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
7 'N Commonwealth Edison
[ _
_/ one First National Plaza. Chic +go. Illinois i Address Reply to: Post Office Box 767
/3 (,e/ Chicago Illinois 60690
May 27, 1980 Mr James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commjssion 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Byron Station Units 1 and 2 Response to IE Inspection Report 50-454/80-05 and 50-455/80-05 NRC Docket Nos. 50-454 and 50-455 Reference (a): April 25, 1980, letter to C. Reed from J. G. Keppler.
Dear Mr. Keppler:
Reference (a) contained the results of an inspection conducted by Mr. I. T. Yin of your of fice on March 25-26, 1980, of activities at Byron Station. During this inspection, certain activities appeared to be in noncompliance with NRC requirements.
Commonwealth Edison Company's response to the items of noncompliance are contained in Attachment A to this letter. Note that based on the additional information presented in response to Infraction #6, Commonwealth Edison requests that the basis for this infraction be reconsidered and that such reconsideration result in the infraction being withdrawn.
Please address any additional questions that you might have concerning this matter to this office.
Very truly yours, t
D. L. Peo es Director of Nuclear Licensing attachment 80062303(% 01880 4084A
NRC Docket Nos. 50-454/455 Attachment A INFRACTION #1 10 CFR 50, Appendix B, Criterion V, states, in part, that " Activities affecting quality shall be prescribed in documented instructions, ,
procedures, or drawings ... and shall be accomplished in accordance with these instructions, procedures, or drawings."
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 5 that "The quality assurance actions carried out for design, construction, testing, and operation activities will -
be described in documented instructions, procedures, drawings, specifications, or checklists. These documents will assist ',
personnel in assuring that important activities have been performed.
These documents will also reference applicable acceptance criteria which must be satisfied to assure that the quality related activity has been properly carried out."
Contrary to the above, the procedures established for installing safety related hangers and snubbers did not satisfy the above pro-gram in that manufacturer's installation requirements were not fully incorporated. ,
Corrective Action Taken and Results Achieved:
The safety related hanger and snubber supplier has forwarded its latest installation instructions which are as follows:
(1) ITT-G PHD-7594-1, Rev. 3, 10/12/79; (ii) ITT-G PE-217-1, Rev. O, 5/2/80; and (iii) ITT.G PHD-6511-8, Rev. O, 6/22/78.
The Site Work Instruction for Installation of Hanger Specialty Items has been revised to incorporate the latest instructions from the manufacturer for installation. This has been accomplished through the issuance of Site Work Instruction (SWI) No. 2, Revision 1.
The " Maintenance and Installation Manual ITT-Grinnell Fig. 306 and Fig. 307 Mechanical Shock and Sway Suppressor" ITT-G PHD-7594-1, Rev. 3, 10/12/79 does not contain any requirement for safety wire for the connection of the transition tube to the snubber. According to ITT-Grinnell personnel, this is no longer a requirement due to the use of high strength assembly screws.
Corrective Action Taken to Avoid Further Noncompliance:
Added emphasis will be placed on audits of instructions and procedures performed during 1980 by Commonwealth Edison Company to assure that site work instructions and procedures reflect the latest criteria.
Date When Full Compliance Will be Achieved:
! Full compliance will be achieved by June 2, 1980.
INFRACTION #2 10 CFR 50, Appendix B, Criterion X, states, in part, that "A program for inspection of activities affecting quality shall be established and executed by or for the organization performing the activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activities."
Commonwealth Edison Company Topical Report CE-1-A " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 10 that "QA inspection ... will be conducted
... at the site during construction ... to verify conformance to ,
applicable drawings, instructions ... to verify quality". .
Contrary to the above, many installed hangers and snubbers had not s' been QC inspected. The inspection program did not include suf ficient requirements in the areas of verif'1 cation of piping suspension system location, configuration, and condition, and did not require timely inspections to ensure prompt corrective action.
