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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray 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 ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058G2941990-11-0505 November 1990 Advises That Written & Operating Operator & Senior Operator Licensing Exams Scheduled for Wk of 910204 & Requests Listed Ref Matls 60 Days Prior to Exam Date ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant 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 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 ML20055G2951990-07-13013 July 1990 Advises That SALP 9 Presentation Time Changed Due to Commissioner Carr Visit on 900723 ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl IR 05000237/19890181989-09-0808 September 1989 Forwards Safety Insp Repts 50-237/89-18 & 50-249/89-17 on 890715-0828.No Violations Noted ML20246K6121989-08-25025 August 1989 Advises That 890818 Proposed Scope & Objectives for Plant Annual Emergency Preparedness Exercise Scheduled for 891101 Acceptable ML20246D0711989-08-10010 August 1989 Forwards Amends 107 & 102 to Licenses DPR-19 & DPR-25, Respectively & Safety Evaluation.Amends Revise Testing Requirements for Other Sys or Subsystems of ECCS or Standby Gas Treatment Sys When One Sys or Subsystem Inoperable ML20248D6401989-08-0404 August 1989 Forwards FEMA Transmitting Revised Exercise Rept for Sept 1987 Emergency Exercise at Plant.No Deficiencies Noted.Six Areas Requiring Corrective Action Identified.Nrc Expects Util to Devote Attention to Resolving Concerns 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 IR 05000010/19890021989-07-31031 July 1989 Forwards Safety Insp Repts for 50-010/89-02,50-237/89-17 & 50-249/89-16 on 890530-0714 & Notice of Violation ML20245G4591989-06-21021 June 1989 Forwards Notice of Consideration of Issuance of Amend to License DPR-2 Re 860107 Application Concerning Decommissioning Plan & Safstor 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 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 ML20246F9731989-05-0303 May 1989 Advises That Requalification Program Evaluation Scheduled for Wk of 890828.Listed Ref Matl Requirements Necessary 60 Days Prior to Exam Date ML20236B7611989-03-0808 March 1989 Advises That Rev 5b to Plant Emergency Plan Consistent W/ Provisions of 10CFR50.54(q) & Acceptable.Approval of Emergency Action Levels (EAL) Does Not Preclude Additions to Upgraded EALs Resulting from NRC Review of Decommissioning ML20235Z6501989-03-0707 March 1989 Ack Receipt of 890127 Submittal of Rev 54 to QA Topical Rept CE-1-A.Program Continues to Satisfy Requirements of 10CFR50,App B & Acceptable ML20246L7481989-03-0303 March 1989 Confirms 890323 Meeting in Glen Ellyn,Il to Discuss Util Quality Verification Program,Per ML20236A0461989-03-0202 March 1989 Advises That 890228 Rev 26 to Plant Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20235T2541989-02-28028 February 1989 Forwards Safety Insp Rept 50-249/89-04 on 880604-890208 & Forwards Notice of Violation IR 05000237/19890061989-02-28028 February 1989 Forwards Safety Insp Rept 50-237/89-06 on 890123,24,27 & 0214-16.No Violations Noted ML20205J4331988-10-24024 October 1988 Advises That 881023 Rev 25 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20207L5581988-10-0707 October 1988 Advises That 880912 Rev 52 to QA Topical Rept CE-1-A Consistent W/Requirements of 10CFR50,App B & Acceptable ML20154Q4071988-09-27027 September 1988 Forwards Request for Addl Info Re Proposed Tech Specs Changes,Decommissioning Plan & Environ Rept to Delete Authority to Operate Facility ML20153G9491988-08-31031 August 1988 Advises That 880809 Rev 6B to Emergency Plan Consistent W/Provisions of 10CFR50.54(q) & Acceptable ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20151C9871988-07-12012 July 1988 Confirms 880706 Plans Re 880714 Mgt Meeting at Region III to Discuss Plant Performance ML20151E8131988-07-12012 July 1988 Forwards Safeguards Insp