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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes 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 BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 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 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 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 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 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 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 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 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 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 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999 Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5 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 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F5931990-11-19019 November 1990 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 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 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 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 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 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 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 ML20246F1401989-08-22022 August 1989 Forwards Safety Insp Repts 50-456/89-16 & 50-457/89-16 on 890731-0803.No Violations Noted ML20245F2031989-08-0404 August 1989 Forwards Safety Insp Repts 50-456/89-19 & 50-457/89-19 on 890618-0729.No Violations Noted ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20247J2121989-07-24024 July 1989 Forwards Safety Team Insp Repts 50-456/89-18 & 50-457/89-18 on 890612-0706.No Violations Noted ML20247G2941989-07-21021 July 1989 Discusses Inleakage Test to Determine Air Infiltration Into Control Room Envelope When Control Room Placed in Isolation Mode.Performance of Test During Unit 1 Outage Will Satisfy Commitment by Util ML20247D1401989-07-18018 July 1989 Forwards SER Supporting Util Proposed Implementation of ATWS Design,Per 10CFR50.62 Requirements ML20247A2341989-07-17017 July 1989 Forwards Enforcement Conference Repts 50-456/89-20 & 50-457/89-20 on 890711 & Notice of Violation.Plant May Be Subj to Escalated Enforcement Action Upon Discovery of Addl Valve Mispositioning Affecting ECCS Operability ML20246C1091989-07-0505 July 1989 Advises That 890612 Proposed Scope & Objectives for 1989 Emergency Preparedness Exercise on 890906 Acceptable ML20245K0411989-06-27027 June 1989 Confirms 890711 Enforcement Conference W/Util in Region III to Discuss Concerns Associated W/Operability of Centrifugal Charging Pump 2B & Previous Instances in Which ECCS Equipment Operability Affected by Mispositioned Valves ML20245H8391989-06-26026 June 1989 Forwards Safety Insp Repts 50-456/89-17 & 50-457/89-17 on 890601-20.Violations Noted.Decision Re Enforcement Action Will Be Sent by Separate Correspondence ML20245H9141989-06-23023 June 1989 Forwards Safety Insp Repts 50-456/89-15 & 50-457/89-15 on 890430-0617.No Violations Noted ML20245B7191989-06-19019 June 1989 Forwards Safety Insp Repts 50-456/89-11 & 50-457/89-11 on 890508-24.No Violations Noted.Dates Requested for Completing Actions Re Open Items Identified in Rept.Commends Util for Overall Quality of Emergency Operating Procedures ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20244C8301989-06-13013 June 1989 Advises of Changes to 890621 Visit of French Ministry of Research & Industry to Plant to Exchange Info on Protection of Commercial Nuclear Reactors in Us & France.Names & Bibliographical Info & Revised Schedule for Visit Encl ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20247P9281989-06-0101 June 1989 Advises That Two French Security Experts Will Visit Us on 890616-22 to Exchange Info on Protection of Commercial Nuclear Reactors in Us & France.Delegation List & Itinerary Encl ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied ML20247N7991989-05-30030 May 1989 Requests Encl Listed Ref Matls 60 Days Before Operator & Senior Operator Licensing Exams During Wk of 891030.Facility Training Staff Required to Retain Simulator Exam Scenario Info Until Examinees Either Passed Exam or Filed Appeal ML20247P0451989-05-26026 May 1989 Forwards Insp Repts 50-456/89-14 & 50-457/89-14 on 890425-28.No Violations or Deviations Noted.Ltr,Documenting Actions in Response to Inattentiveness Incidents,Requested within 60 Days of Ltr Receipt ML20247K4921989-05-25025 May 1989 Forwards Requalification Exam Rept 50-456/OL-89-01 for Exam Administered During Week of 890417 ML20247H3511989-05-19019 May 1989 Advises That Licensee Response to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation,Per Rev 3 to Reg Guide 1.97,acceptable,except for Four Items Listed in Technical Evaluation Rept ML20247C1521989-05-18018 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Understands That Westinghouse Will Provide Util W/Generic Bounding Analysis Re Seismic Loadings ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 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 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 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 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 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 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 