Similar Documents at Byron |
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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) ML20217M2871999-10-21021 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 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes 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.. 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 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 ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations 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) 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 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 ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff 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 ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick 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 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 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) 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 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) 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 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes 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.. 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 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 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 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 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 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event 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 ML20207E9831999-05-18018 May 1999 Forwards Copy of Commonwealth Edison Co EP Exercise Evaluation Objectives for 1999 Byron Station Annual EP Exercise,Which Will Be Conducted on 990825.Without Encl ML20206N8551999-05-11011 May 1999 Forwards 1998 Annual Radioactive Environ Operating Rept for Byron Station. Rept Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Site ML20206U3351999-04-30030 April 1999 Forwards Evaluation of Matter Described in Re Byron Station.Concludes That Use of Overtime at Byron Station Was Controlled IAW Administrative Requirements & Mgt Expectations Established to Meet Overtime Requirement of TS 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 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 ML20206E7521999-04-22022 April 1999 Submits Rept on Number of Tubes Plugged or Repaired During Inservice Insp Activities Conducted at Plant During Cycle 9 Refueling Outage,Per TS 5.6.9 ML20206A7431999-04-22022 April 1999 Forwards Comments Generated Based on Review of NRC Ltr Re Preliminary Accident Sequence Precursor Analysis for Byron Station,Unit 1 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 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 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 ML20206A8141999-04-20020 April 1999 Advises NRC of Review of Cycle 10 Reload Under Provisions of 10CFR50.59 & to Transmit COLR for Upcoming Cycle ML20205T3901999-04-13013 April 1999 Forwards Byron Station 1998 Occupational Radiation Exposure Rept, Which Is Tabulation of Station,Utility & Other Personnel Receiving Annual Deep Dose Equivalent of Less than 100 Mrem ML20196K6661999-03-31031 March 1999 Forwards Byron Nuclear Power Station 10CFR50.59 Summary Rept, Consisting of Descriptions & SE Summaries of Changes, Tests & Experiments.Rept Includes Changes Made to Features Fire Protection Program,Not Previously Presented to NRC 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) 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 ML20207K0351999-03-0404 March 1999 Forwards Util Which Transmitted Corrected Pages to SG Replacement Outage Startup Rept.Subject Ltr Was Inadvertently Not Sent to NRC Dcd,As Required by 10CFR50.4 ML20205C6861999-03-0404 March 1999 Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219 ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207D4301999-02-26026 February 1999 Informs NRC That Supplemental Info for Byron & Braidwood Stations Will Be Delayed.All Mod Work Described in Ltr Is on Schedule,Per GL 96-06 ML20207B8971999-02-25025 February 1999 Expresses Concern That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazard at Some Commercial Nuclear Plants in Us ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202F5911999-01-29029 January 1999 Forwards Byron Unit 1 Cycle 9 COLR in ITS Format & W(Z) Function & Byron Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function. New COLR Format Has Addl Info Requirements ML20199E1611999-01-15015 January 1999 Forwards Response to 980902 RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. CE Endorses Industry Response to RAI as Submitted by NEI ML20199B7511999-01-0808 January 1999 Forwards Proprietary Versions of Epips,Including Rev 52 to Bzp 600-A1 & Rev 48 to Bzp 600-A4 & non-proprietary Version of Rev 52 to Bzp 600-A1 & Index.Proprietary Info Withheld 1999-09-30
