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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 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 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 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 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 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 ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 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 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 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) 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 ML17191B3951999-07-15015 July 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4) 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 ML17191B3941999-07-0909 July 1999 Ack Receipt of Rev 7L to Portions of Emergency Plan in Oct 1998.No NRC Approval Required Based on Determinations That Rev 7L Does Not Decrease Effectiveness of Emergency Plan 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 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 ML17191B3821999-06-17017 June 1999 Discusses 990521 Meeting in Downers Grove,Il.Purpose of Visit to Meet Risk Mgt Staff Collectively Prior to Visiting Each Plant.Forwards Attendance List & Licensee Presentation 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-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 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 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 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 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-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 ML20206E4201999-04-29029 April 1999 Forwards 1998 Radioactive Effluent Release Rept. Rept Submitted IAW 10CFR50.36a & TS 5.6.3, Radioactive Effluent Release Rept & Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Jan-Dec 1998 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 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 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 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 ML17191B2671999-03-12012 March 1999 Forwards Revs to Dresden,Quad Cities,Zion,Lasalle,Byron & Braidwood Station Odcm,Current as of 981231.ODCM Manual & Summary of Changes,Included ML20207J4321999-03-0808 March 1999 Forwards Braidwood Station ISI Outage Rept for A1R07, Per Requirements of ASME Section Xi,Article IWA-6200 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 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 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 ML20059B7551990-08-24024 August 1990 Forwards Braidwood Nuclear Station Unit 2 Inservice Insp Summary Rept,Interval 1,Period 1,Outage 1 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 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 ML20034B6901990-04-12012 April 1990 Forwards Rev 58 to CE-1-A, QA Program for Nuclear Generating Stations. Rev Being Made to Reflect Correct Frequency of Cumulative Deviation Reporting & to Clarify Applicability of Other ANSI N45.2 Stds ML20042F0241990-03-28028 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML20012D8671990-03-21021 March 1990 Reissued ,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date ML20042G4641990-03-20020 March 1990 Responds to NRC 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. ML20033E8261990-02-27027 February 1990 Provides Info Re High Density Fuel Storage Rack Blackness Testing for NRC Review & Acceptance & Advises That Schedule to Perform Blackness Testing within 2 Yrs of Placing Racks in Svc Reflects Relevant Testing Schedule on Boraflex 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 ML20006C0431990-01-29029 January 1990 Forwards Response to NRC Bulletin 89-003.Util Nuclear Fuels Dept Designs or Reviews & Approves Each Core Reload for Plants & Refueling Operations Recently Reviewed to Ensure Appropriate Procedural Controls in Place 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 1990-09-17
[Table view] |
Text
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j Commonwealth Edison 1 One First National Plan. Chic;go. Hhnois j-Address Reply to. Post Office Box 767 g4 Chicago, Illinois 60690 April 9, 1984 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Braidwood Station Units 1 and 2 s
Response to IE Inspection Report 50-456/83-17 and 50-457/83-16 NRC Docket Nos. 50-456/457 References (a):
R. C. Knop letter to Cordell Reed dated February 3, 1984 (b):
E. D. Swartz letter to J. G. Keppler dated February 28, 1984
Dear Mr. Keppler:
Reference (a) provided the Commonwealth Edison Company with the results of an inspection conducted by Mr. L. G. McGregor of your of fice during the period of October 3 through December 16, 1983, of activities at our Braidwood Station.
During that inspection, certain activities appeared to be in non-compliance with NRC requirements.
The Attachment to this letter provides the Commonwealth Edison Company response to the Notice of Violation as appended to Reference (a).
Our delay in submittal of this thirty day response was discussed cith Messrs. R. C. Knop and D. W. Hayes of your office on separate occasions, and we appreciate having been given additional time to respond in this matter.
Our response to the item of non-compliance addresses each of the six examples cited in Reference (a).
Our review of each of the Region's concerns did not reveal any adverse impact on the safety-related battery installations at Braidwood Station.
Additionally, as requested in Reference (a), Reference (b) provided the Commonwealth Edison Company response to the woven wire fence issue for both Byron and Braidwood Stations.
It is our belief that cxisting designs adequately address ventilation, hydrogen control, and fire protection requirements as accepted by NRR.
0405290171 840522 PDR ADOCK 05000456 0
PDH
.a J. G. Keppler 2-April 9, 1984 Please address any questions that you or your staff may have concerning this matter to this office.
