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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 ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff 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 ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 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) ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted 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 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20210E0501999-07-22022 July 1999 Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed 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) ML20209H5171999-07-15015 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129 ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20209F6931999-07-13013 July 1999 Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J4711999-06-30030 June 1999 Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2 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 ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E0201990-11-0909 November 1990 Forwards Safety Insp Repts 50-373/90-21 & 50-374/90-22 on 900902-1020 & Notice of Violation ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20059N7431990-10-0404 October 1990 Confirms 901012 Mgt Meeting at Region III Ofc to Discuss Util Corporate & Site Engineering Organizations 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 ML20059E8091990-08-31031 August 1990 Forwards Safety Insp Repts 50-373/90-20 & 50-374/90-21 on 900820 & 22-24.Violation Noted But Not Cited ML20059E6391990-08-30030 August 1990 Forwards Safeguards Insp Repts 50-373/90-18 & 50-374/90-19 on 900813-17.Violations Noted,But Not Cited ML20059N0291990-08-22022 August 1990 Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping IR 05000373/19900081990-08-16016 August 1990 Confirms 900821 Meeting in Glen Ellyn,Il to Discuss Findings in Insp Repts 50-373/90-08 & 50-374/90-09.Util Should Include Status of Radwaste Tank Room Repair & Cleaning Project Addressed in Insp Repts 50-373/90-13 & 50-374/90-14 ML20059A5921990-08-14014 August 1990 Advises That 900806 Rev 34 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable 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 ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20056A8611990-07-31031 July 1990 Forwards Safety Insp Repts 50-373/90-14 & 50-374/90-15 on 900603-0717.No Violations Noted ML20055D8061990-06-29029 June 1990 Forwards Safety Insp Repts 50-373/90-11 & 50-374/90-11 on 900514-0613.No Violations Noted ML20055E0701990-06-28028 June 1990 Forwards Safety Insp Repts 50-373/90-05 & 50-374/90-06 900605-08.No Violations Noted.One Exercise Weakness Identified ML20055D9721990-06-28028 June 1990 Forwards Mgt Meeting Repts 50-373/90-13 & 50-374/90-14 on 900530 & Notice of Violation.Meeting to Discuss Radiological Conditions Caused by Overflows in Radwaste Tank Rooms,Plans for Decontamination & Corrective Actions Taken ML20055D2401990-06-27027 June 1990 Forwards Safety Insp Repts 50-373/90-12 & 50-374/90-13 on 900611-13.No Violations Noted.Exemption Granted from Conducting Type a Test During Each Refueling Outage Until Two Consecutive Tests Satisfy App J Acceptance Criteria ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3821990-02-27027 February 1990 Requests Addl Info on Licensee Application for Amend Under Generic Ltr 87-09.Amend Based on Assumption That Remedial Measures Provide Sufficient Level of Protection to Permit Operational Mode Changes & Safe long-term Operation ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248A2191989-09-21021 September 1989 Forwards Safety Insp Repts 50-373/89-19 & 50-374/89-19 on 890725-0911 & Notice of Violation ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247K8861989-09-15015 September 1989 Forwards Safety Insp Repts 50-373/89-20 & 50-374/89-20 on 890808-31.No Violations Noted ML20247N1901989-09-15015 September 1989 Confirms 890914 Discussion Between W Morgan & DE Jones Re Meeting on 891006 in Glen Ellyn,Il to Discuss Util Analysis of 890826 Scram ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246H7341989-08-28028 August 1989 Confirms 890928 Meeting in Seneca,Il to Present SALP 8 Rept for Util.Encourages Util to Have Appropriate Plant Mgt Representation ML20246J3211989-08-28028 August 1989 Forwards SALP Repts 50-373/89-01 & 50-374/89-01 for Period 880316 - 890630 ML20246K6971989-08-25025 August 1989 Forwards Safeguards Insp Repts 50-373/89-16 & 50-374/89-16 on 890605-0807.No Violations Noted ML20246H0521989-08-23023 August 1989 Forwards Requalification Exam Rept 50-373/OL-89-02 on 890801-04 for Units 1 & 2 ML20246G3091989-08-21021 August 1989 Forwards Safety Insp Repts 50-373/89-15 & 50-374/89-15 on 890801-03 & App Describing Exercise Weaknesses.Planned Actions to Correct Weaknesses Should Be Submitted within 45 Days of Ltr Date ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20245F9091989-08-0909 