[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 ML20059L6611990-09-10010 September 1990 Forwards Byron Station Units 1 & 2 Inservice Insp Program 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 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 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 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 ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants 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 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 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 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 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 ML20044B2141990-07-11011 July 1990 Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification ML20044A9521990-07-10010 July 1990 Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage 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 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 ML20043D3151990-06-0101 June 1990 Forwards Rev 30 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 ML20043C8641990-05-29029 May 1990 Forwards Rept of Local Leakage Rate Test Results for Third Refueling Outage.Leakage Rates of Six Valves Identified as Contributing to Failure of Max Pathway Limit ML20043B7691990-05-23023 May 1990 Forwards Endorsement 11 to Nelia & Maelu Certificates N-93 & M-93 & Endorsement 9 to Nelia & Maelu Certificates N-101 & M-101 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 ML20043A6391990-05-11011 May 1990 Submits Revised Schedule for Implementation of Generic Ltr 89-04 Guidance.Rev to Procedures for Check Valve & Stroke Time Testing of power-operated Valves Will Be Completed by 900629 ML20043A2891990-05-10010 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for Byron Nuclear Power Station 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 ML20042G3591990-04-30030 April 1990 Forwards Errata to Radioactive Effluent Rept for Jul-Dec 1989,including Info Re Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor ML20055C5761990-04-30030 April 1990 Forwards Results of Investigation in Response to Allegation RIII-90-A-0011 Re Fitness for Duty.W/O Encl ML20042E9601990-04-30030 April 1990 Forwards Response to NRC 900327 Ltr Re Violations Noted in Insp Repts 50-454/90-09 & 50-455/90-08.Response Withheld (Ref 10CFR73.21) ML20042E9111990-04-25025 April 1990 Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. ML20012E1081990-03-21021 March 1990 Forwards Calculations Verifying Operability of Facility Dc Battery 111 W/Only 57 of 58 Cells Functional & Onsite Review Notes,Per Request ML20012D8671990-03-21021 March 1990 Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date 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 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 ML20012A4491990-02-16016 February 1990 Advises That 16 Tubes in All Four Steam Generators Removed from Svc as Result of Eddy Current Insp During Cycle 3 Refueling Outage.Tube Plugging Distribution Between Steam Generators Listed 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 ML20006E2611990-02-0909 February 1990 Responds to NRC Bulletin 88-009 Re Thimble Tube Thinning. Thimble Tube Insps Performed Using Eddy Current Testing Methodology & Performed at Every Refueling Outage Until Sufficient Data Accumulated to Generate Correlation ML20011F3661990-02-0707 February 1990 Forwards Errata to Radioactive Effluent Rept for Jan-June 1989 & Advises That Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor 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 ML20006E1521990-01-31031 January 1990 Discusses Applicability of Safety Evaluations Prior to Manipulation of ECCS Valves,In Response to Violations Noted in Insp Repts 50-454/89-16 & 50-455/89-18.Nuclear Operations Directive Re ECCS Valve Positions Will Be Sent by 900415 ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20005G3831990-01-10010 January 1990 Suppls 891117 Application for Amends to Licenses NPF-37 & NPF-66,incorporating Further Clarification of Curve Applicability in Tech Spec Figure 3.4-2a,per 891229 Telcon W/Nrc ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML20005E1751989-12-22022 December 1989 Forwards Rev 29 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML19332F6621989-12-14014 December 1989 Forwards Amend 12 to, Byron/Braidwood Stations Fire Protection Rept. Amend Reflects Changes to Facility & Procedures Effective 890630 1990-09-17
[Table view] |
Text
-
- 1. .
j, -KN Commonwealth Edison
/ J One First Natiomi Plut Chicigo, libnois
-( r 7 Address Heply to. Post Office Box 767
\ j/ Chicago. Ittinois 60690 )
July 10, 1984 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 i
Subject:
Byron Generating Station Units 1 and 2 I&E Inspection Report Nos. 50-454/84-27 and 50-455/84-19 Reference (a): June 6, 1984 letter from R. L. Spessard l
Cordell Reed.
t
Dear Mr. Keppler:
Reference (a) provided the results of an electrical inspection
- ct Byron by Messrs. Love and Christnot. During that inspection it was determined that certain activities were not in compliance with NRC requirements. . Attachment A to this letter contains Commonwealth Edison's response to the Notice of Violation appended to reference (a). For each violation we have provided important additional information to clarify the record.
Please address any questions regarding this matter to this Very ly yours
}
D. L. Farrar 4&
Director of Nuclear Licensing Im 8955N Y
8407310288 840725
$LO PDR G
ADOCK 05000454 PDR
ATTACHMENT A Response to Notice of Violation VIOLATION 1: (50-454/84-27-02; 50-455/84-19-02) 10 CFR 50, Appendix B, Criterion V, as implemented by Commonwealth Edison Company Topical Report (CE 1-A), Section 5, requires that activities affecting quality be prescribed by documented instructions or procedures.