Very truly yours,
- ::_mp Dennis L. Farrar Director of Nuclear Licensing EOS/lm Attachment cc:
RIII Inspector - Braidwood
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JATTACHMENT 4
COMMONWEALTH EDISON COMPANY RESPONSE TO NOTICE OF VIOLATION i
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VIOLATION i
10 CFR 50, Appendix B, Criterion II requires holders of construction 4
permits for nuclear power plants to document by. written. policies, procedures, or instructions, a quality assurance program which complies j
with the requirements of. Appendix B for all activities affecting the quality of safety-related structures, ith those documents. systems, and components and to i
implement that program in accordance w l'
I Contrary to the above, Commonwealth Edison Company did not adequately document and implement a quality a?surance program to comply with the i
requirements of Appendix 8 as evidenced by the following examples:
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EXAMPLE 1 i
10 CFR 50, Appendix B, Criterion.V requires in part:
" Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the. circumstances, and j
shall be accomplished in accordance.with these instructions, procedures or drawings."
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Commonwealth Edison Company.(CECO) Quality Assurance Manual,-Quality 1
Requirement No. 5.0 (QR 5.0) states in part:
"The quality assurance actions carried out for design, construction, testing'and operation i
activities will be described in documented. instructions, procedures, i
drawings, specifications, or checklists...".
The CECO Quality Assurance Manual, Quality Procedure No. 5-1 (QP-5.1) implements'this requirement.-
1 l
Contrary to the above, Station approved-procedures for the installation, maintenance and surveillance of the station safety related battery banks (No.'s 111, 112,.211 and 212) did not exist.until October.1981, when Station Procedure BWOS-PC-02 was approved.
This procedure was not implemented until January 1982, however the station batteries were
,i
" turned.over" to the Stations Operations Department"on May 14, 1981.-
i Further,.no maintenance or surveillance procedures.were' developed by the t
' installation contractor,;L.!K.'Comstock.
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Procedures for battery maintenance and surveillance were indeterminate i
until March 17, 1983 when an internel memorandum was written to L. K.
I Comstock Qual'ity. Assurance Department stating:
"The following battery
. groups are under the direction of OAD" (Operational Analysis' Department, a CECO Electrical Construction-test lsection), "and have been relieved from L. K. Comstock Quality. Control maintenance inspection since the j
associated dates, Battery 111, 112,-211 and 212 sinceLDecember, 1979."=
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. RESPONSE TO EXAMPLE 1 The Commonwealth Edison Company agrees that inconsistencies existed in the station development, approval, and implementation dates for procedures concerning the safety-related battery banks.
While instal-lation procedures existed and were used, maintenance and surveillance procedures were not organized and approved in a systematic manner.
However, it should be noted that certain maintenance and surveillance activities were performed, and that no actual hardware problems were identified in the field as a result of the inconsistencies.
Battery installation was the responsibility of the L. K. Comstock Company, and they developed installation procedures in accordance with the manufacturer's approved drawings (DC Storage Battery and Battery Installation, Procedure 4.3.4).
These procedures were reviewed and approved by the Commonwealth Edison Company and were used by L. K.
Comstock to install and verify the battery banks.
Since 1979 when the batteries first arrived on site, the Commonwealth Edison Company Operational Analysis Department had responsibility for the battery maintenance and surveillance.
These activities, performed in the field by L. K.
Comstock electricians under the direction of OAD, were accomplished pursuant to OAD Procedure No. 9 (Electric Construction Test Procedure DC Battery and Battery Charger).
As noted in our discussion of other Examples cited under this violation, this procedure was not always followed in a consistent manner.
However, OAD documentation exists to demonstrate that the procedure was employed.
As such, it was not the L. K.
Comstock responsibility to develop maintenance and surveillance procedures.
In addition to our Operational Analysis Department maintenance and surveillance inspections, the Commonwealth Edison Company Station Operating Department and the battery manufacturer (Gould Incorporated) performed maintenance and surveillance inspections.
Station Operating began battery inspections as carly as August 1981, even though the station procedure was not yet approved.
As early as October 1979, a representative from Gould Incorporated performed inspections on the batteries.
A recent inspection report from Gould Incorporated states, in part, that the battery cells are in good l
condition.
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED, AND CORRECTIVE ACTIONS TAKEN TO AVOID FURTHER NONCOMPLIANCE The Commonwealth Edison Company Project Construction Department has turned all safety related battery banks over to Station Operating for maintenance and surveillance activities.
