|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217P6171999-10-21021 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 ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 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 ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry 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 ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities 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 ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 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 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr 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 ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) 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 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl 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 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl 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 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 ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS 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) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles 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 ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also 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 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS 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 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER 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 ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed 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 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 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 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 ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram 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 ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 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 ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 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 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls 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 ML20059H5321990-09-11011 September 1990 Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers ML20059L6611990-09-10010 September 1990 Forwards Byron Station Units 1 & 2 Inservice Insp Program ML20059H4271990-09-0707 September 1990 Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831 ML20059G0941990-09-0505 September 1990 Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp ML20059C6891990-08-30030 August 1990 Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary 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 ML20056B4061990-08-21021 August 1990 Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements ML20064A0181990-08-16016 August 1990 Submits Supplemental Response to NRC Bulletin 88-008,Suppls 1 & 2.Surveillance Testing Revealed No Leakage,Therefore Charging Pump to Cold Leg Outage Injection Lines Would Not Be Subjected to Excessive Thermal Stresses ML20059A3991990-08-15015 August 1990 Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program ML20059B8961990-08-14014 August 1990 Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed ML20059D1731990-08-10010 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels ML20063Q1051990-08-10010 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2 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 ML20058N2971990-08-0606 August 1990 Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21) 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 ML20064A5491990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation ML20056A7031990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring 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 ML20055H7661990-07-24024 July 1990 Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20055H0291990-07-17017 July 1990 Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990 ML20055G3251990-07-16016 July 1990 Responds to SALP Board Repts 50-454/90-01 & 50-455/90-01 for Reporting Period Nov 1988 - Mar 1990.Effort Will Be Made to Continue High Level of Performance in Areas of Radiological Controls,Plant Operations,Emergency Preparedness & Security ML20055G2011990-07-13013 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for LaSalle County Unit 1.Outage/Reduction 16 Corrected 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 ML20044B2081990-07-11011 July 1990 Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl ML20044A9521990-07-10010 July 1990 Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage ML20055F1831990-07-0909 July 1990 Provides Status Rept on Breaker Replacements in Response to NRC Bulletin 88-010.Breaker Replacements for Plants Scheduled to Be Completed by 901031 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 ML20044B1751990-07-0909 July 1990 Responds to NRC Request for Addl Info Re Util 890726 Proposed Amend to Tech Specs to Allow Continued Operation for Period of 12 H W/Main Steam Tunnel High Ambient Temp & High Ventilation Sys Differential Trips Bypassed ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D1921990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues 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 ML20055D4811990-06-29029 June 1990 Discusses Revised Schedule for Implementation of Generic Ltr 89-04 Re Frequently Identified Weaknesses of Inservice Testing Programs.All Procedure Revs Have Either Been Approved or Drafted & in Onsite Review & Approval Process ML20055J2021990-06-26026 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-06 & 50-374/90-06.Corrective Actions:Perimeter Zone Repairs Commenced on Schedule & Completely Functional & Out of Compensatory Measures on 900614 ML20055D2951990-06-22022 June 1990 Discusses Results of 900529-0607 Requalification Exam.Based on Results of Exam,Station Removed/Prohibited Both Shift & Staff Teams & JPM Failure from License Duties.Shift Team Placed in Remediation Program from 900611-14 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 ML20044A5071990-06-22022 June 1990 Forwards Revised Response to Station Blackout Rule for Plant.During Blackout Event,Plant Can Utilize RCIC Sys or HPCS to Provide Required Reactor Vessel Inventory Makeup 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 ML20043E8651990-06-0707 June 1990 Forwards Relief Request RV-57 for Emergency Fuel Pool Makeup Crosstive Vent Valve 1(2)E12-F097.Expedious Review of Request Requested Because Valve 1(2)E12-F097 Inoperable & Will Remain So Until NRC Approval Received ML20043D3221990-06-0101 June 1990 Forwards Rev 33 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043D3151990-06-0101 June 1990 Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043D3141990-06-0101 June 1990 Forwards Rev 18 to Security Plan.Rev Withheld (Ref 10CFR73.21) 1990-09-07
[Table view] |
Text
e L- . .\ id n
, f 's Commonwealth Edison '
J ~ *
/ ) ona First National Plaza. Chicego, Illinois
\a!)
