response on the code inquiry which Commonwealth Edison has submitted to the American Society of Mechanical Engineers (ASME) C omraitt e e .
Please address any additional questions thct you might have to this office.
Very trulv vours, LPD1L -
~78 / 0 0 5'00 6 / )) ~ .da u'L "Cordell Reed Assistant Vice-President PDK A M c-k- os v- yrs 9 76%9 xy .p'
- a t t a C h'.*.e nt h " h I,
(>Q "Q~ j
Commonwealth Edison NRC Docket Nos. 50-456/457 ATTACHMENT
_I_ TEM A.1 l
Contrary to 10 CFR 50, Appendix B, criterion XII, the Braidwood Station PSAR, Chapter 17, and the Commonwealth Edison l
QA Manual, Quality Requirement QR-12, on June 13-15, 1978, the l inspector determined that Pittsburgh Testing Laboratory (PTL) was I using standard sieves for acceptance of materials affecting quality, such as aggregate and soils gradation tests, that did not meet the requirements of ASTM E-11, " Standard Specification for Wire-Cloth Sieves used for Testing Purposes", in that the #8,
- 50, and #100 sieves had " punctures or other obvious defects in the cloth". Furthermore, the PTL procedure QC-cal-3, Tools, Gauges, and Instrument Control did not include,these or any of the standard sieves in the inspection and calibration frequency <
or control requirements.
RESPONSE
The apparent noncompliance involved the use of defective and "uncalibrated" sieves. The guidance which our testing laboratory is and has been using for testing is the appropriate ASTM standards. Many standards relating to this area exist. By various ASTM standards (C-136, 134, etc.), Commonwealth Edison is recuired to use sieves manuf actured in accordance with ASTM E-ll.
~
ASTM E-ll in tu'rn clearly states with a footdote to the scope section that " complete instructions and procedures on the use of test si' eves are contained in ASTM STP 447". This cascading of standards forms the basis for applying the guidance of ASTM STP 447 for instructions on the use of test sieves as discussed below.
The NRC inspector observed four "obviously" defective j sieves (one #8, two #50's, and one #100). Two of the sieves, one :
- 8 and one #50, did indeed have punctured screens at the time of the NRC Audit. The PTL Lab Supervisor acknowledged the fact that the two screens were now defective but stated that the two sieves were not damaged the previous day when he inspected them prior to their use in accordance with PTL Procedure oc-LT-1. Further, ASTM STP 447A as referenced in ASTM E-ll states in part " holes or breaks are somet ime s indicated by verv noticeable irregularities in the end-point weighings". No such irregularities have been observed. In view of this, Cochonwealth Edison is very confident that no defective or punctured sieves were used to perform any tests! In addition, due to the nature of the equic=ent, the physica!
condition of all sieves is examined prior to each test tc assure that no defective sieves are used.
l
I
', Commonwealth Edison NRC Docket Nos. 50-456/457
~
t i
The physical condition of the two punctured sieves would have been observed and found unacceptable by PTL technicians during their routine pre-test equipment inspection. Upon obser'vance of the defective nature of the sieves, they would have been immediately removed from use and replaced, as was the case.
The fact that the NRC inspector examined the two sieves prior to our required inspection should not be used as a basis for questioning the quality of future inspections. Furthermore, since time had elapsed since the last test was performed with these sieves, the NRC inspect'or should not assume that the physical condition found when examined also existed during previous tests. Rather, the fact that the sieves had not been placed in a procected storage area is a nore plausible explanation for the cordition of the sieves when observed by the NRC inspector. As a result, a special storage rack has been constructed for protection of sieves.
The inspector also observed two additional defective sieves (one #50 and one #10,0) . However, the inspection report did not clearly indicate the form of the defects in these sieves.
Although based on observations while accompanying the inspector during his examination and subsequent visual examinations, Commonwealth Edison personnel concluded that the referenced
" defects" were as follows: .