Corrective Action Taken and Results Achieved:
Site Implementation Procedure No. 4.000 has been revised to incorporate more detailed in-process inspections, which are as -
follows:
~
(1) Inspection of location of hanger attachment to the building structure; and (ii) Inspection of the completed installation of the assembly for compliance with the design drawing requirements and specific assembly instruction requirements.
Additionally, a Site Implementation Procedure No. 4.201,
" Installation Verification" has been generated which, for the area of component supports, initiates an inspection for hanger condition at time of completion of installation of all hangers in a given subsystem, and a reinspection for hanger condition at time of system inspection for turnover for operation. The inspection of location and inspection of completed installation, items (i) and (ii) above, are performed in-process, which is near term to the time of actual performance of the work.
Corrective Action Taken to Avoid Further Noncompliance:
Surveillance and audits will be conducted to assure that procedures are properly being implemented.
Date When Full Compliance Will Be Achieved:
Full compliance will be achieved by June 2, 1980.
I h
INFRACTION #3 10 CFR 50, Appendix B, Criterion VI, states, in part, that " Measures shall De established to control the issuance of documents ...
including the changes thereto, which prescribe all activities .
affecting quality. These measures shall assure that documents, including changes, are reviewed ... and approved ... by authorized p??sonnel and are distributed to and used at the location where the pcsscribed activity is performed."
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, date<j July 16, -
1979, states in Section 6, that "A document control system will be ,
used to assure that documents such as specifications, procedures, '.
and drawings are reviewed for adequacy and approved for release by authorized personnel. Such documents will be distributed to and used at the locations where the prescribed activity is performed.
Changes to these documents will be handled similarly and will be reviewed and approved by the same organization that performed the original review and approval, unless delegated by the originating organization to another responsible organization."
Contrary to the above, the con. tractor used inter-office memorandum to document procedure change and as a result bypassed the established document control procedures.
Corrective Action Taken and Results Achieved:
The use of inter-office memoranda to document procedure changes had been discontinued ef fective 8/27/79 which was prior to the subject inspection. The changes contained in the subject memoranda, HC-QA-23 have been incorporated into the latest revision of the applicable procedures, and the memoranda have been removed from use.
Corrective Action Taken to Avoid Further Noncompliance:
Added emphasis will be placed on audits of instructions and procedures performed during 1980 by Commonwealth Edison Company to assure that site work instructions and procedures are not updated through the use of inter-office memoranda.
Date When Full Compliance Will Be Achieved:
Full compliance will be achieved by June 2, 1980.
- . .
INFRACTION #4 10 CFR 50, Appendix B, Criterion III, states, in part, that " measures
, shall be established to assure that applicable ... design basis ...
for those structures, systems, and components ... are correctly ,
. translated into ... drawings ...".
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 3 that "The fundamental vehicle for design control involves multi-level review and/or evaluation of design .
documents by individuals or groups other than the original designer .
or designer's immediate supervisor whose authority and responsibility -
are identified and controlled by written procedures. The design documents include, but are not limited to, system flow diagrams, 8 design and construction specifications, load capacity data sheets, design reports, equipment specifications, process drawings."
Contrary to the above, design details shown on several installation 3
drawings did not meet the manufacturer's design parameters, and questionable adjustment requirements were specified.
5 Corrective Action Taken and Results Achieved:
7
- Manufacturer's design parameters regarding design pin-to-pin
, dimensions have been revised during the course of the project.