Contrary to the above, the licensee failed to assure that the requirements of S&L Drawing 6E-0-3237 B, February 1983 Revision, Note 47, were translated into instructions or procedures. Note 47 requires the electrical contractor to inspect for cable tray separation and add cable tray covers when the minimum separation requirements have been violated.
This is exemplified by the fact that 124 units of safety-relat'ed cable tray has been installed since February 1983 and this tray has not been inspected for separation requirements. Additional details are discussed in Paragraph 2.d of Inspection Report 454/;84-27; 455/84-19(DE).
RESPONSE
Note #47 was first released as Engineering Change Notice (ECN) #3585, dated February 2, 1983. By procedure, the contractor's QA and engineering departments are required to review these approved changes.
On February 23, 1983, the contractor conducted a training session on the requirements of ECN #3585. This training session was attended by the contractor's Project Manager, Project Engineer and all engineering personnel, production personnel from Superintendents down through sub-foremen, and the QA/QC Manager and QA and QC inspection personnel and supervisors.
As the CECO Project Construction Electrical Supervisor and the HECo Project Engineer recall, they were asked by the Region III Inspector how construction notified the architect-engineer (Sargent & Lundy) of pan covers which may have been installed as a result of Note #47. The CECO Project Construction Electrical Supervisor's response to the Region III Inspector was that he was not aware of any requirement to do so and suggested that they review the note together. Upon reading the note, he pointed out to the Region III Inspector that Note #47 did not require notification to S&L of as-built information.
He agreed with the Region III Inspector that tne contractor's procedure could be considered deficient in that the QC inspection checklist did not contain specific checklist items to inspect for these separation requirements. He also pointed out to the Inspector that the cable pan cover installation procedure would have to be revised to ensure that covers were installed on any cable pans identified as not meeting the separation requirements of Note #47. As a result, he committed to the Region III Inspector to have the appropriate procedures revised to address the requirements of Note #47. He also agreed to include a method of supplying S&L with as-built information even though it wasn't specifically required by the note.
1 Corrective Action Taken and Results Achieved The 124 (83 Unit 1 and Al Unit 2) cable pan inspection reports documented on Hatfield Electric Nonconformance Reports 975 and 976 (for Unit 1 and Unit 2, respectively) which were initiated to address this concern and are described in DETAILS section of Inspection Report 84-27/84-19 will be reviewed and the required cable pans shall be reinspected for conformance to the separation requirements of Note #47 on the 0-3237B drawing.
Corrective Action Taken to Avoid Further Noncompliance On May 29, 1984, installation, inspection and notification criteria was established to meet the requirements of Note #47 on the 0-32378 drawing.
This new criteria has been added to the contractor's Cable Pan Installation Procedure 98 and implemented on June 15, 1984.
The contractor has also to revised his Cable Pan Cover Installation Procedure 9C to address the criteria established to meet the requirements of Note #47.
Date When Full Compliance Will Be Achieved The contractor's Cable Pan Installation Procedure 9B was revised and implemented on June 15, 1984. This revision includes specific quality control inspection checklist items as well as a CPSNF (Cable Pan separation Notification Form) which is forwarded to the owner and subsequently to the architect-engineer.
The contractor's revised Cable Pan Cover Installation Procedure 9C was implemented as of June 25, 1984.
It is anticipated that the 124 cable pan inspection reports documented on Hatfield Electric Nonconformance Reports 975 and 976 will be reviewed and reinspected as required per the new criteria and the NCR's closed by July 13, 1984, at which time we will be in full compliance with regard to this item.
8955N
i VIOLATION 2: (50-454/84-07-01; 50-455/84-19-01) 10 CFR 50, Appendix B, Criterion XVI,Has implemented by Commonwealth Edison Company Topical Report (CE 1-A), Section 16, requires that measures be established to assure that conditions adverse to quality such as nonconformances are promptly identified and correcteo.