Repts 50-010/88-04,50-237/88-16 & 50-249/88-17 on 880628-30.Rept Details & Notice of Violation Withheld (Ref 10CFR73.21) ML20150F9801988-07-0808 July 1988 Informs That 880527 Rev 24 to Security Plan for Facility Consistent w/10CFR50.54(p) & Acceptable.Stated Item Deleted Due to Administrative Error Must Be Returned to Plan.Encl Withheld ML20150D8901988-07-0707 July 1988 Requests Addl Info Re Emergency Plan Requirements for Fuel Storage.Lists Questions Requiring Licensee Response Needed for Evaluation of Emergency Action Levels in Emergency Plan.Rev of Site Emergency Plan Suggested ML20150B4481988-07-0505 July 1988 Forwards Hj Miller 880608 Memo Re Site Visit to Attend Exit Meeting for Insp of Emergency Operating Procedures & to Tour Facility ML20150B8991988-06-23023 June 1988 Forwards Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations. W/O Encl ML20153E8941988-05-0303 May 1988 Forwards Safeguards Insp Repts 50-010/88-03,50-237/88-07 & 50-249/88-08 on 880404-08 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21) ML20151Z9261988-05-0202 May 1988 Advises That Changes to 880418 Revs 49 & 50 to QA Topical Rept CE-1-A Meets Requirements of 10CFR50,App B & Acceptable ML20151Y4951988-04-26026 April 1988 Notifies That Submittals Re Allegations Concerning Use of Poor Matls & Poor Mfg Practices by C&S Valve Co Have Been Reviewed.Util Procedures Re safety-related Purchases in Accordance W/Specs.Allegation Considered Closed ML20147J1891988-03-0404 March 1988 Requests Remittance of Fee for Review of 871222 Application Re Decommissioning Documents for Facility ML20147F2241988-03-0101 March 1988 Advises That Util Released from 870306 Commitment to Provide Equipment out-of-svc List to NRC on Weekly Basis.Amount of Equipment out-of-svc Reduced to Level Consistent W/Good Maint Practices ML20149H9241988-02-12012 February 1988 Commends Dedication & Commitment of Individuals Having Gone Through Rigorous Study & Training for NRC License.Nrc Will Formally Present License Certificates of Newly Licensed Individuals,If Requested ML20149G5261988-02-12012 February 1988 Forwards Pilot Requalification Exam,In Anticipation of Resumption of Requalification Testing Later This Yr.Util Should Review Programs & Manpower Commitments.W/O Encl ML20148G2701988-01-20020 January 1988 Informs That Revs 42-48 of QA Topical Rept CE-1-A Acceptable Per 10CFR50,App B ML20234B8361987-12-31031 December 1987 Responds to Re Scope & Objectives for Plant Exercise Scheduled for 880301.Proposed Objectives Acceptable ML20237D7661987-12-22022 December 1987 Responds to to TE Murley Re Effects of Postulated Dc Power Failure on ECCS Performance for Plants.Compliance W/Requirements of 10CFR50.46 & App K Cannot Be Concluded. Operation of Units During 60-day Period Acceptable ML20237F0571987-12-17017 December 1987 Confirms 880119 Enforcement Conference in Glen Ellyn,Il to Discuss 861128 & 29 Deinerting Events,Per 871204 & 10 Discussions ML20237D3881987-12-11011 December 1987 Summarizes 871117-18 Meeting to Review Performance of Operating Nuclear Power Plants & Related Issues of Greatest Safety Significance.Facility Categorized as Requiring Close Monitoring to Determine Effectiveness of Corrective Actions ML20236X8811987-12-0808 December 1987 Advises That 871125 Rev 22 to Security Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20236V6171987-12-0101 December 1987 Forwards Exam Rept 50-237/OL-87-03 Administered on 871026-30.Exam & Answer Key Encl ML20236W5351987-12-0101 December 1987 Forwards Safeguards Insp Repts 50-010/87-08,50-237/87-34 & 50-249/87-33 on 871026-30 & 1102.No Violations Noted ML20236N5091987-11-10010 November 1987 Ack Receipt of Allegation RIII-87-A-0138 in Which Alleger Expressed Concern Re Plant Fuel Pool.Util Requested to Address Procedures or Practices in Place to Assure Integrity of Fuel Racks in Fuel Pool & Concrete Structure ML20236L1031987-11-0202 November 1987 Forwards Request for Addl Info Re 861126 Application for Amend to Physical Security Plan in Response to Miscellaneous Amends & Search Requirements.Requests Response within 60 Days of Receipt of Ltr 1990-09-25