1 Current design is based on the latest pin-to-pin dimensions provided g by the manufacturer.
3 Adjustments are not being specified beyond what is allowed by the 6 manufacturer. The initial issue of a drawing for an ITT Grinnell Figure 306 indicates the required pin-to-pin dimension. Revisions e to the analysis, for example, may require a change in setting within the adjustabla stroke for the snubber. The field would then be instructed by drawing revision to field adjust to the required revised pin-to-pin dimension, as indicated on the drawing. Consider, for example, the two examples of noncompliance delineated in Section 6.a and 6.b of Reference (a) .
a) For snubber M-1CV020055, a revision to the pin-to-pin dimension as indicated on Rev. A was required. Rev. B was issued instructing che field to adjust to the pin-to-pin dimension as indicated on Rev. B. The adjustment is consistent with the adjustment capability of the snubber.
b) For snubber drawings M-lCV01006S and M-1CV030185, the current manufacturer design pin-to-pin dimension is exceeded. The drawings were reviewed by ITT Grinnell and it was determined that the design was acceptable based on the actual design load for the snubbers.
l
4 Corrective Action Taken to Avoid Further tJoncompliance:
A procedure is being finalized that will establish a review of all snubber drawings previously issued to insure that the current manufacturer's design requirements are met for all snubbers. The .
procedure will include. provisions for design reviews by the manufacturer (ITT Grinnell) to determine if specific deviations from stated pin-to-pin dimensions are acceptable.
Date When Full Compliance Will Be Achieved:
The review of snubber drawings will be completed by June 30, 1980. -
If necessary, adjustments will follow in a timely manner. ,
o' I
t t
i h
i l
4 INFRfCTION #5, 10 CFR 50, Appendix B, Criterion XII, . states', la part, that " Measures shall be established to control the .. . preservation of material and equipment in accordance with work and inspection instructions to -
prevent damage or deterioration".
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 13 that " Written instructions for handling, preservation, storage and shipping will be used to specify special
- protective conditions necessary to prevent damage or deterioration ,
, of materials and equipment". e Contrary to the above, several installed mechanical snubbers had not been properly protected and as a result hardware was damaged.
- Corrective Action Taken and Results Achieved:
Effective March 26, 1980, the installation of safety related mechanical and hydraulic snubbers ceased, and removal of those mechanical ar,1 hydraulic snubbers that had been installed was
- initiated. Ir.3tallation of mechanical and hydrmJ11c snubbers will j not be reinitiated until the building construction environment is
- such that the exposure to damage is minimal, or until protection can a
be provided and maintained for installed snubbers.
1'
- Corrective Action Taken to Avoid Further Noncompliance
No further action than that stated above is regelred to avoid further noncompliance.
I Date When Full Compliance Will Be Achieved:
j Jull compliance will be achieved by June 2, 1980.
t
INFRACTION #6 10 CFR 50, Appendix B, Criterion XVIII, states, in part, that "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 de'. ermine the ef fectiveness of the program."
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations", Revision 9, dated July 16, 1979, states in Section 18, that " 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." ,
U Contrary v.o'the above, the licensee had not performed comprehensive audits on the site hanger contractor ta ensure program adequacy for the installation and inspection of the pipe suspension systems.
Commonwealth Edison Company Response:
i The Commonwealth Edison Company Quality Assurance Department implements a comprehensive system of scheduled audits which are conducted on a regular basis to verify compliance with all aspects of its Quality Assurance Program. In addition to verifying compliance to the Commonwealth Edison Quality Assurance Program, the audit system also includes a comprehensive coverage of Edison's contractors, vendors, suppliers, Architect Engineers and NSSS l vendors.
In regard to specific audits of the site hanger contractor to ensure program adequacy for the installation and inspection of the pipe suspension system, the Commonwealth Edison General Office Quality Assurance Department conducted an extensive audit of the adequacy of the installation of ASME Section III piping and hangers in mid 1978.
Specifically, on August 18, 21, and 22, 1978, an audit was conducted at Byron to check the correctness of the installation of ASME Section III piping and hangers for the Component Cooling (CC),
l Chemical and Volume Control (CV), and Essential Service Water (SX) systems. Dimensions were checked for forty-one pipe spools and all measurements were referenced back to the surveyors marks. The audit team concluded that the components, in the systems audited, were installed according to the approved drawings. Comparable audits were also conducted at the Breldwood and LaSalle Construction Sites.