,, b( 'l Address Reply to: Post Office Box 767 I
pN \ / Chicago. Illinois 60690 4 "'p Y Q N' _
May 11, 1983 jm Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation jf U.S. Nuclear Regulatory Commission %
Washington, DC 20555
Dear Mr. Denton:
In view of the concerns involving design control at other plants, Commonwealth Edison has conducted a detailed review of the procedures and practices used in the control of design and construction of its Byron Station. The principal managers responsible for Byron's design and quality assurance have reviewed the work done on the project with senior project management and their staffs to verify that proper design control practices were utilized. This review has reinforced our confidence that Byron Station has been designed and constructed with adequate controls and can be operated safely. This letter will document the completion of this review and highlight the important findings.
Statements of these managers which summarize this review are enclosed.
Summary Commonwealth Edison has extensive experience in nuclear power plant design, construction and operation. Additionally, the Company has employed an architect-engineer with extensive nuclear power plant design experience. Edison has a strong corporate commitment to quality assurance and the auditing of the Byron Project has been extensive, including detailed technical audits of the architect-engineer and the NSSS vendor.
Several major recent evaluations, including an Independent Design l Verification of the LaSalle County station and an INPO self-evaluation of Byron Station, have shown that Commonwealth Edison and its principal contractors effectively control the overall design process and construc-tion activities of our nuclear stations. Edison's Department of Nuclear Safety is performing an independent design review of several critical safety-related areas in order to verify the design assures the protection of the health and safety of the public.
Byron is now almost entirely constructed. The operating licensing hearings are nearly complete; a decision from the licensing board and fuel loading is projected within six months. The NRC, testifying at Byron's operating licensing hearings stated that it had found Byron's quality assurance program provided a reasonable assurance that the plant would operate without undue risk to public health and safety. It characterized Edison as a capable utility, willing to institute corrective action for any deficiencies which may occur.
he o
t 9_5 t . .. -- - - - - - -
Byron's inspection history by the NRC bears out these observa-tions. Never, in Byron's entire history, has it received a civil fine for any reason. During the past year, it has undergone extensive scrutiny by the NRC. In 1982 alone, 2,547 NRC inspector hours were spent at the site. This includes a special Construction Assessment Inspection which evaluated Edison's quality assurance program, compliance history, corrective action system, design control, material traceability, electrical work activities, in process inspections, weld rod control and quality control inspector effectiveness. The inspection team found Edison's quality assurance program at Byron to be effective. Although several deficiencies were identified, they were deemed isolated occurrences, most "of minor significance", the rest "not of major concern at all".
Finally, an extensive two-week design audit by I&E Region IV is already in progress at the architect-engineer's office, and we expect that it will provide additional assurance that proper design controls are in place for the Byron project.
Highlights of Review The following paragraphs highlight some of the significant features of the design control practices utilized on Byron Station which support our confidence in the project.
- 1. Commonwealth Edison Company has conducted an INPO self-initiated evaluation of the Byron Station A special intensive evaluation of the Byron project was performed in late October, 1982. The basis for the evaluation was the Institute of Nuclear Power Operations performance objectives and criteria. Commonwealth Edison Quality Assurance coordinated the self-initiated evaluation which was carried by a twenty man team. The team consisted of senior management personnel with broad backgrounds in construction, engineering, and operation along with five consultants.
The team looked, in depth, at the plant facilities, work under construc-tion, construction practices, design input, design output, and design review. The Byron project was found to measure up well against the INPO criteria. Corrective action for the deficiencies identified by the team was promptly undertaken. It is felt that this industry evaluation adds considerable creditability to the view that the Byron Station facilities are adequately designed and constructed and are of good quality.
- 2. Commonwealth Edison's Nuclear Safety Department is conducting an independent design review of Byron Station's critical areas The Director of Edison's Department of Nuclear Safety has established an independent team of experienced engineers from within his department to perform a design review of the Byron project. This team is supplemented by personnel from other departments in specific areas for i
o examinations in depth where necessary. Members of the review team have extensive experience and expertise in station operations, plant engineering, mechanical systems, nuclear engineering, instrumentation and controls, and electrical design. A similar design review was performed for the Director of Nuclear Safety on LaSalle County Station. The results of the LaSalle review were presented as an attachment to Mr.
Cordell Reed's January 4, 1982 letter to Harold Denton regarding design control practices utilized on the LaSalle County Station.
The Byron review is designed to examine the breadth of work done by the design agents to assure the availability of emergency power, the ultimate heat sink, and the ability to deliver water to the reactor when needed. The review will be completed prior to the Unit 1 fuel load. The topics selected for review are those in the critical safety-related areas.
