ML20137Z909
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| ML20137Z909 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/04/1985 |
| From: | Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20137Z914 | List: |
| References | |
| NUDOCS 8510080402 | |
| Download: ML20137Z909 (2) | |
Similar Documents at Braidwood | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999
[Table view]Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML17191B4761999-09-16016 September 1999 Refers to Meeting Conducted at Region III Office in Lisle,Il on 990713 Re Licensee Nuclear Generation Group Performance as Performance Relates to Actions Comed Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant 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.. ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That RT That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That RT That Occurred on Unit 2 During Startup Was Inadvertently Omitted ML17191B3951999-07-15015 July 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4) ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML17191B3941999-07-0909 July 1999 Ack Receipt of Rev 7L to Portions of Emergency Plan in Oct 1998.No NRC Approval Required Based on Determinations That Rev 7L Does Not Decrease Effectiveness of Emergency Plan ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML17191B3931999-06-30030 June 1999 Forwards Rev to Confirming Discussion Between Members of Staff to Have Meeting on 990713,in Region III Ofc to Discuss Util Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54 Ltr ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML17191B3821999-06-17017 June 1999 Discusses 990521 Meeting in Downers Grove,Il.Purpose of Visit to Meet Risk Mgt Staff Collectively Prior to Visiting Each Plant.Forwards Attendance List & Licensee Presentation 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 1999-09-08 Category:NRC TO UTILITY MONTHYEARML20062F5931990-11-19019 November 1990
[Table view]Forwards Safety Insp Repts 50-456/90-18 & 50-457/90-20 on 900817-1030.No Violations Noted ML20058E7071990-10-30030 October 1990 Ack Receipt of 901015 Response to Violations Re Employee Protection at Plant Sites ML20058B9531990-10-23023 October 1990 Forwards Insp Rept 50-456/90-20 on 901004-06.No Violation Noted.Nrc Plans to Meet W/Licensee to Discuss Corrective Actions.Licensee Should Prepare to Discuss Act of Conducting Multiple Surveillances on Sys W/High/Low Pressure Interface ML17202U8481990-10-17017 October 1990 Advises That 900926 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, Vendor Interface for Safety-Related Components, Acceptable ML20059N7001990-10-0505 October 1990 Forwards Safety Insp Repts 50-456/90-16 & 50-457/90-16 on 900729-0915.Noncited Violations Noted ML20059M1511990-09-14014 September 1990 Discusses Investigation Rept 3-85-018S from Investigation Conducted from 851107-880422 & 881101-900416 & Forwards Notice of Violation IR 05000295/19900131990-08-24024 August 1990 Forwards Notices of Violations from Insp Repts 50-456/90-13, 50-457/90-16,50-295/90-13 & 50-304/90-15 Inadvertently Removed from Rept Package Due to Administrative Error ML20059B3531990-08-17017 August 1990 Forwards Safety Insp Repts 50-456/90-13 & 50-457/90-16 on 900617-0728 & Notice of Violation.Licensee Appears to Have Weakness in Overall Mgt Control of non-routine Tech Spec Surveillance Activities ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20058L9911990-08-0606 August 1990 Forwards SERs of Responses & Associated Science Application Intl Corp 900614 Technical Evaluation Rept SAIC-89/1640 Re Station Blackout.Revised Response Addressing Areas of Nonconformance Should Be Submitted within 60 Days ML17202U7701990-08-0101 August 1990 Forwards Exam Form a W/Answers & Individual Answer Sheets from Generic Fundamentals Written Exam on 900606 ML20058L7241990-07-31031 July 1990 Discusses Potential Safety Issues Contained in Deposition Transcripts Provided by Util Attys Re Concerns Identified by Former Employee Including Quality of Welds at Facility, Welder certifications,N-5 Data Packages & Related Matters ML20055J1551990-07-24024 July 1990 Forwards Safeguards Insp Repts 50-456/90-15 & 50-457/90-18 on 900621-27.No Violations Noted ML20055G4161990-07-18018 July 1990 Forwards Safety Insp Repts 50-456/90-12 & 50-457/90-15 on 900429-0616 & Notice of Violation ML20044B0071990-07-11011 July 1990 Advises That 900627 Proposed Scope of Participation & Exercise Objectives for 900912 Emergency Preparedness Exercise Acceptable ML20055E0691990-06-29029 June 1990 Forwards Synopsis of NRC Investigation Rept 03-87-011 Re Investigation Performed at Facility,For Info ML20055E2411990-06-29029 