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 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 ML20204J9001999-03-23023 March 1999 Forwards Insp Repts 50-456/99-02 & 50-457/99-02 on 990120- 0301.No Violations Noted 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 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 ML20203C9761999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 44 to Security Plan.No NRC Approval Required ML20203A4601999-02-0505 February 1999 Ack Receipt of 981109 Evaluation of Indication in Base Metal of Braidwood Station,Unit 1,main Steam Piping Sys Elbow ML20203A3641999-02-0303 February 1999 Forwards Copy of FEMA Evaluation Rept for 980520 Emergency Preparedness Exercise at Braidwood.One Deficiency & Three Areas Requiring Corrective Action Identified.Deficiency Corrected During Remedial Exercise Held on 980806 ML20199E6561999-01-15015 January 1999 Discusses Unresolved Security Item Re Adequacy of Compensatory Measures Implemented for Section of Vehicle Barrier Sys.Issue Briefly Described as Listed ML20199E1351999-01-0808 January 1999 Forwards Revised Dates for Engineering & Technical Support Insp,Emergency Planning Insp,Security Insp & Operational Assessment Insp for Braidwood IR 05000456/19980141999-01-0505 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts on 50-456/98-14 & 50-457/98-14 Issued on 981117 ML20198R0741998-12-30030 December 1998 Forwards Insp Repts 50-456/98-20 & 50-457/98-20 on 981020-1207.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20197J6831998-12-10010 December 1998 Forwards Insp Repts 50-456/98-21 & 50-457/98-21 on 981110- 24.No Violations Noted.Insp Reviewed Corrective Actions for Previously Identified Issues ML20197H4261998-12-0404 December 1998 Forwards Insp Rept 50-456/98-18 on 981015-23 & 1109-10.No Violations Noted.Some Weaknesses Identified in Operator Performance & Training ML20197K1311998-12-0202 December 1998 Forwards Planned Insp Effort for Next 6 Months at Plant.Info Provided to Minimize Resource Impact on Staff & Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite 1999-09-06
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SEP 101987 Docket No. 50-456 Docket No. 50-457 Commonwealth Edison Company ATTN: Mr. Cordell Reed I Senior Vice President Post Office Box 767 I Chicago, IL 60690 l l
Dear Mr. Reed:
SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. George Vanderheyden, and Mr. Darrel Damon, arrangements were made for the administration of examinations at the Braidwood Station.
The written and oral examinations are scheduled for the week of December 14 and 21, 1987.
In order for us to meet this schedule, it will be necessary for the facility l to furnish the approved reference material listed in Enclosure 1 " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations" at least 60 days prior to the examination date. Any delay in receiving properly bound and indexed reference material will result in a delay in administering the examinations. Our examinations are scheduled far in l advance with considerable planning to best utilize our limited examiner manpower and to meet the examination dates requested by the various facilities.
l Therefore, missing the deadline, even by a fe" days, will likely result in a long delay since it may not be possible to reschedule examinations at other facilities. Mr. Vanderheyden has been advised of our reference material requirements, the number of reference material sets that are required, and the examiners' names and addresses where each set is to be mailed.
I The facility management is responsible for providing adequate space and I
accommodations in order to properly conduct the written examinations.
l Enclosure 2, " Administration of Reactor / Senior Reactor' Operator Licensing l Written Examinations," describes our requirements for conducting these examinations. Mr. Vanderheyden has also been informed of these requirements.
In addition, to better document simulator examinations, the chief examiner will have the facility simulator operator record prespecified plant conditions (i.e. , plant pressure, temperature, pressurizer level, etc.),
for each simulator scenario. The candidate will be responsible for providing this information, along with any appeal of his simulator operating examination. Therefore, the facility training staff should retain the simulator examination scenario information until all candidates h/
taking the examination have either passed the operating examination or all appeals filed by the candidates who failed the operating examination have been completed.
[)Y ' /
8709140228 870910 PDR V ADOCK 0S000456 PDR ggf
SEP 1 o 1997 Commonwealth Edison Company 2 Enclosure 3 contains the Rules and Guidance that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all candidates are aware of these Rules. >
All reactor operator and senior reactor operator license applications should normally be submitted at least 60 days prior to the first examination dates so that we will be able to review the training and experience of the candidates, process the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined. If the applications are not received at least 30 days prior to the examination dates, it is likely that a postponement will be necessary.
l This request for information was approved by the Office of Management and Budget under Clearance Notaber 3150-0101, which expires May 31, 1989.
Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D.C. 20503.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility Review of Written Examination." Mr. Vanderheyden has been informed of these requirements.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Darrel Damon at (312) 790-5278.
Sincerely, Original Signed By T. Burdick 1
Charles W. Hehl, Chief Operations Branch l
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines For License Examinations
- 4. Facility Review Requirements See Attached Distribution l RIII RJjI (III b b L/ O Damon/mnj Burdick H6hl ,
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l SEP1o 1937 l Commonwealth Edison Company 3 l
l Distribution cc w/ enclosures:
D. Butterfield, Nuclear Licensing Manager M. Wallace, Manager of Projects D. Shamblin, Project Manager W. Vahle, Construction Superintendent E. E. Fitzpatrick, Station Manager P. L. Barnes, Regulatory Assurance Supervisor DCS/RSB (RIDS)
- Licensing Fee Management Branch l Resident Inspector, RIII
' Braidwood Resident Inspector, RIII Byron D. W. Cassel, Jr., Esq.
Richard Hubbard J. W. McCaffrey, Chief, Public Utilities Division H. S. Taylor, Quality Assurance Division E. Chan, 0GC G. Berry, 0GC J. Stevens, NRR The Honorable A. Dixon Callihan, ASLB The Honorable Richard F. Cole, ASLB The Honorable Ivan W. Smith, ASLB The Honorable Gary J. Edles, ASLAP The Honorable Dr. W. Reed Johnson, ASLAP The Honorable Christine N. Kohl, ASLAP W. McGee, Plant Training Manager cc w/o enclosures:
J. Stevens, Project Manager, NRR J. N. Hannon, Branch Chief, OLB W. S. Little, Branch Chief, DRP R. W. Cooper, NRR
ENCLOSURE 1 Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 1. Failure to provide complete, properly bound and indexed plant reference material will result in canceling and rescheduling of the examinations.
- 2. Training material should include all substantive written material used' for preparing candidates for initial' R0 and SR0 licensing.
- 3. The written material'should include learning objectives and the details presented during lectures, rather than outlines.
- 4. Training material and procedures should be identified by plant and unit along with appropriate indexes or table of contents.
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- 5. The reference material and procedures should be approved, final issues, and should be so marked.
- 6. If the facility is in the process of revising some of the material, the material received by the Commission will be used for the examination.
Any material under revision, upon receipt of this letter, must be finalized when the required material is submitted.
- 7. The following training materials shall be provided:
- a. System Descriptions.
System descriptions should include descriptions of all operationally relevant flow paths, components, controls, and instrumentation.
- b. Existing system learning objectives and lesson plans. System training material should draw parallels to the actual procedures used for operating the applicable system,
- c. Complete and operationally useful descriptions of all safety-system interactions.
l d. Where available, Balance-of-Plant system interactions under emergency and abnormal conditions, including consequences of i anticipated operator error, maintenance error, and equipment i failure.
- e. Comprehensive theory material that includes fundamentals in the area l of theory of reactor operations, heat transfer and fluid flow, and ;
specific applications to actual in plant components. '
- Thermodynamics learning objectives and lesson plans.
d Enclosure 1 2 For example, mechanical theory material on pumps should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and systems in which they are installed i.e. , Reactor Coolant pumps, all ECCS pumps, Recirculation pumps, Feedwater pumps, and Emergency Feedwater pumps.
- Reactor theory learning objectives and lesson plans.
For example, Reactor Theory material should include descriptions that draw explicit ties between the fundamentals and actual operating limits followed in the plant i.e., reactor theory material should contain explanations of how principles relate to the actual curves used by operators to verify shutdown margin or calculate and ECP.
- f. Training manuals.
- g. Training material and learning objectives used to clarify and
- strengthen understanding of emergency operating procedures.
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- h. Procedure index (alphabetical by subject).
- i. All applicable reactor operating and safety administrative procedures.
l j. A table of contents for all facility administrative procedures.
- k. All integrated plant operating procedures (normal and general operating procedures).
- 1. Emergency procedures (emergency instructions, abnormal or special procedures).
- m. Standing orders (important orders that are safety-related and may supersede the regular procedure).
- n. Fuel handling and core loading procedures (initial core loading procedures, when appropriate).
- o. Annunciator procedures (alarm procedures, including set points).
- p. Radiation protection manual (radiation control manual or procedure),
- q. Emergency plan implementing procedures.
