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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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J1)l,f31987 l 1
l 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-
Dear Mr. Reed:
SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. Steven Styles, Training Supervisor, and Mr. Gregory M. Nejfelt, Nuclear Regulatory Coiumission, on July 15 and 16,1987 arrangements were made for the administration of examinations at the Dresden Nuclear Power Station.
The written and oral examinations are scheduled for the week of October 26, 1987, In order for us to meet this schedule, it will be necessary for the facility 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 advance with considerable planning to best utilize our limited examiner manpower and to meet the examination dates requested by the various facilities.
Therefore, missing the deadline, even by a few days, will likely result in a ;
long delay since it may not be possible to reschedule examinations at other facilities. Mr. Styles 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.
The facility management is responsible for providing adequate space and accommodations in order to properly conduct the written examinations.
Enclosure 2, " Administration of Reactor / Senior Reactor Operator Licensing j Written Examinations," describes our requirements for conducting these ;
examinations. Mr. Styles has also been informed of these requirements.
In aduition, to better document simulator examinations, the chief examiner !
will nave the' facility simulator operator record prespecified plant ;
conditions (i.e., plant pressure, temperature, pressurizer level, ecc.), !
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 j B707300gog g79,gg -
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JUL 2 81987 l Commonwealth Edison Company 2 i taking the examinatfor. have either passed the operating examination or all appeals filed by the candidates who failed the operating examination have been completed.
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 awars of these Rules.
All reactor operator and senior reactor operator license applications l should normally be submitted at least 60 days prior to the first l examination dates so that we will be able to review the training and !
experience of the candidates, process the medical certifications, and !
prepare flnal 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.
This request for information was approved by the Office of Management !
and Budget under Clearance Number 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 Writte;1 Examination." Mr. Styles 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
, Gregory H. Nejfelt at (312) 790-5528.
Sincerely,
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Charles W. Hehl, Chief Operations Branch
Enclosures:
i 1. Reference Material Requirements l for Reactor / Senior Reactor Operator Licensing Examinations l
- 2. Requirements for Administration of Written Examinations,
- 3. NRC Rules and Guidelines For '
License Examinations
- 4. Facility Review Requirements See Attached Distribution RIII RIII RIII RIII VFI b
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.cc w/ enclosures:
D. Butterfield,'-Nuclear ~
~ Licensing Manager LJ. Eenigenburg,. Plant l Manager o DCS/RSB (RIDS): .
Licensing Fee Management Branch l Resident Inspector,.,RIII-Richard:Hubbard ._.
.J. W. McCaffrey,. Chief,'Public l
. Utilities-Division '
LS. Styles, Plant' Training Supervisor
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J~ 'cc w/o' enclosures: . . .
M.'Grotenhuis, Project. Manager,LNRR:
J. N.-Hannon, Branch Chief, OLB Mr A. Ring, Section Chief, DRP R..W. Cooper,'NRR ,
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[ _ ENCLOSURE 1 Reference Material Requirements for Reactor / Senior Rcartor Operator Licensing Examinations
- 1. Existing learning objectives and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.).
Training materials should include all substantive written material used for preparing candidates for initial R0 and SR0 licensing. The i written material should be inclusive of learning objectives and the details-presented during lecture, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed.
Failure to provide complete preperly bound and ino2xed plant reference mater ial will result in canceling and rescheduling of the examinations. Training materials which include the following sN;0d be provided:
- System descriptions including descriptions of all operationally relevant flow paths, components, controls, and instrumentation. ;
System training material should dray parallels to the actual procedures used for operating the applicable system.
- Complete and operationally useful descriptions of all 3 safety-system interactions and, where available, B0P syste.n interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
- Training material used to clarify and strengthen understanding of emergency operating procedures.
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- Comprehensive theory material'that includes fundamentals in {
the area of theory of reactor operation, thermodynamics, heat transfer and fluid flow, as well as specific application to
. actual in plant components. 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 the systems in which they are installed (i.e.,
Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps, Feedwater pumps, and Emetgency Feedwater pumps). Reactor Theory material should include descriptions that draw explicit ties between the fundamentals and the actual operating limits followed in the plant (i.e. , reactor theory material should contain explanations how principles relate to the actual curves
'used by cperators to verify shutdown margin or calculate an ECP).
- 2. Procedure Index (alphabetical by subject).
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[ 3. jA11l administrative' procedures (as applicable to reactor operation or' safety).
- 4. . All Lintegrated plant procedures -(normal or general operating . ]
- procedures). j .
- 5. Emergency procedures (emergency instructions, abnormal or specfal _i procedures). i 1
- 6. , Standing orders-(important orders that are safety related and.may i supersede the regular procedures). '
. 7. Fuel-handling and core-loading procedures, (initial,coresloading
' i procedure, when appropriate). ;
, 8. Annunciator proceduces (alarm procedures, including set points), a
- 9. ' Radiation protection manual (radiation control manual.or procedures).
- 10. Emergency plan' implementing procedures.