Station Procedure BWOS-PC-02 was approved in October 1981, and is currently in effect to provide direction when performing battery maintenance.
Assurance of procedure implementation will be documented on an ongoing basis through audits and surveillances performed by Station Quality Assurance.
DATE OF FULL COMPLIANCE Full compliance has been achieved.
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EXAMPLE 2 j
"A program for i
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10.CFR 50, Appendix B, Criterion X requires in part:
F inspection of activities affecting quality shall be established and
.oxecuted by or for the organization. performing the activities to verify conformance-with the documented instructions, procedures, and drawings for accomplishing the activity."
The Commonwealth Edison Company Quality Assurance Manual, QR No. 10.0, paragraph 10.2 states.in part:
" Inspection and test plans shall be prepared'by respective contractors, vendors or organizations having responsibility for the. item (s) involved, either as a separate docu.nent identified ~with the parts', components or assemblies; or as an integral j
part of work instruction and procedure' documents.. Inspection and test plans shall consist of a flow chart, diagram or narrative description of the sequence of procurement, fabrication, processing, assembly, inspection and test activities and shall specify the inspection points.
l The inspection and test plan shall provide testing requirements, the i
characteristic to be measured, the inspection and test procedure and the applicable acceptance criteria."
.The Commonwealth Edison Company Quality Assurance Manual, QP 10-1 implements this requirement.
l Contrary to the above, a battery inspection program was not develured to j
verify the proper surveillance and installation of the battery banks.
No records exist indicating that process sheets or other documentation were i
used or reviewed by Commonwealth Edison Company Quality Assurance or the contractors quality control department during the movement, surveillance, l
maintenance and installation of the safety-related battery banks for Units 1 and 2.
However, OAD did perform monthly and quarterly surveil -
I j_
lance on the batteries during'the period of December, 1979 through May.14, j
1982.
The procedure used during this period, Surveillance. Procedure 4.0, l
was not approved by Site Quality Assurance.
Further.the procedure was not adequate to perform the surveillance and requirements, as stated by j
the bettery manufacturer.
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h RESPONSE TO EXAMPLE ' 2 j
Commonwealth Edison had established a program for the. installation snd surveillance of battery banks but:as.the Example points out, the 4
^
program did not at~all times adequately record all the aspects of j
battery surveillance.
As the discussion in our response to Example 1 indicates, there was i
an approved installation procedure pursuant to which the batteries i
'were installed. 'This L. K.'Comstock-installation Procedure 4.3.4 was supplemented'by a variety'of approved construction procedures involving'among other things, welding, concrete expansion anchor
' installation, and the use of calibrated: wrenches.
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-4 The surveillance program was accomplished pursuant to Operational Analysis Department Procedure No. 9 (Section 4.0 of which relates to surveillance procedures).
Because this is an OAD procedure, under Company practice it had to be approved by Commonwealth Edison Corporate Quality Assurance, and in fact was.
Braidwood Site Quality Assurance does not have the responsibility for review and approval of OAD procedures.
Commonwealth Edison believes that all the activities necessary to ascertain that the batteries would properly function were performed.
However, Commonwealth Edison acknowledges thet the procedure was inadequate in that it did not require the recording of certain information as recommended by the battery manufacturer.
Documentation exists for the installation, surveillance and maintenance activities performed with regard to the battery banks.
Commonwealth Edison agrees that the movement of the battery banks was not documented.
However, the movement was witnessed and accomplished pursuant to L. K. Comstock Procedure 4.10.1.
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED, AND CORRECTIVE ACTIONS TAKEN TO AVOID FURTHER NONCOMPLIANCE The Commonwealth Edison Company Project Construction Department has turned all safety related battery banks over to Station Operating for maintenance and surveillance activities.
Station Procedure BWOS-PC-02 was approved in October 1981 and is currently in effect to provide direction when performing battery maintenance.
Assurance of procedure implementation will be documented on an ongoing basir through audits and surveillances performed by Station Quality Assurance.
DATE OF FULL COMPLIANCE Full compliance has been achieved.
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, EXAMPLE 3 10 CFR 50, Appendix B, Criterion XIII requires in part:
" Measures shall be established to control the handling, storage, shipping, cleaning and preservation of material and equipment in accordance with work and inspection instructions to prevent damage or deterioration."