- 1. The #50 sieve was discolored due to use of a zinc-chloride solution to perform the ASTM-Cl23 test for lightweight pieces in aggregate. ASTM-C123 specifies the use of sieves manufactured in accordance with ASTM E-ll.
However, neither ASTM-Cl23 nor ASTM STP 447 warns.
or even cautions against the normal discoloration of brass sieves when used with zinc-chloride.
Therefore, commonwealth Edison has concluded that discoloration is an expected condition and not a defect.
- 2. The only observable discontinuity on the #100 sieve was an area which had been repaired by soldering. ASTM STP 447A " Manual on Test i Sieving Methods" establishes and allows for this type of repair by stating in part "small holes can be repaired by soldering".
l
W
- Commonwealth Edison NRC Docket Nos. 50-456/457 If the discontinuities, as discussed above, were not the.cause of the apparent noncompliance, Commonwealth Edison would appreciate a prompt disclosure of their exact nature.
However, if the " defects" were as previously described,
! C'ommonwealth Edison requests that the NRC reconsider its findings since no physical requirements appear to have been violated. In addition, Commonwealth Edison is concerned that the aesthetics of the sieves in a field laboratory environment may have had an undue influence on the insoector's observations.
The discolored #50 sieve and the solder repaired #100 sieve along ;
with the two previously menti ^oned defective sieves were removed from use immediately after the inspection. However, based on the '
the above considerations, there appears to be no reason why
- 50 and #100 sieves cannot be returned to service.
The secondary portion of the apparent noncompliance 9 deals with the lack of a program for calibrating sieves to ASTM E-ll. Pittsburgh Testing Laboratory (PTL) does not include the calibration of sieves in its calibration procedures, QC-CAL-3, because no calibration of sieves is required. ASTM E-11 standard Specification for Wire-Cloth Sieves for Testing Purposes is a manufacturing standard. ASTM STP 447A, " Manual on Test Sieving Methods" , states that " ASTM Specifications E-ll specify
.certain manufacturing tolerances". Upon receipt of the sieves PTL verifies that certification to ASTM E-ll accompanies each sieve.
According to ASTM STP 447A "a test sieve should retain the accuracy of its openings throughout the lif6 of the sieve, since ordinary wear is on the top of the knuckles of the wire cloth and no measurable wear occurs in the openings".
Furthermore, ANSI N45.2, Section 13 dealing with calibration states "This requirement (for calibration) is not intended to i imply a need for special calibration and control measures on rulers, tape measures, levels and such other devices if normal cractices erovide adequate accuraev". Commonwealth Edison feels that sieves are covered by this category since ASTM E-ll requires a permanent label stating certification be affixed to the sieve by the sieve manufacturer and since the previous quote from ASTM 447A clearly implies that this is the case!
The f act that ASTM E ,ll is a manuf acturing standard is additionally reinforced by t'he following statement on sieve skirts "... the bottom of the frame or sieve skirt shall be so constructed as to have an easy sliding fit in any sieve".
The NRC Inspection Report references the aforementioned statement and continues with "The inspector observed The that none of the sieres in use are sieves being used met this requirement".
L
. Cornmonwealth Edison- PRC Docket Nos. 50-456/457-certified to be manufactured (constructed) to fit easily together, however, it is inconceivable that the slight
^
tolerance dimension of +.03 in. referenced in ASTM E-ll is
{ intended for' verification of test sieves being used in a field laboratory. The ASTM standard for " Test Sieving Methods" does not appear to be concerned with the fit of the sieve skirts as it does not even deign to mention this fact when describing the j effects of wear on the accuracy of the sieves.
At the time of the inspection, ASTM.STP 447A " Manual on Test Sieving Methods" was not used as a basis for the NRC inspector's determination. By various ASTM standards (C-136, 134, etc.) Commonwealth Edison is required to use sieves manufactured in accordance with ASTM E-ll which states " Complete instructions and procedures on the use of test sieves are con- ,
tained in ASTM STP 447". ASTM STP 447 in turn refers to E-ll to "specify certain manufacturers tolerances". Commonwealth Edison is concerned that the requirements applicable to manuf acturing and manuf acturer's responsibilities were in-correctly imposed on sieves being used in its field testing laboratories. Therefore, based on this additional information which identifies a more appropriate baseline for interpretation of the inspector's field observations, Commonwealth Edison requests that the NRC reexamine this apparent item of ,
noncompliance and consider changing this infraction to an observation.