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety 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) ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given ML20154F6291998-10-0606 October 1998 Forwards Insp Rept 50-010/98-16 on 980723-0918.No Violations Noted.During Period Covered by Insp,Activities in Areas of Facility Mgt & Control,Spent Fuel Safety & Radiological Safety Examined ML20154B6761998-10-0101 October 1998 Informs That NRC Reviewed Comm Ed Submittals & Finds,Util Has Adequately Addressed Actions in GL 95-07,as Discussed in Encl SE ML20153C4941998-09-21021 September 1998 Forwards SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station IR 05000010/19980151998-08-13013 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Issued on 980629.Corrective Actions Will Be Examined During Future Insps ML20237B1321998-08-11011 August 1998 Forwards Corrected Copy of NOV Re Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Conducted on 980601-04.Notice Did Not Contain Safeguards Info.Administrative Error Resulted in Document Being Marked as Safeguards Info ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20236L1151998-07-0606 July 1998 Forwards Insp Rept 50-010/98-13 on 980319-0630.No Violations Noted.Activities in Area of Facility Mgt & Control,Sf Safety & Radiological Safety Were Examined ML20236F1471998-06-29029 June 1998 Forwards Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18 on 980601-0604.Areas Examined within Security Program Were Identified ML20236G9961998-06-26026 June 1998 Forwards Insp Repts 50-237/98-14 & 50-249/98-14 on 980403- 0527.No Violations Noted.Unavailability of HPCI Sys Continued to Be Problem at Dresden During Insp Period ML20249C3121998-06-23023 June 1998 Inorms That Proposed Revision 66 to QA Topical Rept,CE-1-A, Not Acceptable.Requests That Licensee Refrain from Implementing Changes Until Formally Notified ML20248B9431998-05-27027 May 1998 Discusses 980520 Public Meeting Re Dresden Unit 1 Decommissioning Activities & Dry Cask Storage Project. Meeting Handouts Encl ML20247E3061998-05-0808 May 1998 Confirms Discussion W/B Snell Re Agreement to Have Meeting on 980520 at Plant,Training Bldg to Discuss Unit 1 Status & Plans,Problem Identification & Prevention & Dry Cask Storage Status IR 05000010/19980081998-05-0101 May 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-08, 50-237/98-08 & 50-249/98-08.Corrective Actions Will Be Examined During Future Insps ML20216G6311998-04-0909 April 1998 Summarizes 980312 Meeting Conducted at Region III Ofc in Lisle,Il,To Discuss Util Performance Re Action That Util Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance at Facilities.List of Attendees Encl ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217E8191998-03-26026 March 1998 Discusses Review of Dec 1997,rev 7K to Generating Stations Emergency Plan,Submitted Under Provisions 10CFR50.54(q).NRC Approval Not Required,Changes Do Not Decrease Effectiveness of Plan ML20217D5951998-03-25025 March 1998 Forwards Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08 Conducted Between 980302 & 11.Areas within Security Program Were Examined.Nov & Insp Details Being Withheld ML20248L7911998-03-18018 March 1998 Forwards Insp Rept 50-010/98-02 on 971215-980226 & Nov.Rp Program Exhibited Number of Weaknesses.Program Declined Through Most of 1997 Until Control Informal,Personnel Not Well Informed or Disciplined & Mgt Involvement Lacking ML20216B8321998-03-0606 March 1998 Forwards Decommissioning Insp Plan for Remainder of FY98 for Plant,Unit 1,for Info.