Contrary to the above, the licensee failed to assure that nonconforming cable tray hangers were identified and corrected. This is exemplified by the fact that as a result of this NRC inspection, 345 previously accepted cable. tray hangers were reinspected and 119 were found defective and 19 were indeterminate because they were inaccessible for reinspection. A contributing factor to this item is that CECO Quality Assurance failed to determine the ef fectiveness of the electrical contractor's cable tray hanger reinspection program (Reference - HECo NCR 407R). Additional details are discussed in Paragraph 2.c of Inspection Report 454/84-27; 455/84-19(DE).
Response
A. After review of the circumstances surrounding Hatfield NCR 407, we cannot accept the NRC's characterization that Commonwealth Edison
" failed to assure that nonconforming cable tray hangers were identified and corrected." Extensive efforts have been made to verify the acceptability of cable tray hangers. Only 10 deficiencies have been identified.
Prior to February 1982, the documention of cable pan hanger inspections included little objective evidence with regard to the dimensional, type, and configuration attributes inspected. This observation was identified by the Hatfield Electric (HECo) Quality Assurance Manager in February 1982 and resulted in HECo NCR 407. The corrective action for HECo NCR 407 was to reinspect all cable pan hangers installed to date utilizing a supplemental inspection form which required notation of dimensional, type, and configuration attributes. This reinspection began in March 1982. Additionally, all subsequent installations and revisions to installed hangers required documentation of these attributes utilizing the supplemental form. This activity required the reinspection of over 4,000 previously installed hangers. This was an internally identified and corrective action activity undertaken to assure that nonconforming cable tray hangers were identified and corrected. Evidence was retained for external scrutiny.
In conducting this reinspection, it was found that the fireproofing which had been installed on the building structural steel framing rendered the hanger-to-structure connection detail visually unverifiable in a number of cases. As an alternative to requiring the removal of fireproofing, the existence of weld traveler inspection report on file evidencing an acceptable weld inspection
r_f" was-utilized as the basis'for acceptance of the connection detail when these conditions occurred. This was documented on the cable pan hanger inspection form by reference to the weld traveler number for the hanger. HEco QA/QC Memorandum 295 dated September 17, 1982, later documented this specific guidance. All other dimensional, type, and configuration attributes were reinspected and recorded on the hanger supplemental inspection form.
In August, 1982, an allegation was made to NRC Region III which questioned the validity of the alternative practice of accepting connection details by use of reference to acceptable. weld travelers.
.The program of reinspections to resolve NCR 407 was reviewed by a Region III inspector between August 16 and September 17, 1982. As documented in Inspection Report Nos. 50-454/82-17 and 50-455/82-12, the Commonwealth Edison Project Construction Department was to evaluate specific data from the cable pan hanger reinspection to determine the validity of this alternative approach. The key data points for this evaluation were: the total quantity of hangers which required removal of fireproofing to perform a weld inspection due to lack of a weld inspection record (including some welds inspected outside the scope of NCR 407 reinspection); from this total, the total quantity which had improper connection detail; and the total quantity of hangers inspected where the connection detail was not covered by fireproofing and which were unacceptable due to improper connection detail. The data for this evaluation was requested by the Commonwealth Edison Project Construction Department by letter to Hatfield Electric dated September 22, 1982.
The inspector indicated that this matter would be reviewed again and it was tracked as unresolved item 50-454/82-17-04 and 50-455/82-12-04. The Region III Inspector found that utilization of the weld traveler card was an adequate basis for accepting the hanger connection detail provided the weld traveler card identified the specific hanger connection detail. He made no finding regarding the validity of this approach when the connection detail was not documented on the traveler. The Inspection Report did not indicate that Memo 295 should be revoked. The inspector indicated that the matter would be held open until he could review the data and the CECO evaluation.
During the inspection period April 24 through May 11, 1984, the Region III Inspector again reviewed this unresolved item (.99-454/82-17-04; 50-455/82-12-04). Based on his review of the data, the alternative of accepting the connection detail based on existing weld travelers was not considered valid unless the weld traveler specifically referenced the connection detail.
