IR 05000454/1984051
From kanterella
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| ML20128B778 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 06/18/1985 |
| From: | Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20128B780 | List: |
| References | |
| NUDOCS 8507030348 | |
| Download: ML20128B778 (3) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999
[Table view]Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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 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 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 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 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 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 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required 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 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 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 BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr 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 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 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) 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 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 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 ML20217A1551990-11-14014 November 1990 Forwards Safety Insp Rept 50-455/90-22 on 901002-1107. Violations Noted ML20217A4431990-11-14014 November 1990 Forwards Safety Insp Rept 50-455/90-21 on 900910-11,24-26 & 1107.No Violations Noted ML20058G3241990-11-0505 November 1990 Forwards Page 9 of Insp Repts 50-454/90-16 & 50-455/90-15. Page Erroneously Deleted from Original Rept ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant 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 ML20059N7001990-10-0505 October 1990 Forwards Safety Insp Repts 50-456/90-16 & 50-457/90-16 on 900729-0915.Noncited Violations Noted ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L3051990-09-14014 September 1990 Forwards SER Re Util 900706 Request for Relief Concerning Inservice Testing Program.Relief Granted from Testing Requirements Which Would Impose Undue Hardship If Immediate Compliance Was Imposed ML20059L4531990-09-14014 September 1990 Forwards Suppl to SER Re Results of Inservice Testing Program Changes Based on Review of 881221 & 890203 Submittals.Changes Acceptable ML20059M1511990-09-14014 September 1990 Discusses Investigation Rept 3-85-018S from Investigation Conducted from 851107-880422 & 881101-900416 & Forwards Notice of Violation ML20059E1141990-08-30030 August 1990 Forwards Safety Insp Repts 50-454/90-16 & 50-455/90-15 on 900814-17.No Violations Noted 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 ML20059B4271990-08-17017 August 1990 Forwards Safety Insp Repts 50-454/90-17 & 50-455/90-16 on 900701-0811.No Violations Noted 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 ML20059A2401990-08-14014 August 1990 Advises That Operator & Senior Operator Licensing Exams Scheduled for Wk of 901203.Preliminary License Applications Should Be Submitted at Least 30 Days Before First Exam Dates in Order to Review Training & Experience of Candidates 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 ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls 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 ML20055J1521990-07-20020 July 1990 Forwards Final SALP Repts 50-454/90-01 & 50-455/90-01 for Nov 1989 - Mar 1990 ML20055G6661990-07-18018 July 1990 Confirms 900802 Enforcement Conference in Region III Ofc to Discuss Ofc of Investigations & Regional Findings Re Lack of Control of Operability Determinations Involving Emergency Diesel Generators at Plant.Listed Items to Be Discussed ML20055G4161990-07-18018 July 1990 Forwards Safety Insp Repts 50-456/90-12 & 50-457/90-15 on 900429-0616 & Notice of Violation ML20055G3301990-07-17017 July 1990 Forwards Safety Insp Repts 50-454/90-14 & 50-455/90-13 on 900513-0630.No Violations Noted ML20055E2171990-07-0202 July 1990 Forwards Requalification Exam Rept 50-454/OL-90-01 for Units 1 & 2 Administered During Wks of 900528 & 0604.Requests Response to Issue of Training & Evaluating Operators on Uncontrolled Depressurization of Steam Generators 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 ML20055D0251990-06-28028 June 1990 Forwards Safety Insp Repts 50-454/90-15 & 50-455/90-14 on 900611-14.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 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 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 ML20055C6191990-05-17017 May 1990 Forwards Safety Insp Repts 50-456/90-10 & 50-457/90-11 on 900318-0428 & Notice of Violation ML20055C5731990-05-16016 May 1990 Ack Receipt of 900430 Response to Allegation RIII-90-A-0011 Re Employee Fitness for Duty.Confirms That Results of fitness-for-duty Test Negative & Allegation Unsubstantiated ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20247R8411989-09-26026 September 1989 Forwards Safety Insp Repts 50-456/89-22 & 50-457/89-22 on 890730-0916 & Notice of Violation.Requests That Util Provide Description of Mgt Actions to Assure Proper & Timely Notifications in Future ML20248D4981989-09-26026 September 1989 Accepts Scope & Objectives for Annual Emergency Preparedness Exercise Scheduled for 891206 & 07,submitted by ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247H8291989-09-12012 September 1989 Forwards Safety Insp Repts 50-456/89-24 & 50-457/89-24 on 890703-0901 & Notice of Violation.Particular Concern Re Violation 2 in Which Several Layers of Oversight Failed to Identify Recorded Survey Which Exceeded Stated Limit Noted ML20247E9721989-09-0707 September 1989 Forwards Safeguards Insp Repts 50-456/89-21 & 50-457/89-21 on 890731-0815.Violations Noted ML20246M5921989-08-29029 August 1989 Forwards Safety Insp Repts 50-454/89-16 & 50-455/89-18 on 890701-0819 & Notice of Violation 1990-09-25 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M2871999-10-21021 October 1999