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability ML20203H9651998-02-26026 February 1998 Confirms Discussion to Have Meeting on 980312 in Lisle,Il to Discuss Comed Nuclear Operating Division Performance as Relates to Actions Comed Taken in Response to NRC Ltr ,re Safety Performance at Comed Nuclear Facilities ML20203B1651998-02-0909 February 1998 Informs That Effective 980209 R Burrows Has Been Assigned as Project Manager for Plant,Unit 1 ML20202H1701998-02-0909 February 1998 Discusses 980114 Meeting W/Listed Attendees in Lisle,Il to Discuss Commonwealth Edison Co Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54(f) Ltr Concerning Safety Performance at Util Facilities IR 05000010/19970241998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-24, 50-237/97-24 & 50-249/97-24.Actions Will Be Examined During Future Insp ML20202C7821998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-19, 50-237/97-19 & 50-249/97-19.Corrective Actions Will Be Examined During Future Insp ML20198T4491998-01-20020 January 1998 Advises of Planned Insp Effort Resulting from Dresden Plant Performance Review.Details of Insp Plan for Next 6 Months Encl ML20198N7181998-01-15015 January 1998 Discusses Conversation Between I Johnson & J Gavula Re Cancellation of Planned Routine Mgt Meeting on 980122 in Lisle,Il ML20197H8761997-12-23023 December 1997 Forwards Insp Repts 50-010/97-26,50-237/97-26 & 50-249/97-26 on 971029 & 1106.No Violations Noted.Noncited Violation Re Failure to Implement FFD Provisions Contained in Plant Procedure Was Identified ML20197G5641997-12-19019 December 1997 Ask Receipt of Ltr Dated 971002,which Transmitted Changes Identified as Rev 56 to Dresden Nuclear Station Security Plan,Submitted Under Provisions of 10CFR50.54(p).Changes Do Not Decrease Overall Effectiveness of Plan ML20197E9681997-12-19019 December 1997 Forwards Insp Repts 50-010/97-24,50-237/97-24 & 50-249/97-24 on 971016-1122 & Notice of Violation ML20203J6481997-12-16016 December 1997 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Will Be Available in PDR ML20203J8091997-12-15015 December 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-20, 50-237/97-20 & 50-249/97-20 on 971030 1999-08-02
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, e MAY 0 31989 Docket No. 50-10 Docket No. 50-237 Docket No. 50-249 Commonwealth Edison Company ATTN: Mr. Cordell Reed Senior Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:
SUBJECT:
REQUALIFICATION PROGRAM EVALUATION In a telephone conversation on May 2, 1989 between Mr. Steve Stiles, Training Coordinator, and Mr. John Bjorgen, Chief Examiner, arrangements were discussed for an evaluation of the requalification program and licensed personnel at the Dresden Nuclear Station. The evaluation visit is scheduled for the week of August 28, 1989.
For this visit, the NRC examiner will administer NRC prepared written and .
operating examinations. The NRC examiners will discuss with the appropriate '
facility personnel and operators the schedule and the process for these examinations. For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved items listed in Enclosure 1, " Reference Material Requirements," at least 60 days prior to the examination date. Mr. Stiles has been advised of our reference material requirements and where they are to be sent.
NRC reserves the right to postpone NRC-administered requalification examinations if the facility generated materials are inadequate for examination preparation.
It is requested that an employee be provided to complete the examination team. The employee shall be an active (per the requirements of 10 CFR 55.53(e) or (f)) SR0 from the Dresden Operations Department. If desired by the facility, and agreed to by the Chief Examiner, an additional employee from the Training Department may be a member of the examination team.
This employee shall preferably be an active (per the requirements of 10 CFR 55.53(e) or (f)) SRO, but may be a facility of INPO certified instructor. These individuals must not be scheduled for an NRC-administered I
examination during this visit, or participate as instructors once selected. l The facility representatives will be required to certify that they did not knowingly compromise any portion of the examination.