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I As.a result of the Region III Inspector's concerns with utilizing Memorandum 295 as a means of accepting connection details, a review of all acceptable cable pan hanger inspection reports and their supplements was instituted to identify those which employed Memorandum 295 for the acceptance of the connection detail. This review identified an initial population of 345 hanger inspection reports. In geviewing the documenta- tion packages for these 345 inspection reports, it was found that 31' hangers were duplicated and/or had a subsequent inspection documenting acceptable connection detail. Of the 314 remaining hangers, 19 were inaccessible due to encasement in concrete or concrete block walls. The 295 remaining hangers had fireproofing removed and the connection detail to l
building structure reinspected. The raw unreviewed data was provided !
to the inspector by telephone on May 11, 1984.
After review, the inspection results are Nummarized as follows:
- 1. 91 deficiencies were reported for unacceptable gap between end of auxiliary steel and the building' steel. In March 1984 (prior
- to the Region III inspector's inspect' ion of April 24 through May l 11, 1984) we began an evaluation of tha need for inspection of t
this dimension. Prior to this the specified auxiliary steel length dimension was the inspection attribute inspected; the '
resultant spacing (gap) to building structure was not inspected. The size of the resultant gap is controlled by the tolerances associated with the ' building framing dimensions and ;
the auxiliary steel length. Samplinj inspection results and !
evaluations performed to date indicate the as-installed conditions are acceptable and do not indicate a need to inspect previously installed hangers for the resultant gap dimension.
- The inspection of the 295 hangers from which fireproofing was I removed included inspection of this resultant gap dimension.
l The evaluation of those hangers for the need for inspection of l this dimension which was begun in March 1984 by the architect-engineer is yet to be completed. Furthermore, when the 91 gap dimensions are compared with current design requirements, 83 of the 91 are not deficiencies. These 91 deficiencies affected 91 hangera of the 295 hangers inspected.
s l 2. 38 deficiencies were reported for wrong connection detail, wrong *
- weld length, elevation, ausiliary steel plate size, or missing l bolts. After review, it wai found that 42' deficiencies on 40 hangers were actually recorded. These 42 deficiencies fall into the following classes: N l ,
a) 10 occur because the drawing revision had not changed a detail which had been previously approved by a Field Change i Request or Engineering Change Notice, or were because of '
l drafting errors resulting in inconsistent dimensions; '
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b) 4 were under rework and were not complete through inspection and the inspector did not have the rework information at time of reinspection; c) 6 were due to errors by the reinspector and were not deficiencies; d) 2 were for resultant gap dimension between auxiliary steel to building framing steel and when compared with current design requirements are not deficiencies; i
e) 6 were auxiliary steel to framing steel centering deficiencies which.when compared with current design j requirements are not deficiencies; f) 4 were weld quality deficiencies not identifed by the original welding inspector; g) 8 were due to member size and appear to be errors by the first inspector; h) I was due to missing bolts on pan to hanger connection and appears to be error by first inspector; ;
i) 1 occurred because the hanger had sustained unacceptable damage.
After review, the data on the use of Memorandum 295 indicates that 10 actual deficiencies existed: I was a result of damage, I was a result of missing bolts, and 8 were a result of member size. We do not find that these constitute a failure to assure that nonconforming cable tray hangers were identified and corrected. Rather than falling to assure that nonconforming hangers were identified and ,
corrected, there may have been an error of judgement in using accepted weld traveler records as an alternative means of accepting hanger connection details which were not visible due to fireproofing.