Commonwealth Edison Company Quality Assurance Manual, QR No. 13-1, paragraph 4.2 states in part:
"On-site contractors will perform the caterial and equipment unloading based on approved procedures (Ref. QP 5-1) or instructions.
On-site contractors are required to provide approved facilities, handling equipment, procedures and personnel to receive, store, inspect, document and control the material and equipment chen it arrives on site.
On-site contractor procedures shall provide:
a.
Methods for identifying and marking material and equipment.
b.
Control of records and documentation.
c.
Type of storage provided, d.
Maintenance or adherence to manufacturer's special instructions for equipment in storage or equipment stored in place.
e.
Controls to assure that material is used only as specified or intended.
f.
Periodic inspections and surveillance for stored equipment.
Contrary to the above, a program for handling, storage, cleaning and preservation of safety-related station battery banks in accordance with inspection instructions, procedures, maintenance and surveillance requirements was not established or implemented.
RESPONSE TO EXAMPLE 3 As acknowledged in our response to Example 2, the Commonwealth Edison Company program for the surveillance and maintenance of the batteries did not completely address all the measures necessary for the maintenance of the betteries, although Commonwealth Edison does believe that the program for handling and storage was adequate under its procedures.
L. K. Comstock was the on-site contractor responsible for the handling (movement) and the storage (receipt) of the batteries and approved procedures (L. K. Comstock Procedures A.10.1 and 4.10.2) were developed to control these activities.
Batteries were received in accordance with the requirements of Commonwealth Edison Company Quality Assurance Manual Q.P. No. 7-1, and a check for shipping damage was performed.
. l The results of this check were documented on Commonwealth Edison l
Company MRR Numbers 5281 and 5285.
L. K. Comstock Procedure 4.10.2 (Receiving and Storage) Paragraphs 3.1.2 and 3 1.3 describe their responsibilities with respect to Receipt Inspections.
In addition to the L.K. Comstock Procedure 4.10.2, the Commonwealth Edison Company Project Construction Department Procedure BG-3 (Receipt and Inspection) describes a program to assure items (a) through (f) listed in the Example are provided for.
The Commonwealth Edison Company Operational Analysis Department had
~
responsibility for the maintenance (storage and cleaning) activities.
These Operational Analysis Department activities were directed by their Electrical Construction Test Procedure No. 9.
Upon battery receipt, it was determined that certain manufacturer's recommendations were to be monitored.
The following are examples of I
these considerations which were included. in the procedure:
Manufacturer recommends:
Indoor storage, in a cool (600F - 900F) clean, dry location.
Commonwealth Edison Company provided:
1 1
Storage in an unused electrical switching building that is provided with heat and ventilation.
Manufacturer recommends:
An initial charge within six (6) months of the date of shipment; repeat this charge once every six (6) months.
Commonwealth Edison Company provided:
An initial charge ninety (90) days after delivery; I
connection to a-constant voltage charger; monthly surveillances of pilot cell voltage and specific gravity; battery terminal cleaning per manufacturer recommendations.
However, as noted in our response to Example 2, the surveillance measures were inadequate in that they did not provide for the recording of the amount of water added to the pilot cell l'n accordance with the manufacturer's recommendations.
Performance testing has shown that no adverse effects have resulted.
. i CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED, AND CORRECTIVE ACTION TAKEN TO AVOID FURTHER NONCOMPLIANCE-The Commonwealth _ Edison Company Project Construction Department has turned all safety related battery banks over to Station Operating for maintenance and surveillance activities.
Station Procedure BWOS-PC-02 was approved in October 1981, and is currently in effect to provide direction when performing battery maintenance.
Assurance of procedure implementation will be documented on an ongoing basis through audits and surveillances performed by Station Quality i
Assurance.
DATE OF FULL COMPLIANCE Full compliance has been achieved.
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EXAMPLE 4-
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10 CFR 50, Appendix B, Criterion XV requires.in part:
" Measures shall be established to control materials, parts or components which do not
- conform to requirements in order to prevent their inadvertent use or installation.
These measures shall include, as appropriate, procedures for identification, documentation, segregation, disposition, and notification to affected organizations."