The review is being performed under the direction of members of the Nuclear Safety Department. A separate scope of review has been prepared for each area of the design review. The review is examining design criteria, FSAR equipment descriptions, pre-operational and startup procedures, operating procedures, Zion modifications, industry event reports and similar documents, and the installed equipment at Byron.
From this review and examination, a list of questions is being developed for discussion with the station, engineering, Sargent & Lundy and Westinghouse. A list of recommendations and observations will be developed from any items which can not be resolved.
The review is being focused on the ability to remove heat from the core during both cooldown and emergency conditions. Examples of items being evaluated include:
Ultimate heat sink Refueling water storage tank Essential service water (including ultimate heat sink)
High pressure safety injection Auxiliary feedwater Charging System Residual heat removal system Power supplies to selected instrumentation Cable loading to the major ECCS pumps Control power for automatic throwaver The Byron design review has been in progress since March, 1983, and is expected to be completed in July, 1983. If any significant items of concern are found they will be brought to Project Management immediately to obtain resolution. A report will be issued upon conclusion of the design review summari;ing any recommendations.
~
o
- 3. Commonwealth nas recently had an Independent Design Verification review conducted at our LaSalle County Station A limited independent design review for LaSalle County Station was conducted in 1982 by Teledyne Engineering Services. This review verified that adequate controls and documentation were in place to demonstrate that the system reviewed was constructed in accordance with approved design documents, procedures, and FSAR commitments. The NRC determined from their review of the IDVP that Commonwealth Edison and its principal contractors "did effectively control the overall program and construction activities"; and that "the interdisciplinary review and interface control, including the internal and external transmittal distribution and use of design data among and within all interfacing organizations" was adequate. Since the same controls are in place for Byron Station as for LaSalle Station, we believe it is reasonable to assume that an independent third party review on Byron would reach a similar conclusion. Such a review would only result in the expenditure of substantial time, money, and personnel resources by Commonwealth Edisen while reaching the aforementioned conclusion that the design control process is adequate.
- 4. Commonwealth Edison is directly involved in the design control process.
Commonwealth Edison's Engineering Department, working with the architect-engineer, nuclear steam supply vendor and other vendors, actually reviews the overall design and the implementation of the plant design to assure that the plant can function adequately and safely.
Edison directly controls the issuance of the specifications, release of many design documents, and purchase of all major equipment for the plant. This involvement by Edison in design control has been an integral part of the construction of the Company's other nuclear plants, such as Zion and LaSalle, and even of our fossil-fired generating plants. (See attachments for more details.)
- 5. Commonwealth Edison has an experienced Engineering Project Group.
Edison's Engineering Project Group is staffed with eighteen engineers, many of whom nave more than ten years of nuclear experience at Commonwealth Edison. The Byron Project Engineering Manager has over 31 years of power plant experience at Edison which includes over 16 years as Project Engineer for the Zion Project and as Project Engineering Manager for the Byron and Braidwood Projects. The Byron Project Engineer has nine years of nuclear experience at Edison, over 8 of which were as Project Engineer on Byron. He also has over 14 years of non-Edison nuclear experience. Four nther engineers in the Project Group have worked in the project group from five to ten years. (See attachments for
%re details.)
l
- 6. Commonwealth Edison's Engineering Project Group has received ASME certification for adequate design control.
It is significant that Edison was one of the first utilities to obtain the ASME Code Stamp (N-Stamp) which is the certification by the American Society of Mechanical Engineers (ASME) that an engineering organization has adequate design control to perform engineering, purchasing and construction of a nuclear power plant in accordance with ASME's standards. This certification was first obtained in 1974 for the Engineering Department and includes the Byron /Braidwood Projects as well as the Dresden/ Quad Cities, Zion, and LaSalle County Projects.
Additional audits by ASME, conducted in 1977 and 1980 in connection with the renewal of the certification, have covered all phases of work done by the Engineering Department. The certification has been awarded on the basis of the strong quality assurance (QA) program followed by the Engineering Department and the detailed engineering procedures which expand upon the corporate QA procedures. The engineering procedures discuss in depth how our design review process is implemented and contain interface procedures and memorandums of understanding between our various engineering departments. Thirty-nine technical and quality procedures cover specific steps in the design review process such as: review of NSSS documents; review of balance-of-plant items; review of specifications; field change requests; and non-conformance reports. (See attachments for more details.)
- 7. Commonwealth Edison's Quality Assurance organization is completely independent of Engineering, Construction, and Operations Commonwealth Edison has a strong commitment to quality assurance. The Quality Assurance organization is completely independent of the Engineering, Construction and Operating organizations with freedom to identify quality problems and it reports directly to senior management.