June 1990 Forwards Synopsis of NRC Investigation Rept 03-85-18S. Licensee Will Be Notified of NRC Decision Re Enforcement Action Based on Findings Concerning Violations ML20055D1341990-06-28028 June 1990 Forwards Safety Insp Repts 50-456/90-14 & 50-457/90-17 on 900618-22.No Violations Noted ML20055E8791990-06-27027 June 1990 Forwards Notice of Withdrawal of 880302 Application for Amend to Change Tech Spec 4.6.1.6.1.d,to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin Not Reflected in Values Currently in Tech Specs,Per ML20043H8161990-06-20020 June 1990 Forwards Ofc of Investigations Case Rept 3-87-019 for Use in Preparing for Enforcement Conference.W/O Encl ML20055C7541990-06-15015 June 1990 Forwards Maint Team Insp Repts 50-456/90-08 & 50-457/90-08 on 900416-20 & 0430-0504 & Notice of Violation.Overall Insp Concluded That Implementation of Maint Program Adequate ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043F7841990-06-0505 June 1990 Advises That Written & Oral Operator & Senior Operator Licensing Exams Scheduled for Wk of 901022.Approved Ref Matl Listed in Encl Needed to Meet Schedule ML20043F7741990-06-0505 June 1990 Advises That 900412 Rev 58 to QA Topical Rept CE-1-A, Satisfies Requirements of 10CFR50,App B & Acceptable ML17202L2611990-05-30030 May 1990 Discusses Util Response to Generic Ltr 89-10, Safety- Related Motor-Operated Valve Testing & Surveillance. NRC Supports Concept of Coordinated Program for All Utils to Ensure Operability of motor-operated Valves ML20043C5541990-05-29029 May 1990 Confirms Plan to Conduct Mgt Meeting on 900531 to Discuss General Topics of Mutual Interest ML20055C6341990-05-23023 May 1990 Advises That Revised Schedule to Perform Blackness Testing within 2 Yrs of Placing Racks in Svc & Every 5 Yrs Thereafter,Acceptable ML20043B2401990-05-21021 May 1990 Forwards SER Accepting Util Proposal to Implement Seismic Stops at Plant & Computer Program for Evaluating Dynamic Response of Piping Sys Containing Seismic Stops Based on Std Dynamic Analysis Methodology ML20043B2351990-05-21021 May 1990 Forwards Request for Addl Info Re Plant First 10-yr Inservice Insp Program.Licensee Should Provide Boundary Diagrams Which Define ASME Code Class 1,2 & 3 Boundaries for Sys at Plant ML17202L2451990-05-21021 May 1990 Advises That 890711 Response to NRC Generic Ltr 89-06 on SPDS for Plants Acceptable.Nrc Review & Licensee Implementation of SPDS Considered Complete for Facilities ML20055C6191990-05-17017 May 1990 Forwards Safety Insp Repts 50-456/90-10 & 50-457/90-11 on 900318-0428 & Notice of Violation ML20043B1831990-05-17017 May 1990 Advises That Util Implementation Schedule Re Programmed Enhancement for Generic Ltr 88-17, Loss of DHR Acceptable. NRC Review of Generic Ltr 88-17 Will Be Accomplished as Insp Under Temporary Instruction 2515/103 in NRC Insp Manual ML20043A7341990-05-17017 May 1990 Forwards Safety Evaluation Concurring W/Licensee Conclusion That Venting Containment Liner Weld Leak Chase Channels During Containment Integrated Leak Rate Test Unnecessary Provided Visual Insp of Accessible Portions Performed ML20043A5541990-05-17017 May 1990 Forwards Request for Addl Info to Continue Review of Util 890821 Submittal Re Discrepancy Between Existing Byron & Braidwood Designs for Containment Hydrogen Monitoring Sys, Approved in Original Sers.W/O Encl ML20043A3851990-05-14014 May 1990 Forwards Safety Insp Rept 50-457/90-13 on 900417,23 & 0507. No Violations Noted ML20042G8991990-05-11011 May 1990 Advises That Util 900129 Response to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations Acceptable ML20042G7621990-05-0909 May 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 900606.Map of Area Including Time & Location Where Exams Will Be Administered Also Encl ML20042G1161990-05-0404 May 1990 Accepts Util 891027 60-day Response to Generic Ltr 88-20, Individual Plant Exams. NRC Anticipates That Any Possible Addl Analysis or Reporting Requirements,Such as External Events,Will Not Have Adverse Effect on Util Schedule ML20042G5111990-05-0303 May 1990 Forwards Requalification Exam Rept 50-456/OL-90-01 on 900402 for Units 1 & 2 ML20042E8941990-04-20020 April 1990 Forwards Safety Insp Repts 50-456/90-11,50-457/90-14, 50-454/90-13,50-455/90-12,50-237/90-14,50-249/90-13, 50-373/90-07,50-374/90-08,50-254/90-07,50-265/90-07, 50-295/90-10 & 50-304/90-11 on 900220-0404 ML20034B7291990-04-18018 April 1990 Forwards Safety Insp Rept 50-457/90-12 on 900320-0405.No Violations Noted.Cause of Event Appears to Have Originated as Result of Poor Communication Practices Between Supervisors & Operators ML20034A6521990-04-16016 April 1990 Forwards Safety Insp Repts 50-456/90-09 & 