- r. Technical specifications.
Enclosure 1 3-
- s. Piping diagrams of flow charts,
- t. Instrumentation diagrams of flow charts.
- u. Electrical diagrams of flow charts.
- v. Technical data book and/or plant curve information as used by operators.
- w. Facility precautions, limitations and set points.
- x. Questions and answers prepared by the facility (voluntary by the facility).
- y. ECCS system Surveillance procedures required by Technical Specifications.
- z. The following information on the plant referenced simulator:
- List of all available initialization points.
- List of all present malfunctions with a clear identification number. This list should include cause and effect information and a list of which annunciators are to be initially expected.
- Specifically, for each malfunction, a concise description of l the expected result, or range of results, that will occur upon implementation.
- A description of simulator failure capabilities for valves, breakers, indicators and alarms.
- When the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e. , ability to vary the size of a LOCA or steam leak, or the ability to cause a slow failure of a component such as a feed water pump, turbine generator or major valve. For ,
example, the drifting shut of a main feed water regulating l valve. !
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- A list of modeling conditions or simulator problems that may .
impact the examination, j
- Identification of any known performance test failures not yet I completed.
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4 Enclosure 1 4
- Copies of facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR),
degraded heat removal capacity (PWR and BWR), and containment challenges (BWR).
- Simulator instructor's manual. (voluntary by the facility)
- Description of the scenarios used for the training class.
- 8. Additional material required by the examiners to develop examinations that meet the requirements of these standards and the regulations.
ENCLOSURE 2 Requirements for Administration of Written Examinations Operator-Licensing Branch requirements are:
- 1. A single room shall be provided for complet'ing the written examination.
The-location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination. If necessary,~
! the facility should make arrangements for the use of a suitable room at I a local school, motel, or other building. Obtaining this room is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one candidate per table, with 3 foot spacing between tables. No wall charts, models, and/or other training materials shall be present in the examination room.
- 3. Suitable arrangements are to be made by the facility if the candidates are to have lunch, coffee, etc. These arrangements shall comply with Item 1 above. These arrangements will be reviewed by the examiner and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to provide formal written comments with supporting documentation on the examination and answer key to the chief examiner or to the regional office section chief.
- 5. The facility licensee will provide pads of 8-1/2 x 11" lined paper in unopened packages for each candidate's use in completing the examination.
The examiner will distribute these pads to the candidates. All reference material needed to c.omplete the examination will be furnished by the examiner. Candidates can bring pens, pencils, calculators or slide rules into the examination room and no other equipment or reference material l will be allowed. '
- 6. Only black ink or dark pencils should be used for writing answers to questions.
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ENCLOSURE 3 NRC Rules and Guidelines fer License Examinations During the administration of this examination the following rules apply: 1
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties, j
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions. '
- 4. Print your name in the Llank provided on the cover sheet of the 4 examination. {
- 5. Fill in the d:te on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided fer answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category =" as appropriate, start each category on a new page. write on only one side of the paper, and write "Last Page" on the last cnswer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets' face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature. -)
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- 13. The point value for each question is indicated in parentheses after the l question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer ;
to mathematical problems whether indicated in the question or not. l
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWERS BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
Enclosure 3 2
)
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has l
been completed.
- 18. When you complete your enmination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still ,
in progress, your license may be denied or revoked. !
ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATION ,
- 1. There shall be no review of the written examination by the facility staff before or during the administration of the examination. Followingthp]
administration of the written examination, the facility staff shall be, provided a marked-up copy of the examination and the answer key. ,
- 2. The facility will have five (5) working days from the day of the written..,
examination is given to provide formal comment submittal. The submittal will be made to the responsible Regional Office by the highest levelEof corporate management for plant operations, e.g., Vice President for,1 '
Nuclear Operations. A copy of the submittal will be forwarded to the' chief examiner, as appropriate. Comments not submitted within five'(5) >
working days will be considered for inclusion in the grading process on a case by case basis by the Regional Office section chief. Should the comment submittal deadline not be met, a long delay for finalization of the examination results may occur.
- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and reference,
- b. Facility comment
- c. Supporting documentation NOTES: (1) No change to the examination will be made without submittal of complete, current, and approved reference material.
(2) Comments made without a concise facility recommendation will not be addressed.
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