Since 1973, the Quality Assurance organization has been headed by a senior manager who currently has 35 years of experience with Commonwealth Edison in engineering and construction. He reports to the Vice Chairman of the Company, who does not have responsibility for engineering, construction or operations.
At the Byron construction site the Edison Quality Assurance organization functions under the direction of the Site QA Superintendent independently of the construction site organization. The Site QA Superintendent reports off-site to the Director of Quality Assurance (Engineering and Construction) who reports in turn to the Manager of Quality Assurance. The Byron Quality Assurance organization has expanded over the years to keep pace with the construction and station pre-opera-tional activities, and currently consists of about twenty-seven qualified people augmented with an Independent Testing Agency contractor.
O o
The Independent Testing Agency contractor, with a workforce of about fifty qualified inspector-type technicians, performs normal independent inspections, tests and examinations of contractor work at Byron under the direct control of Edison's Site Quality Assurance Group.
Site Quality Assurance also uses the Independent Testing Agency to perform special inspections as deemed prudent or necessary to check work performed and inspected by contractors.
- 8. The Manager of Quality Assurance has and exercises stop-work authority The Manager of Quality Assurance has responsibility and authority to stop unsatisfactory work or to stop further processing of unsatisfactory materials during design and construction of nuclear plants such as Byron. Quality Assurance personnel are required to promptly report conditions adverse to quality which need immediate action but which cannot be resolved at the respective locations to the Manager of Quality Assurance or his designated alternate for action. There have been nine cases of stop-work by the Manager of Quality Assurance at Byron ranging from a very short time to many weeks. The extended stop-work cases involve, for the most part, welding, inspection and/or procedure problems. (See attachments for more details).
- 9. Commonwealth Edison's Quality Assurance auditing has been extensive The auditing by the Quality Assurance organization of the Byron Project has been extensive. Since the start of construction, the Site Quality Assurance Group has performed over 410 audits of site construction and design activities which identified about 1,250 deficiencies which for the most part have been corrected.
In addition to the audits, Edison's Site Quality Assurance Group performs regular surveillances of construction activities and, as
, previously stated, uses an Indpendent Testing Agency Contractor to perform inspections, tests and examinations of contractor work.
i Surveillances are less formal than audits in that they are not conducted
, to approved checklists but rather involve checking to ensure adherence to some specific documented requirement such as procedures, specifications, i drawings or standards. Surveillances, which are documented, are l performed frequently between audits to assure that construction and other i
activities continue to be correctly performed. Surveillances cover the same types of activities and items as those involved in audits. An item found deficient in a surveillance must be corrected in a timely manner or
, it will be elevated to an audit citation. To date, in excess of 4,100
~
documented surveillances have been performed at the Byron Project, and Quality Assurance is currently performing such surveillances at the rate j of about 800 a year.
- 10. Detailed technical audits have been performed on the architect-engineers and NSSS vendor 4
Audits of the architect-engineer's and NSSS vendor's design activities are given special attention by Edison Corporate Quality Assurance management. All such audits are conducted under the immediate direction of either the Manager of Quality Assur8nce or the Director of Quality Assurance for Engineering and Construction. These audits cover all aspects of the quality assurance program and in many cases go into considerable depth in specialized design areas and into subtier design activities.
Audits of the architect-engineers were performed by independent consultants and by senior Edison engineering people who have design
, experience. When it was deemed necessary to augment the Edison audit teams, technically capable independent design personnel with technical expertise in a particular design activity were assigned to the audit team as consultants. In addition to the basic quality assurance requirements, the scope of the design audits covered such items as: (1) technical review and evaluation of calculations; (2) performance of work; (3) computer program validation and usage; (4) design analysis; (5) controlling and processing design changes; (6) stress analysis; (7) design support activities by other design organizations; (8) competency (9) incorporation of verification design of design criteria and design and engineering documents; (personnel;
- 10) design interface and data j control with other design organizations; (11) technical aspects of j electrical, mechanical and structural design including instrumentation and controls; (12) design of supports, hangers, snubbers and restraints including application of loadings; (13) seismic and environmental qualification requirements; (14) effectiveness of design control and design review including data verification; and (15) overall design i review. (See attachments for a more detailed explanation of the audit coverages by Commonwealth Edison and the independent Consultant organizations).