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MAY0 3 1989 ,
- Commonwealth Edison Company 3 f .. 1 1
Distribution ,,
cc w/ enclosures: l T. Kovach, Nuclear l Licensing Manager E; D. Eenigenburg, Station Manager DCD/DCB(RIDS)
' Licensing Fee Management Branch Resident Inspector, RIII Richard Hubbard J. W. McCaffrey, Chief, Public Utilities Division S. R. Stiles, Training Manager cc w/o enclosures:
K. E. Perkins, LOLB B. Siegel, Project Manager, NRR J. J. Harrison, Section Chief, DRP l
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l W0 3 1999 Commonwealth Edison Company 2 The facility representatives shall be restricted (1) from knowingly communicating by any means the cortent or scope of the examination to unauthorized persons and (2) from participating in any facility programs such as instruction, examination, or tutoring in which an identified regt.alification examinee (s) will be present. These restrictions shall apply from 60 days prior to the examination date.
The facility management is responsible for providing adequate space and ,
accommodations to properly develop and conduct the examinations. Enclosure 2, '
" Administration of Requalification Examinations," describes our reqisirements for developing and conducting the examinations. Mr. Stiles has also been informed of these requirements. Also, a facility operations management representative (as a minimum, first level above shift supervisor) should observe the simulation facility examination process at the site.
Enclosure 3 contains the "NRC Rules and Guidance for Examinees" that will be in effect during the administration of the written examination. The facility management is responsible fer ensuring that all oper4 tors are aware of these rules. The requalification examinations and the subsequent evaluation of the l facility requalification program will be performed in accordance with ES-601.
This request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1989. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing the required material. Comments on the accuracy of this estimate and suggestions to reduce the burden may be directed to the Office of Management and Budget, Paperwork Reduction Project (3150-0101), Room 3208, New Executive Office Building, Washington D.C. 20503, and the U.S. Nuclear Regulatory Commission, Records and Reports Management Branch, Office of Information Resources Management, j Washington, D.C. 20555.
Thank you for your consideration in this matter, If you have any questions on ,
the evaluation process, please contact Mr. John Bjorgen at (312) 790-5559.
Sincerely, I 0P.IGIIJAU S!GilED BY. GE0i7aEY C. Vlabi Geoffrey C. Wright, Chief Ope ations Branch
Enclosures:
- 1. Reference Material Requirements
- 2. Administration of Requalification Examinations
- 3. NRC Rules and Guidance for Examinees See Attached Distribution II III orgen/ib g
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ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS l
- 1. For the written examination, the following items must be provided to the NRC !
60 days prior to the examination date:
Proposed R0 and SRO requalification examination test items. (A minimum of 350 per section of the examination, or the 30 questions per month based from August 1988.)
Since the written examination is open reference, examination items must meet the following:
- a. Items that require only memorization or recall are not permitted;
- b. Items should require that the examinee comprehend, interpret, integrate, or apply available information;
- c. Items ~should contain situations, aspects, or conditions that do not duplicate lesson plans or references; and
- d. Items should reqaire examinees to locate and use references.
l The written examination will be composed of two sections, each designed to be completed in 1-1/2 hours. Each section will be separate.
Section A will be administered on a static simulator; Section B will be administered in a classroom setting. Section A is designed to evaluate the operator's knowledge of plant systems, integrated plant operations, and instrumentation and controls. In addition, recognition of Technical Specification LCOs and the operator's ability to diagnose postulated events should be evaluated. Section 8 of the written examination is designed to evaluate the ability of the operator to analyze a given set of conditions and determine the proper procedural and/or administrative guidance.
- 2. All reference material and objectives for the proposed test items.