50-457/90-09 on 900313-23 & Notice of Violation ML20012F3711990-03-30030 March 1990 Forwards Safety Insp Repts 50-456/90-06 & 50-457/90-06 on 900201-0317.One Noncited Violation Identified ML20012E8521990-03-26026 March 1990 Confirms Plans for 900426 Meeting at Plant Training Facility to Present Initial SALP 9 Rept ML20012F5561990-03-26026 March 1990 Forwards SER & Technical Evaluation Rept Accepting Util Responses to Generic Ltr 83-28,Item 2.2.1 (Part 1), Equipment Classification Program for All Safety-Related Components ML20012D7471990-03-16016 March 1990 Forwards Safety Insp Repts 50-456/90-07 & 50-457/90-07 on 900220-0306.No Violations Noted ML20033F4061990-03-14014 March 1990 Approves Request for Use of B&W & Westinghouse Steam Generator Plugs Mfg w/nickel-base Alloy (ASME Designation SB-155/Alloy 690) as Alternative to Use of Alloy 600 ML20012C5121990-03-12012 March 1990 Documents NRC Understanding of Requalification Exam Process to Be Administered at Plant During Wks of 900402 & 09.Format to Be Employed at Plant for Operating Exams Will Defer from Previous NRC Administered Exams in Listed Specific Features ML17202J1791990-03-0808 March 1990 Forwards Understanding of Current Status of All Unimplemented USIs for Plants,Per Generic Ltr 89-21 ML20012B1911990-03-0505 March 1990 Forwards Request for Addl Info Re Elimination of Dynamic Effects of Postulated Pipe Ruptures in Reactor Coolant Bypass & Accumulator Piping from Design Basis 1990-09-14 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217G9791999-10-14014 October 1999
[Table view]Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML17191B4761999-09-16016 September 1999 Refers to Meeting Conducted at Region III Office in Lisle,Il on 990713 Re Licensee Nuclear Generation Group Performance as Performance Relates to Actions Comed Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 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 ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA 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) ML17191B3951999-07-15015 July 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4) ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML17191B3941999-07-0909 July 1999 Ack Receipt of Rev 7L to Portions of Emergency Plan in Oct 1998.No NRC Approval Required Based on Determinations That Rev 7L Does Not Decrease Effectiveness of Emergency Plan ML17191B3931999-06-30030 June 1999 Forwards Rev to Confirming Discussion Between Members of Staff to Have Meeting on 990713,in Region III Ofc to Discuss Util Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54 Ltr ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML17191B3821999-06-17017 June 1999 Discusses 990521 Meeting in Downers Grove,Il.Purpose of Visit to Meet Risk Mgt Staff Collectively Prior to Visiting Each Plant.Forwards Attendance List & Licensee Presentation ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative ML17191B3761999-06-11011 June 1999 Confirms Plans to Hold Meeting on 990713 in Region III Ofc to Discuss Ceco Nuclear Generation Group Performance Re Actions Taken in Response to NRC 970127 10CFR50.54(F) Ltr Safety Performance at Nuclear Facilities ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration 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 ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified ML20206U4641999-05-18018 May 1999 Responds to Util 990517 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3.0.3. Documents 990516 Telcon with Licensee Re NOED ML20206N4791999-05-13013 May 1999 Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date ML17191B3441999-05-11011 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206Q5321999-05-11011 May 1999 Forwards Insp Repts 50-456/99-06 & 50-457/99-06 on 990302-0413.Configuration Control Error Resulted in Isolation of Unit 1 Emergency Boration Flow Path Through Designated Boric Acid Pump for Period of 3 H Occurred ML20206H8161999-05-0505 May 1999 Confirms Discussion Re Meeting to Be Conducted on 990527 at Braidwood Station Training Building.Meeting Will Discuss Braidwood Station Performance as Described in Most Recent Plant Performance Review ML20206E7021999-05-0303 May 1999 Advises That Info Contained in Document Entitled, Licensing Rept for Sf Rack Installation at Byron & Braidwood Stations, HI-982083,will Be Withheld from Public Disclosure Per 10CFR2.790 ML20205G9631999-03-26026 March 1999 Advises of Planned Insp Effort Resulting from Braidwood Plant Performance Review for Period 870830-990131.