~11. Technica1 Specifications.
,a 12.' ' System operating procedures.
'13; Piping'and instrumentation diagrams, electrical single-line diagrams,
.c .or flow diagrams.
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- 14. Technical. Data Book,'and/or. plant curve information as used by i operators and facil-ity precautions, limitations, and set points (PLS) for the facility.
- 15. Questions and answers that licensee has prepared (voluntary by licensee). .
- 16. The following on the plant reference simulator:
a.- . List of all readily available initialization points.
- b. List of all preset malfunctions with a clear identification number. The list-should include cause and effect information. !
. Specifically, for each malfunction a concise description of j the expected result, or range of.results, that will occur upon implementation should be provided. Additionally, an indication i of which annunciators are to be initially expected should be l given.
- c. - A~ description of simulator failure capabilities, for valves, !
breakers, indicators and alarms.
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I d, Where the capability exists, an explanation of the ability to j vary the severity of a particular malfunction should be ;
provided,. i.e. , ability to vary the size of a given LOCA or j steam leak, or the ability to cause a slow failure of a 1 component such as a feed pumps turbiae generator or major valve !
(e.g.,-drifting shut of a main feedwater control valve).
- e. An indication of modeling conditions / problems that may impact I the examination. j
- f. Identification of any known Performance Test Failures not yet completed.
- g. Identification of significant differences oetween the simulator !
and the control room.
- h. Copies of' facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR) and containment challenges (BWR) .
may be provided,
- i. Simulator instructor's mariual.
- 17. Additional material required by the examiners to develop examinations :
that meet the requirements of these standards and the regulations. '
< .DTS 8134, Unit 2(3) Shutdown Margin Demonstration DTS 8471, General Procedures for Fuel Transfers Involving the Reactor DOS 800-3, Source Range Instrumentation Response During Refuelirg DOS 800-1, Refueling Interlock Check DIP 260-1, Refuel Wide Range Reactor Level Instrumentation DOS 700-6, SRM Functional Test Prior to Core Alterations DTS 300-6, Control Rod Drive Friction Test Commonwealth Edison Nuclear Procedures DTS 8473, Duties of the Control Room Nuclear Observer ;
Appendix A, Unit 2(3) Operator's Daily Surveillance Log DIS 700-3, SRM Rod Block Calibrating Check ,
DOS 800-6, Surveillance of the 2/3 Reactor Building Crane Prior to Operation in Restricted Mode j Dresden Safe Shutdown Procedures j Lesson plans on emergency procedure basis Copies of facility prepared scenarios I
The above reference material should be approved, final issues and should i be.so marked. If a plant has not finalized some of the material, the :
chief examiner shal? verify with the facility that the most complete, up-to-date material is available and that agreement has been reached with ,!
the licensee for limiting changes before the administration of the examination. All procedures and reference material should be bound with appropriate indexes or tables of contents so that they can be used efficiently.
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, L 'EN' CLOSURE ' 2 '
Requirements for Administration of
~ Written Examinations Operator Licensing Branch requirements are:
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- 1. A single room shall be provided for' completing the written examination.
The ~ location:of. this . room and supporting -restroom facilities shall be-such as to prevent contact with'a11'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-a local school, motel, lor other building. 0btaining this room-is the'
(. responsibility of the. licensee.
Minimum; spacing is required tr ensure examination integrity as' determined
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& 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.
- o. =3s Suitable arrangements are to be made by the facility'if the candidates-L cre 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 fact 11'ty staff shall be provided a copy of the written examination and answer key after the last candidate.has completed and handed in his =
wr'itten 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 complete 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
.will be allowed.
- 6. Only black ink Lor dark pencils should be used for writing answers to questions.
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ENCLOSURE 3 l
NRC Rules and Guidelines for License Examinations l During the administration of this examination the following rules apply:
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- 1. Cheating on the examination means an automatic denial of your application l and could result in more severe penalties. '
- 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. 1
'3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the )
examination. '
- 5. Fill in the date on the cover sheet of the examination (if necessary). !
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each sectinn 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 answer 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.
I i 11. Separate answer sheets from pad and place finished answer sheets face
( down on your desk or table. ,
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- 12. Use abbreviations only if they are commonly used in facility literature.
- 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.
1 1 14. Show all calculations, methods, or assumptions used to obtain an answer l to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWERS SLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
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- 17. -You must' sign lthe 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 1 been. completed. ' '
>18. ~ When you complete your' examination, you shall:
- a. Assemble your examination ~as follows:
(1) . Exam questionso'n top.
l (2) ' Exam aids - figures, tables, etc.
(3) Answer.pages including figures which are a part.of the answer.
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- 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.
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ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATION j i
- 1. There chall be no review of the written examination by the facility ctaff before or during the administration of the examination. Following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key.
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- 2. The facility, will have five (5) working days frem 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 level of corporate management for plant operations, e.g., Vice President for Nuclear Operatinns. 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.
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- 3. The following format should be adhered to for submittal of specific commeats:
'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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