For the simulation facility, the following items must be provided to the NRC 60 days prior to the examination date:
- a. A minimum of 15 scenarios i The scenarios should sample areas such as LERs, emergency and l abnormal procedures, and design and procedural changes that exercise the crew's ability to use facility procedures in accident preventicn and mitigation. The scenarios should evaluate each crew member as appropriate to his/her license, and shall exercise their abilities in the use of Emergency Operating Procedures, Technical Specifications, and the Emergency Plan. The scenario's net time (not including time spent on briefings, setup or simulation facility problems) should average 50 rinutes, based upon real time performance.
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Enclosure 1 2 i
For the plant walkthrough examination, the following items must be provided to the NRC 60 days prior to the examination date:
(1) A list of systems and topics appropriate to the plant walkthrough examination that were covered during the requalification cycle l and are important to safety. All reference material required :
to support an examination on these topics should be provided.
(2) Seventy-five (75) job performance measures.
These performance measures should be both in plant and control room operater functions, that are required for the safe operation of the facility. They shall include acceptable performance crit (ria. l (3) Any additional reference material required for examination- ,
l preparation will be requested by the examination team. !
- 3. A sampling plan shall be provided by the facility which indicates the relative emphasis of topics which were included in the most recent l requalification training cycle. t f
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ENCLOSURE 2 1
ADMINISTRATION OF REQUALIFICATION EXAMINATIONS l l
- 1. Twenty percent of the facility licensed operators snall be selected for ;
evaluation. Normally the crew currently in the requalification cycle will be selected. A random sample without replacement will be used to preclude a satisfactory operator from being subject to re-examination by the NRC'during the term of the license. The sample will include other !
shift (s) made up of licensed personnel who are not routinely performing shift duties.
- 2. The simulator and a simulator operator (s) will be provided for examination development. The date(s) and duration of time needed to develop the examinations will be agreed upon by the chief examiner and the facility.
- 3. The reference material used in the simulator will be reviewed by the ;
chief examiner. No material will be used that is solely used for !
training.
- 4. A single room shall be provided for completing Section B of the written examination. The location of this room and supporting rest room facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the examination.
- 5. Minimum spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one examinee per table, with a 3 foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination rN m.
- 6. Copies of reference material for Section 8 of the written examination will be provided for each examinee. The reference material will be reviewed by the chief examiner and will consist of Technical Specifications, operating /
abnormal procedures, administrative procedures, and Emergency Plans as available to the plant operators. '
- 7. Video taping capabilities can be utilized. The facility should contact the chief examiner for restrictions related to its usage.
- 8. Since common tasks and detailed systems knowledge will be probed during the walkthrough portion of the operating test, operators will be requested not to discuss the wzlkthrough with other examinees until after the complete examination has been administered.
- 9. An attempt will be made to distinguish between R0 and SR0 knowledge and abilities, to the extent that such a distinction is supported by the facility training materials.
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' ENCLOSURE 3 NRC RULES AND GUIDANCE FOR EXAMINEES
- 1. Use black ink or dark pencil DNLY to facilitate legible reproductions.
- 2. Print your name in the blank provided on the cover sheet of the examination.
- 3. Fill in the date on the cover sheet of the examination, if necessary. .
- 4. Answer each question on the examination. If additional paper is required, use only the lined paper provided by the examiner.
- 5. Use abbreviations only if they are commonly used in facility literature.
- 6. The point value for each question is indicated in parentheses after the ;
question and can be used as a guide for the depth of answer required. I
- 7. Show all calculations, methods, or assumptions used to obtain an answer ,
to a mathematical problem whether asked for in the question or not. '
- 8. Unless solicited, the location of references need not be stated.
- 9. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.
- 10. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
- 11. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
- 12. Rest room trips are to be limited and only one examinee at a time may i leave. You must avoid all contact with anyone outside the examir.ation room to avoid even the appearance or possibility of examination compromise.
- 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 14. Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section for a total of four hours.
- 15. Due to the existence of questions that will require all examinees to refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
i Enclosure 3 2
- 16. When you are finished and have turned in your completed examination, leave the examination area.
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth-0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
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