August 1989 Discusses Util Response to Violation Noted in Insp Repts 50-373/87-27 & 50-374/87-26 Re Fire Protection Program Requirements.Analysis Viewed as Deviation from License Commitment 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 ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245E8701989-08-0303 August 1989 Forwards Safety Insp Repts 50-373/89-17 & 50-374/89-17 on 890610-0724 & Notice of Violation ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20245J5471989-08-0202 August 1989 Forwards Exam Repts 50-373/OL-89-01 & 50-374/OL-89-01 Administered During Wk of 890619-24 ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20246D6151989-06-30030 June 1989 Forwards Safety Insp Repts 50-373/89-14 & 50-373/89-14 on 890523-0616 & Notice of Violation ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20245K7911989-06-28028 June 1989 Forwards Maint Team Insp Repts 50-373/89-10 & 50-374/89-10 on 890501-05,15-19 & 25 & Notice of Violation.Insp Team Conclusion That Maint Satisfactorily Performed & Effective Noted.Weaknesses Discussed ML20245J6741989-06-26026 June 1989 Forwards Corrected Amends 66 & 47 to Licenses NPF-11 & NPF-18,respectively,correcting Typos ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245K5051989-06-23023 June 1989 Requests Addl Info Re All Valves Addressed by BWR Owners Group in NEDC-31322 within 1 Month ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245C2061989-06-20020 June 1989 Grants Util Request for Relief from Notification & Reporting Requirememts of Bulletin 86-002, Static O-Ring Differential Pressure Switches. Util Should Continue to Investigate Each Failure & Document Investigation in Deviation Rept 1990-09-25
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted ML20210E0501999-07-22022 July 1999 Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed 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) ML20209H5171999-07-15015 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129 ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted ML20209F6931999-07-13013 July 1999 Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses ML20196J4711999-06-30030 June 1999 Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2 ML20195B6031999-05-24024 May 1999 Ack Receipt of Which Transmitted Changes Identified as Rev 60 to LaSalle Nuclear Station Security Plan,Submitted Per Provisions of 10CFR50.54(p) ML20206U3641999-05-19019 May 1999 Confirms Plans to Conduct Routine Mgt Meeting on 990630 in Lisle,Il Re Recent Plant Performance & Lessons Learned from Unit 2 Restart ML20206T0081999-05-19019 May 1999 Forwards Insp Repts 50-373/99-03 & 50-374/99-03 on 990401-0512.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations.One Violation Re Two Operators Failure to Log Suppression Pool Temp as Required ML20206S5291999-05-14014 May 1999 Forwards Insp Repts 50-373/99-10 & 50-374/99-10 on 990419-23.Violation Noted:Nrc Determined That Previously Unresolved Item Involving Failure to Adequately Implement fitness-for-duty program,non-cited Violation ML20206K7401999-05-0303 May 1999 Informs That as Result of April 1999 Senior Mgt Meeting, LaSalle Identified as Routine Oversight Plant.Summary of NRC Discussion Related to LaSalle Listed.Meeting Scheduled for 990506 to Discuss Latest Meeting of NRC Senior Managers ML20206G7511999-05-0303 May 1999 Forwards Insp Repts 50-373/99-09 & 50-374/99-09 on 990406-09.No Violations Were Identified.Insp Focused on Actions Recently Taken to Identify Common Causes for Previously Identified Programmatic Radiation Staff Problems ML20206G6631999-05-0303 May 1999 Forwards Insp Repts 50-373/99-07 & 50-374/99-07 on 990329- 0402.NRC Determined That Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205S8101999-04-20020 April 1999 Forwards Insp Repts 50-373/99-08 & 50-374/99-08 on 990311- 26.No Violations Noted.Overall,Insp Results Indicated That Unit 2 Mods Properly Installed & That Plant Matl Condition of Unit 2 Acceptable ML20205R4171999-04-16016 April 1999 Forwards Summary of 990406 Meeting Re Readiness for Restart of Plant,Unit 2 & Dual Unit Operation & Recent Plant Performance Review Issued by NRC ML20205R5461999-04-16016 April 1999 Forwards Insp Repts 50-373/99-02 & 50-374/99-02 on 990217- 0331.Non-cited Violation Re Failure of Operator to Follow Procedure Which Resulted in Surveillance Procedure Acceptance Criteria Being Evaluated ML20205J2381999-04-0505 April 1999 Submits Summary of 990322 Meeting with Util to Discuss Experiences & Performance of Plant Since Startup of Unit 1 Status of Matl Condition & Unit 2 Outage.Associated Meeting Summary & Handouts Provided by Util Encl ML20205D6971999-03-29029 March 1999 Discusses Insp Repts 50-373/98-17 & 50-374/98-17 & OI Rept 3-98-015 Completed on 981119 & Forwards Nov.Apparent Deliberate Violation of NRC-required Comed Fitness for Duty Program Noted ML20205D5801999-03-29029 March 