'O. During the course of the Region III inspector's inspection of April 24 through May 11, 1984, he conducted a review of the data packages associated with 3 specific hangers and reported the results of his review in Inspection Report 50-454/84-27-01, 50-455/84-19-01. After further review of the records and other associated records, the following information is provided to clarify the record:
Section 2.C.(1) of 84-27/84-19; (Hanger 8HVil on Drawing 0-3097H01, Revision T) '
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a Weld Traveler #28780, dated 2/4/80, was identified as both the
, -initial weld traveler and the-welo traveler for the north side of the ha6ger. It {4ddressed only the particular work done on this hanger at the time. lIt 7 1s also the first of five weld travelers which were generated on this hanger between 2/4/80 and 12/16/82. - ,
- It appears that this hangef;upon which installation was begun in February,'1980,~was not requested-to be inspected until approximately June, 1982. It is likely that this hanger was found to have no inspection reports on file during the course of review for accountability performed in 1982 and from which inspection was initiated which resulted in DR 119 dated June 11,
-1982.- Inithe_ activity in response 0to DR'119, the responsible production ~ personnel initiated HDRF-ll51, dated September 30, 1982, in' order,to rebuild the hanger to the requirements of the current' design drawing,' FCR 1807 and FCR 2921. In that the condition of the requirement to rebuild the hanger to the latest design was identified by production personnel rather than inspection personnel, the HDRF was the means to perform the
, activity ^rather than a DR or NCR.
'Se5 tion 2.C . (2 ) 'o f 84-27/64-19 ; (Hanger H005 on Drawing 1-3051H, Revision H)
~
_- _ As noted in the.NRC inspection report, this hanger was inspected on 7/20/8,2 and the connection detail accepted on 9/27/82 based on Memos #295.
The fireproofing material was removed and the connection details inspected on 5/1/84. The hanger connection details and welding
- .,was found to be acceptable as _ installed.
~
- c -
- The summary report datedml0/10/83 appears to have been in error
-. _with zegard to this hanger. It should not have been listed as rejected for connection detail. ,
~
'Sec't ion 2.C . (3 )" o f 84-27/(4-19; (Hanger H153 on Drawing 1-3061H, (Revi'sionS) &
. ,_7 Thisshanger was removed and reworked due to structural beam modifications. As a result of Obstruction Removal Request
, (ORR), #3109;, HDRF #2197 was written to remove and rework H153.
HDRF-#2197 references ORR.#3109~cnd FCR #22920. In addition, S Rewor.k-Recuest,~7,A-1 #648 was written to remove and replace horizontal members of hanger H153 per FCR #22920 Rev. 1. The L dates :
of documents identified are as follows:
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- i HDRF #2197 is dated 5/4/83.
FCR #22920 is dated 6/21/83.
FCR #22920 Rev. 1 is dated 11/9/83.
Rework Request 7A-1 #648 is dated 1/3/84.
C. Additionally, the noncompliance states in part that "....a contributing factor to this item is that Commonwealth Edison Quality Assurance failed to determine the effectiveness of the electrical contractor's cable tray hanger reinspection program (Reference - HECo NCR 407R)." The Commonwealth Edison Quality Assurance Department performs audits and surveillance of contractors' nonconformance and corrective action systems to assess if the programs are established and implemented properly. The audits and surveillances examine nonconformance action to achieve an assurance that the programs are e f fective. An audit conducted by the Commonwealth Edison Corporate Office Quality Assurance Department during the time frame of August 8, 1983 - August 18, 1983 reviewed implementation of NCR 407 and found no signficant deficiencies of implementation or corrective action.
Corrective Action Taken and Results Achieved With regard to Hatfield Electric NCR 407R and in response to the Region III Inspector's concerns, Byron Site Quality Assurance Surveillance #6109 was performed to overview the Hatfield E.iectric activities associated with resolution of NRC unresolved item 50-454/82-17-04; 50-455/82-12-04 and NCR 407R. Additionally, an evaluation of those deficiencies which are associated with the resultant spacing (gap) between an auxiliary steel member and the building structure member, which were identified and are a topic previously discussed in this response, are being evaluated to determine if the items are minutiae or are items of significance requiring inspection.
Corrective Action Taken to Avoid Further Noncompliance In that actions previously taken to assure that nonconforming cable tray hangers were identified and corrected, we find that no other program or procedure changes are necessary to avoid further noncompliance. Contingent upon results of evaluation of those features which are under evaluation for necessity of inspection, no further action is intended with regards to cable tray hangers.
Date When Full Compliance Will Be Achieved We expect that the evaluation of the necessity to inspect additional features will be complete by July 20, 1984.
8955N b