[Table view]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 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 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 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 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 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 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 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 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 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 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 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 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 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 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 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 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 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) IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams 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 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 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 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 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 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 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 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 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 ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified 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 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 ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us 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 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 1999-09-08 |
Inspection Report - Byron - 1984051 | |
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Docket No. 50-454 Docket No. 50-455 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:
Thank you for your letter dated May 10, 1985, infonning us of the steps you have taken to correct the violations which we brought to your attention in our letter dated April 3,198 While our inspection revealed that you have taken acceptable actions to correct the problems, we offer the following comments to clarify our review on some of your responses to the Notice of Violation:
Attachment A Item 2.b:
Relative absorbingtomaterial the rubbing)within (EAM enclosure the pipe whip restraint structures, energy the interference would possibly have caused the compression leg to bind up inside the enclosures and result in localized structural deformatio Item Regarding your statement that the test data initially received from the EAM manufacturer did not indicate strength reduction due to height to width (H/W) ratios of two or less, or due to stacking, our review identified that: (1) the Hexcel H/W report dated l August 25, 1981, for 4000 psi EAM indicated that one of the two l pieces of EAM tested with a H/W ratio of two showed that the specimen l started to buckle, and (2) the Hexcel EAM stacking test report dated l
June 16, 1982, for 1000 psi EAM indicated that the three (2" high X 4" wide X 4" long) pieces of EAM that were stacked provided H/W ratio of only 1.5.
l Item Regarding your statement that the EAM retaining box does not affect l
the EAM crush strength during EAM deformation because the retainer box has been provided with sufficient clearance, our inspection l
revealed EAM installed in retaining boxes without any clearance on l one side of the box. We also offer that the amount of clearance considered by you to be sufficient was not defined in the design criteria.
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Comonwealth Edison Company 2 JUN 181985 Attachment B Item 1: Regarding your statement that the NRC reviewed and accepted the qualification tests conducted for the large bore Boeing steam generator snubber re-design and modification, although the Region III review concluded that the results of all tests performed were acceptable, the life cycle test was not consistent with the original test requirement Your response indicated that you plan to have ITT-Grinnell functionally test each Boeing snubber following assembly after modification. We request that you provide us an opportunity to review the test procedures in advance of the tests, and that you notify us sufficiently in advance of the tests to allow us to make arrangements to observe the test setups and testing. Please provide all information related to these matters to Mr. D. Danielson (790-5610)
or Mr. J. Harrison (790-5635) of my staf Should you have any questions, please contact this offic Whm% ye r-R. L. Spessard, Director Division of Reactor Safety cc: D. L. Farrar, Director of Nuclear Licensing M. Wallace, Project Manager D. Shamblin, Construction Superintendent J. F. Gudac, Station Superintendent C. W. Schroeder, Licensing and Compliance Superintendent V. I. Schlosser, Project Manager Gt;nner Sorensen, Site Project Superintendent R. E. Querio, Plant Manager
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Commonwealth Edison Company 3 JUN 181985 cc w/ltr dtd 05/10/85:
DMB/ Document Control Desk (RIDS)
Resident Inspector, RIII, Braidwood Resident Inspector, RIII, Byron W. L. Paton, ELD L. Olshan, LPM, NRR Phyllis Dunton, Attorney General's Office, Environmental Control Division D. W. Cassel , Jr. , Es J. W. McCaffrey, Chief, Public Utilities Division H. S. Taylor, Quality Assurance Division Diane Chavez, DAARE/ SAFE RIII RI I RIE
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