ITEM A.2 Contrary to 10 CFR 50, Appendix B, Criterion XIII, and the Commonwealth Edison QA Manual Quality Requirement QR-13 which requires cleaning and preservation of materials in accordance with work and insp'ection procedures to prevent damage and deterioration, on June 13-15, 1978 the inspector determined that the Unit 1 & 2 tendon bearing plates and trumplets were not being maintained in accordance with specification L-2721, Section 2-303(d). This states, "the interior surf aces on all trumplets and funnels shall be protected from corrosion prior to tendon and greasing installation by coating and inside '
surf ace with a film of . . . the contractor shall maintain this coating orotection durina the entire course of work until tendons are in olace and arease is installed" (emphasis included in spec.) The inspector observed 162 vertical tendon -
bearing platec and trumplets in both Units 1 and 2 noted surface corrosion in every instance'. !
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' Commonwealth Edison ~NRC Docket Nos,._ 50-456/457
,.- .. 5-RESPONSE __
Commonwealth Edison disagrees with the finding that therewas surface corrosion in every instance. The inspector was informed'that the great majority of the surface rusting was actually a coating of rust particles which had been washed dow'n from the vertical sheathing. This was confirmed in the presence of the-inspector by scraping some of this rust coating off the bearing plates, revealing that the plate surface coating was still intact.
Based on this information, Commonwealth Edison. recuests that the NRC reexamine this apparent item of noncompliance and consider changing this infraction to an observa' tion. I ;
As a further measure of protection, immediately after-this inspection the coating of rust particles was removed from the vertical tendon bearing plates and trumplets in both Units 1
-and 2 and an additional protective grea'se coating was applied to minimize corrosion potential. This grease coating will be maintained on the bearing plates and trumplets with no further maintenance being conducted until just prior to the tendon installation at which time the surf aces of the bearing plates t will be. cleaned. In addition, monthly surveillances of the tendon tunnel will be performed by the contractor in order to maintian this grease coating and minimize any corrosion potential.
ITEM A.3 contrary to 10 CFR 50, Appendix B, Criterion IX; the Braidwood PSAR, Table 3.2-2, which lists ASME Section III as'the applicable code for class 1, 2 and 3 components and piping 1' systems; the S&L Specification No. L/F 2739 which specifies safety related piping shall be in accordance with ASME Section III, 1974 Edition; and subarticle NB5100, ASME Section III, which I states . in part that radiographic examination shall be :bs i accordance with ASME Section V, Article 2, the inspector observed during review of radiographs of three welds that an Iridium 192 source had been used on material less than 0.75 inches without a special procedure being' prepared and proven satisfactory by actual demonstration as required by ASME Section V.
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Commonwealth Edison tmC-Docket Nos. 50-456/457 i
RESPONSE
ASME Section V, Article 2, 1974 Edition states in
. 7' part "A special procedure shall be prepared and proved satisfactory by actual demonstration of penetrameter resolution,"
- It is Commonwealth Edison Company's interpretation that an additional "special" procedure is not intended by the code when an existing procedure produces radiographs of acceptable sensitivity. It is Commonwealth Edison's contention that the procedure is p'roven satisf actory with each radiograph shot "by actual demonstration of penetrameter resolution."
In order to clarify this position, commonwealth Edison has submitted a code inquiry to the appropriate committee of the ,
i American Society of Mechanical Engineers. A written reply is anticipated from thefcommittee by the end of October 1978.
Therefore, Commonwealth Edison Company requests that this item of apparent noncompliance be placed in abeyance until Commonwealth Edison receive,s a response on this code inquiry.
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