1999 Refers to Insps 50-373/98-17 & 50-374/98-17 & Subsequent OI Investigation 3-98-032 Into Info Reported to NRC by Comed on 980518,that Deliberate Violation of NRC-required FFD Program May Have Occurred at LaSalle & Forwards NOV ML20205G5411999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990204 to Develop Integrated Understanding of Safety Performance. Overall Performance at Plant Improved as Discussed.Insp Plan & Plant Issues Matrix Encl ML20205A6411999-03-25025 March 1999 Refers to Investigation Conducted by OI (Investigations Rept 3-1998-028) to Determine If Employment Discrimination Occurred After Contract Worker Raised Radiation Safety Concerns Re Plant.Synopsis from Subj Rept Encl ML20204J8411999-03-24024 March 1999 Submits Summary of 990226 Meeting Re Performance of LaSalle Since Startup of Unit 1,status of Matl Condition of LaSalle & Status of Unit 2 Outage.List of Attendees & Matl Used Encl ML20205A6211999-03-24024 March 1999 Discusses 990226 Mgt Meeting with Util Re Performance of LaSalle Since Startup of Unit 1,status of Matl Condition of LaSalle & Status of Unit 2 Outage.Associated Meeting Summary & Handout Provided to NRC by Util Encl ML20204J7021999-03-22022 March 1999 Confirms Plans to Conduct Mgt Meeting on 990406 at Mazon Emergency Operations Facility to Discuss Readiness for Restart of Unit 2 ML20204E0751999-03-18018 March 1999 Discusses Review of Rev 6M to Portions of Plant Emergency Plan Site Annex ML20207J8901999-03-10010 March 1999 Forwards Insp Repts 50-373/99-01 & 50-374/99-01 on 990106- 0216.No Violations Identified.Personnel Errors Occurred During Insp Period.Overall Performance of Plant Personnel Acceptable ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203C9811999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 59 to Security Plan.No NRC Approval Required ML20203A1981999-02-0202 February 1999 Forwards Insp Repts 50-373/98-23 & 50-374/98-23 on 981121-990105.No Cited Violations Identified.Two Equipment Problems Identified During Shutdown for Planned Outage Were Not Effectively Addressed to Preclude Problem Recurrence ML20198N4531998-12-18018 December 1998 Confirms Plans to Conduct Routine Mgt Meeting on 990119 at Mazon Emergency Operations Facility to Discuss Lasalle,Unit 1 Performance & Status of Lasalle,Unit 2 Restart Activities ML20198E9281998-12-17017 December 1998 Forwards Insp Repts 50-373/98-22 & 50-374/98-22 on 981010- 1120.No Violations Noted.Overall Performance of Plant Personnel Was Acceptable ML20198F2891998-12-16016 December 1998 Forwards Insp Repts 50-373/98-25 & 50-374/98-25 on 981102-06.No Violations Noted.Insp Was Evaluation of Operator Workaround Program ML20198B3741998-12-14014 December 1998 Forwards SE Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20197H3561998-12-0404 December 1998 Final Response to FOIA Request for Docments.Records in App a Encl & Will Be Available in PDR ML20198B1531998-12-0202 December 1998 Forwards Insp Plan for Next 6 Months & Plant Issues Matrix. Info Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite ML20196F7361998-12-0202 December 1998 Informs That Document GE-NEDC-31531P,Suppl 1, ARTS Improvement Analysis for Lscs,Units 1 & 2,Removal of Direct Scram Bypassed Limits, Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) 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 1999-09-08
[Table view] |
Text
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NOV 2S 1"5 q
.}
Mr. Larry W. Duchek
'(
-{ Commonwealth Edison Company
.~ Mazon EOF j Q] 960 North Route 4T 5 p a., u !
i Morris, Illinois 60450 j; _j ii 4
)
Dear Larry:
1 ,
.l I want to thank you for agreeing to meet with myself and our contractor to discuss the technical aspects of setting up an Emergency Response Data System .{j
.i
.i (ERDS) with your facilities. As I explained in our conversation, the intent of I
] this effort overall is to provide us with a detailed understanding of the )'
q availability of the data we desire, the potential for transmitting the data to
- us, and the hardware and software necessary for use to handle the data. For-d your information, I have enclosed three documents which describe: the person-A nel and reference material we need access to; a sample of our questions on the parameters; and our computer and telecommunications information needs. I m
.j We are attempting to make this data collection effort complete anough so that
- j no subsequent trips to any site will be necessary and that we obtain sufficient 3 information to implement the system should we do so. Therefore, as discussed, f
- i we will plan on arriving at your downtown corporate offices at 9
- 00 a.m. on
! December 2,1985 to obtain as much information as possible at that location. A 3 determination will be made while we are there as to whether or not travel to l
'j the sites is necessary. I l )
{ Should you have any concerns or question please call me at (301)492-4155.