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 6 Months Encl ML20204J9001999-03-23023 March 1999 Forwards Insp Repts 50-456/99-02 & 50-457/99-02 on 990120- 0301.No Violations Noted ML20204J4241999-03-23023 March 1999 Forwards Insp Repts 50-456/99-04 & 50-457/99-04 on 990222-24 & 0303 Onsite & 0309 & 11 Region 3 Ofc.No Violations Noted. Implementation of Physical Security Plan Was Examined ML20204G2031999-03-22022 March 1999 Forwards Year 2000 Readiness Audit Rept Which Documents Results of NRR Audit Conducted at Facility from 990124-28 ML20204C7201999-03-16016 March 1999 Ack Receipt of Expressing Concern Over Sale of Certain Properties by Commonwealth Edison Co ML20204E3341999-03-16016 March 1999 Expresses Appreciation for Re Concerns Over Sale of Certain Properties by Licensee.No Regulatory Basis for NRC to Require Util to Rely on strip-mine Ponds as Suppl Source of Cooling Water ML20204E2801999-03-16016 March 1999 Ack Receipt of Rev 3M to Portions of Braidwood Nuclear Power Generating Station Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Ceco Determinations That Changes in Rev 3M Do Not Decrease Effectiveness of Plan ML20207J9741999-03-11011 March 1999 Discusses Rev 3,to Portions of Braidwood Power Station EP Site Annex.Based on Licensee Determinations That Changes Do Not Decrease Effectiveness of EP & Plan Continues to Meet Standards of 10CFR50.47(b),NRC Approval Not Required ML17191B2541999-02-13013 February 1999 Provides Summary of 990128 Meeting in Lisle,Illinois Re Commonwealth Edison Company Nuclear Generation Group Performance Re Actions Taken in Response to NRC Re Safety Performance at Licensee Nuclear Facilities ML20203E9521999-02-11011 February 1999 Forwards Insp Rept 50-456/98-16 on 980916-990121.No Violations Were Identified.Insp Was Exam of Activities Re Engineering & Maint Activities for Replacement of Steam Generators for Compliance with Commission Regulations ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML17191B2331999-02-0909 February 1999 Discusses Ceco 950105 Request for Review & Approval of Four near-site Emergency Operations Facilities (Eofs) & Corporate EOF Into One Single,Central Eof.Concludes That Central EOF Meets All of Functional & Physical Requirements for EOFs ML20203C9761999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 44 to Security Plan.No NRC Approval Required 1999-09-06 |
See also: IR 05000456/1985032
Text
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iOCT 0 41985
Docket No. 50-456
Docket No. 50-457
Commonwealth Edison Company
ATTN: Mr. Cordell Reed
Vice President
Post Office Box 767
Chicago, IL 60690
Gentlemen:
This refers to the routine safety inspection conducted by Messrs.
R. D. Schulz and W. J. Kropp of this office on June 24 through
- September 6, 1985, of activities at the Braidwood Station, Units 1 and
2, authorized by NRC Construction Permits No. CPPR-132 and No. CPPR-133
and to the discussion of our findings with Mr. M. Wallace at the
conclusion of the inspection.
The enclosed copy of our inspection report identifies areas examined during
the inspection. Within these areas, the inspection consisted of a selective
examination of procedures and representative records, ot servations, and
interviews with personnel.
During this inspection, certain of your activities appeare4 to be in
violation of NRC requirements, as specified in the enclosed Appendix.
A
written response is required.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter and the enclosure (s) will be placed in the NRC's Public Document
Room.
The responses directed by this letter (and the accompanying Notice) are not
subject to the clearance procedures of the Office of Management and Budget
as required by the Paperwork Reduction Act of 1980, PL 96-511.
.
.
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10CT 0 4 SS5
Commonwealth Edison Company
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
W. S. Little, Director
Braidwood Project
Enclosures:
1.
Appendix, Notice of
Violation
2.
Inspection Reports
No. 50-456/85032(DRP);
No. 50-457/85031(DRP)
cc w/ enclosures:
D. L. Farrar, Director
of Nuclear Licensing
M. Wallace, Project Manager
D. Shamblin, Construction
Superintendent
J. F. Gudac, Plant Manager
C. W. Schroeder, Licer. sing and
Compliance Superintendent
DCS/RSB (RIDS)
Licensing Fee Management Branch
Resident Inspector, RIII
Braidwood
Resident Inspector, RIII Byron
Phyllis Dunton, Attorney
General's Office, Environmental
Control Division
D. W. Cassel, Jr. , Esq.
J. W. McCaffrey, Chief, Public
Utilities Division
H. S. Taylor, Quality Assurance
Division
E. Chan, ELD
J. Stevens, NRR
The Honorable Herbert Grossman, ASLB
The Honorable A. Dixon Callihan, ASLB
The Honorable Richard F. Cole, ASLB
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Farber
Williams
Dan- elson
Little
09/25/85
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