Forty-five audits have been performed of the architect-engineer, site architect engineering organizations and the NSSS vendor. 233 deficiencies were found which for the most part have been corrected (See attachments for more detail.)
- 11. Independent checks are made of Edison's Quality Assurance activities Another Icyer of quality assurance audits is performed by the corporate Quality Assurance staff on all Byron site activities including Edison's construction department, all site contractors and the site Quality Assurance organization activities. At least two audits have been conducted each year since 1975. 217 deficiencies have been identifed and essentially all are closed. (See attachments for more details.)
I I
l Finally, a periodic management audit is performed on the entire scope of Edison's quality assurance activities by an outside consultant.
This consultant's report assesses the strengths and weaknesses of ;
Edison's quality assurance activities and is sent to the Vice Chairman of the Company. The management audits, of which four have been conducted since 1975 (the last three involving the Byron Site), gives us additional confidence that our corporate quality assurance activities are effective. The latest audit, which included a review of quality assurance as it relates to the Byron Project, concluded:
The Commonwealth Edison Quality Assurance Program is overall the most complete and comprehensive program [the consultant] has seen in the industry.
(See attachments for more details)
- 12. Commonwealth Edison has employed an architect-engineer with extensive nuclear power plant design experience for the Byron Project.
Sargent & Lundy was employed as the architect-engineer for the Byron Project prior to the award of the NSSS contract. Sargent & Lundy has extensive experience in design of nuclear power plants, including the design of Edison's Dresden, Quad Cities, Zion, and LaSalle County nuclear power plants. The lead engineers assigned to the Byron Project average 11 years of nuclear power plant design experience.
- 13. Commonwealth Edison has exercised complete control over all design ggtivities for balance-of-plant.
Organizations outside Sargent & Lundy were, and are being, utilized for various tasks associated with the piping analysis and support design on the Byron Project. These organizations are basically of two types: (a) technical and professional service contractors and (b) vendors. Technical and professional service contractors work directly for and at the specific direction of either Edison or Sargent & Lundy.
Vendors provide their services to Edison with Sargent & Lundy acting as Edison's agent under the technical guidance outlined in specifications prepared by Sargent & Lundy.
The magnitude and scheduling of the piping analysis and support design work was such that Sargent & Lundy employed an outside consultant, Nuclear Power Services Corporation (NPS) to perform a portion of this design work. NPS was provided with all the documentation and control procedures that Sargent & Lundy used, in addition to a detailed design specification for the work. All design procedures and manuals prepared by NPS were reviewed by Sargent & Lundy for acceptability and consistency.
Technical and quality assurance audits were conducted by Sargent & Lundy, Edison and NPS. Frequent trips were made to the NPS offices for the purpose of resolving technical issues, assuring consistency and
e' monitoring status. The technical basis of the work performed by NPS is identical to that of Sargent & Lundy. (See attachments for more details.) Also, Edison has employed Westinghouse for the piping analyses and support design primarily for the piping in the containment. The scope of responsibility and actual working interfaces have been carefully controlled by Edison. Westinghouse has moved an analytical staff and computer / computer graphic facilities to the Byron site. They employ actual, current physical data from walk downs as input to their analyses and coordinate closely with on-site Sargent & Lundy and Edison engineers in their work.
Conclusion In view of the above, the Company believes that the Byron Station has been designed and constructed in a way that will assure it meets the requirements of the Final Safety Analysis Report (FSAR) and the Safety Evaluation Report (SER) (NUREG-0876 and its supplements).
Very truly yours, 4
av YSbh Cordell Reed Vice-President Nuclear Operations cc: J. G. Keppler R. DeYoung l
1 6434N 1
l l
l l
1 . . . _ _ _ _ __. . _.. _ __ _ __ _ _ . _ . . _ _ _ . _ . _ _ _ - , _ _ _ _ _ .
.4 i'
LIST OF ATTACHMENTS
- 1. Memorandum from J. D. Deress, Project Engineering Manager, to Cordell Reed, dated April 28, 1983, with Exhibits 1 through 3.
- 2. Statement of W. J. Shewski, Manager of Quality Assurance, dated April 19, 1983, with Exhibits A through P.
- 3. " Report on the INPO Self-Initiated Evaluation for Byron and Braidwood Nuclear Station Construction Projects," November 17, 1982.
- 4. " Design Evaluation Report of Sargent & Lundy for Commonwealth Edison Company," Energency Incorporated, April 4, 1983.
- 5. " System Design Review Report," Sargent & Lundy, July 16, 1980.
6434N