During the period February 21 through February 27, 1979, a six man audit team from the General Of fice Quality Assurance Department ,
conducted an extensive audit of Sargent & Lundy primarily to examine I the ef fectiveness of design control and design review in connection I
with pipe supports for the Byron, Braidwood, and LaSalle Stations.
The audit team identified several deficiencies. For the Byron /Braidwood projects, it was found that calculations for the auxiliary steel for certain pipe supports were not documented and i
+ -
that pipe support design documents issued prior to November, 1978, were not received, reviewed or processed by the Sargent & Lundy Structural Group. Both of the items resulted in extensive corrective action by Sargent & Lundy.
On May 22, 23, and 24, 1979, a seven man General Of fice Audit Team, accompanied by a consultant, Mr. R. N. Ferguson of the Energy, Inc.
who also did independent auditing, conducted an audit of the Byron Site. One of the major activities examined was the effectiveness of the Quality Control Inspection programs of the site contractors.
The team found that Hunter, the site piping and hanger contractor, .
was not performing Q.C. Inspections of piping supports other than .
the associated welding. There was evidence that Hunter Q.C. was ,
performing surveillances of hanger installations but the scope of the surveillances was limited. This deficient condition was cited 8 in the audit report.
On September 5, 6, and 7, 1979, a seven man General Office Audit Team conducted an audit of the Byron Site. One of the areas examined was to determine if the site contractors were performing in-process and final inspections for key work activities. The review of Hunter, the site piping and hanger contractor, showed that an extensive inspection program was established and implemented for key work activities. Records were examined which showed documented evidence of contractor Q.C. inspections in: welding, bolt torqueing, NDE, hydrostatic tests, pneumatic tests and pipe supports.
On September 15, 1979, Byron Site Q.A. conducted an audit of Hunter, and verified many items including (1) identification marks on components to assure proper piecas are installed, (2) surveillances and audits by Hunter to assure proper procedures are being followed for hanger installation work, and (3) the acceptability of hanger welds and final sign-off by Hunter Q.C. Inspectors.
On February 27, 28, and 29, 1980, and March 3, 1980, a five man General Ofice Audit Team conducted a follow-up audit of Sargent &
Lundy. During the audit, a check was made to evaluate the progress of documentating calculations for Byron /Braidwood pipe support auxiliary steel. The auditor found that approximately 5,600 of 8,400 safety-related supports had been reviewed for proper calculations and corrective action was proceeding adequately.
On March 19, 1980, Byron Site Q.A. conducted an audit of Hunter to evaluate the design and installation of small bore piping. The major emphasis was placed on organization, training, hanger drawing control and hanger field problems. Six deficiencies were identified including failure to properly protect snubbers in storage or those which were partially installed, as-built hanger drawings did not correctly reflect field conditions, Hunter surveillances did not identify rusty threads on hangers and weld inspections were not being done on a timely basis.
e, .
In addition, during the period 4/19/79 to 3/6/80, Site Quality Assurance Engineers conducted 10 documented surveillances specifically covering hanger installation by Hunter Corporation.
For the most part, no significant problems were identified. During the total period that Hunter has been working at Byron, Site Q. A.
performed about 170 other surveillances envering all aspects of Hunter's work activity. Many of these surveillances involved activities related to the installation of pipe supports. Also, Site Q. A. has performed a total of 15 audits of Hunter as of March 6, 1980.
Commonwealth Edison is committed to a comprehensive system of audits .
to ensure adequate implementation of quality procedures, programs, .
and requirements. '
The audits and surveillances described above are part of Edison's program to fulfill this commitment. It appears r that during the inspection conducted by the NRC, the above listing of Edison involvement in auditing of hanger l'nstallation at Byron was not available in the chronological listing as detailed above.
Commonwealth Edison has implemented a comprehensive system of audits of all contractors and has performed comprehensive and meaningful audits of the piping and piping supports at Byron. Accordingly, it is requested that the basis for this infraction De reconsidered and that such reconsideration result in the infraction being withdrawn.
e W