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The CECO Quality Assurance Manual, "' No. 15.0, paragraph 15.3 states in part:
" Items which are found to be nonconforming to design and i
specification requirements or workmanship standards will be positively identified and uniquely segregated or handled as nonconforming to prevent their inadvertent use."
l Commonwealth Edison Company Quality Assurance Manual, QP No. 15-1, implements the above requirements and states in Paragraph 5.2:
"On-site contractor nonconformances will be documented in accordance with the contractor's approved Quality Assurance Program and Procedures."
l Contrary to the above requirements the Licensee did not implement the j
requirements of its Quality Assurance Program or insure the contractor had implemented a quality assurance program to control material, parts or components which do not conform to design requirements.
Non-conformance reports were not issued on at least three occasions,(November 4, 1982;
}
November 11, 1982 and December 20, 1982), when it was necessary to
-purchase replacement cells which were damaged or broken.
RESPONSE TO EXAMPLE 4 The Commonwealth F.dison Company agrees that nonconformance reports i
were not issued to document three broken cells.
When the damaged cells were discovered on November 4, 1982, November 11, 1982, and December 20, 1982, respectively, they were subsequently. replaced with good cells.
l CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED. AND CORRECTIVE ACTION i
TAKEN TO AVOID FURTHER NONCOMPLIANCE i
The Commonwealth. Edison Company Operational Analysis Department and Project Construction Department personnel were informally I
reinstructed'in the requirements of issuing Non-Conformance Reports
.when damage.is found on safety-related equipment on December 16, 1983.
I DATE OF FULL COMPLIANCE j
The Commonwealth Edison Company Project. Construction Department l
_ issued.a letter of reinstruction to Operational Analysis Department and Project Construction Department personnel on-April 6, 1984.
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EXAMPLE 5 I-I 10 CFR 50, Appendix B, Criterion XVII requires in part:
" Sufficient i
records shall be maintained to furnish evidence of activities affecting i
quality.
The records shall include at least the following:
....results of reviews, inspections, test audits, monitoring of work performances, j
end materials analysis.... Records shall be identifiable and retrievable."
1 i
Commonwealth Edison Company. Quality Assurance Manual, QR No. 17.0, j
Paragraph 17.1-states in part:
" Quality Assurance records sill ~be maintained either by Edison or'by an agent of Edison,:under Edison's control.... Records are retained and maintained in accordance with a i
j Quality ~ Procedure to furnish evidence of activities affecting quality."
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Commonwealth Edison Company Quality Assurance Manual, QR No. 10.0, I
Paragraph 10.5 states in part:
" Inspection and test records will provide objective evidence that inspections and tests were performed in 1
compliance with instructions and procedures to verify design and code j
requirements.
Inspection and test results will be recorded to show conformance sith acceptance criteria and/or record and identify the cause i
j of rejected items."
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i Contrary to the above requirement, with few exceptions, sufficient
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official records were not generated or maintained relative to the responsibility, movement, maintenance, surveillance, installation, repair
]
and cleanliness of the safety rtlated battery banks at the Braidwood site l
j by either Commonwealth Edison Company or their installation contractor.
No records exist to' establish the frequency or necessary data recorded" l
for battery surveillance during the period from May 14, 1981 until January 1, 1982.
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RESPONSE TO EXAMPLE 5 1
j The various activities involving the safety-related battery banks at i
Braidwood Station concerning responsibility, movement, maintenance,
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surveillance, installation, repair and cleanliness have been
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j discussed in the response to the other examples cited under this j
item of non-compliance.
Commonwealth Edison Company acknowledges-that.the existence, location and quality of certain-of the documen-tation of these activities varies as-to acceptability.
No battery-l surveillance records could be located from the period of May 14, 1981 to~ August, 1981.
However, records for surveillance activities i
~
both before May 14, 1981 and after August 1981 to the present are i
e available for review.
Although there were documentation-deficiencies, the-records are adequate to demonstrate that surveillance activities were performed and' inspections of the batteries'show that.they are presently functional.
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CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED, AND CORRECTIVE ACTIGNS TAKEN TO AVOID FURTHER NONCOMPLIANCE i
The Commonwealth Edison Company Project Construction Department has
- turned all safety related battery banks over to Station Operating for maintenance and surveillance activities.
Station Procedure BWOS-PC-02 was approved in October 1981, end is currently in effect to provide direction when performing battery maintenance.
Assurance of procedure implementation will be documented on an ongoing basis
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through audits and surveillances performed by Station Quality
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Assurance.
i DATE OF FULL COMPLIANCE Full compliance has been achieved.
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. EXAMPLE 6 10 CFR 50, Appendix 0, Criterion XVIII requires in part:
"A comprehensive system of planned and periodic audits shall be carried out to verify compliance with all aspects of the quality assurance program and to determine the ef fectiveness of the program.... Followup action, including re-audit of deficient areas, shall be taken where indicated."
Commonwealth Edison Company Quality Assurance Manual, QR No. 18.0, Paragraph 18.1 states in part:
" Audits will be performed by Commonwealth Edison Company and/or its contractors, subcontractors and vendors to verify the implementation and effectiveness of quality programs under their cognizance."
Paragraph 5.1 of Commonwealth Edison Company Quality Assurance Manual, QP 18-1 states in part:
" Audits of on-site contractors will be performed, as a minimum on an annual basis....The selection of contractor on-site activities to be audited and the frequency of audits will be based on site Quality Assurance and Commonwealth Edison Company Construction Surveillance Reports or findings from previous audit reports....The frequency will be based on the nature and safety significance of the work being performed."
Contrary to the above requirements only two audits were performed by Site Quality Assurance, on activities being performed by Operational Analysis Department relative to the safety related batteries.
These audits, No.
20-79-36, dated June 15, 1979 and No. 20-81-44, dated November 24, 1981 were not sufficient in depth or scope to verify the implementation or ef fectiveness of the quality program with relation to the maintenance, repair and surveillance requirements of the station safety-related battery banks, nor were the audits performed "as a minimum on an annual basis."
RESPONSE TO EXAMPLE 6 The Operational Analysis Department was added to the Site Quality Assurance audit schedule in December 1978.
The Operational Analysis Department was scheduled to be audited twice during 1979.
The first audit was performed.
However, the second audit scheduled for October was not performed due to the site shutdown.
The Site Quality Assurance audit schedule was revised in October 1979, to require monthly audits of the Commonwealth Edison Project Construction Department.
These audits examined the storage and preservation of safety related equipment independent of who was actually assigned responsibility for performing the required activities.
This practice continued until the shutdown ended.
With the exception of the disruption caused by the shutdown, the Commonwealth Edison Quality Assurance Department performed annual audits of our Operational Analysis Department in addition to surveillances to verify programmatic compliance with the Commonwealth Edison Company Quality Assurance Manual and Operational Analysis Department Electrical Construction Test Procedures.
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. Following the resumption of construction activities, auditing of the Operational Analysis Department was performed as part of the annual General Office Quality Assurance audits of the site (normally at least twice per year).
The scope of these audits was not geared to specific electrical components, but rather to verifying compliance and effectiveness of the OAD procedures and adherence to the Commonwealth Edison Company Quality Assurance Manual.
These audits were augmented by surveillances which more specifically addressed the OAD testing activities.
These included in-process inspections of OAD work.
They were scheduled for times wherein OAD would be performing the essential elements of its activities.
In addition to these scheduled surveillances, if Site Quality Assurance identified a problem with OAD's implementation of its procedures or the lack of procedures, the area would be addressed by either a special Site Quality Assurance audit or a detailed surveillance to determine the extent of the problem.
The Operational Analysis Department's compliance with the Commonwealth Edison Quality Assurance Program was evaluated by the audits discussed above.
CORRECTIVE ACTION TAKEN AND ACTION TAKEN TO AVOID FURTHER CONCERN Braidwood Site Quality Assurance has currently scheduled Commonwealth Edison Company Operational Analysis Department to be audited quarterly.
While realizing that currently there remains only one battery bank (non-safety related) for which Operational Analysis Department still has maintenance jurisdiction, Site Quality Assurance will perform surveillances of this specific maintenance activity to verify compliance with their existing procedure.
- Also, Braidwood Operating Station Quality Assurance is performing audits and surveillances of battery banks which are under station control.
A review of our inspection records indicates that the more detailed Quality Assurance surveillances and audits described above concentrated on OAD's testing, rather than maintenance activitiese Commonwealth Edison Site Quality Assurance will review records to identify any other maintenance activities OAD might have had responsibility for at the site and will evaluate these activities to determine whether OAD specific practices in the area were properly carried out.
DATE OF FULL COMPLIANCE Regular audits will be performed as scheduled.
The Site Quality Assurance review of OAD's maintenance activities will start as soon as practicable.
Region III will be provided with a schedule of any activities which will have to be conducted as a result of these reviews.
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