Sincerely, i i
- John B. Hickman
! Incident Response Branch
! Division of Emergency Preparedness 1 and Engineering Response 1 Office of Inspection and Enforcement 1
j
Enclosure:
As stated J,
2
{ Distribution:
1 IRB R/F e
j T. McKenna K. Perkins a
1 i *See previous concurrence d
IR8:DEPER:IE IRB:DEPER:IE IRB:DEPER:IE
] .
4
- J8Hickman: ams *TMcKenna *KEPerkins j
.i 11/26/85 11/26/85 11/26/85 !
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.i
} ATTACHMENT 1
't _
' .f 'L ~ O PERSONNEL AND REFERENCE MATERIAL
'.) v lb fiii !
lij It is recognized that the key disciplines necessary to support El the ERDS survey will represent different departments and ;
organizational relationships unique to each utility surveyed l i)i (e . g. , Corporate vs. Plant Site Engineering staff). It is j
- 3 believed that most of the appropriate personnel will be the j
?.j i same as those on the project teams for SPDS and Emergency l 1 Response Facility Data Acquisition System development. !
l 1
!l The appropriate utility manager to coordinate the ERDS site
.l survey is likely to be the same individual who is responsible l j. for SPDS, RG1.97 or ERF upgrade programs. The approximate lj man-hours for each site survey are based on a 2 to 2b day .
Lj survey for a single unit site or a 2 unit site where both units are identical and a common Data Acquisition System has been installed at a common TSC or EOF.
))
1 Personnel
-! Approximate
'e Person or Discipline Man-Hours Required V ~
D ERDS Survey Coordinator 8 - 12
- NSSS System Expert 4-6 i
Plant I&C Expert 2-4 Computer Hardware Expert (for ERDS signal source (s)) 4-6 1
]
~i Computer Applications Expert 4-6
- Emergency Planning Coordinator 1/2 - 1
- Telecommunications Expert 2-4 u Meteorologist or Environmental Engineer 1/2 - 1 Radiological Monitoring System Expert 1 RG1.97, RVLIS, SMM Instrument Expert 1 J
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j1 ib a It is understood that many of the areas of expertise listed above may be represented by a single individual. (e.g. , One I&C engineer may be able to address instrument characteristics and display conventions for RVLIS, SMM, Radiological, and
}h i
Meteorological 1 instruments).
3 lj Reference Material II -
FSAR o
Any locally generated Plant Data Book (Compilation of I N. System Design Data)
] 1
[
Systems Training Manuals i
!j -
Tables or graphs for engineering unit conversion (e.g.,
4 feet to gallons for_ containment sumps)
Data System Design documents and block diagrams a
Hardcopy printouts of Data Acquisition System displays 4 i l1 Ik n
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l ATTACHMENT 2
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la 1
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] This attachment consists of three samples from the parameter-specific section of the ERDS survey instrument. The three 1
i1 samples are as follows:
a Pi !
14 '
Generic Checklist: This four page checklist is repeated
" .for each of the 29 PWR parameters and 25 BWR parameters.
d Some questions in the checklist do not apply to every-
'l parameter (e.g., questions on engineering unit conversion d factors would not be applicable to parameters such as Hot (j Leg Temperature which is always expressed in' degrees i Farenheit).
]
~
Parameter-Specific Checklist for Atmospheric. Stability-p (applicable to both PWRs and BWRs) .
R
!l
- Parameter-Specific Checklist for BWR Low' Pressure Coolant i
I' Injection Flow ii y $.') m 3
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.i GENERIC CHECKLIST:
l 1. Is this parameter available as a digital signal at the
.3,.J preferred host location, the pickoff point determined in Appendix 1, Section 2?
ij .
i e
m A. If not, what is best alternative host location?
a, I.
it i.3 2. At the host location, is this" parameter available as a b
processed signal (i.e. validated, averaged, range checked, etc.) or only as one or more unprocessed discrete signals?
P
- ] 3. Describe the following attributes of the instruments supplying i either the discrete data points or the inputs to the processed
'! variable:
3 A. Sensor type?
.: 4
. =
B. Instrument failure mode for:
- 1. Loss of power (offsite & onsite AC, but static inverter
- battery systems survive); does the control room
.i
., instrument display survive?):
1
- 2. Instrument in test?
1
,1 1 i l ll
- 3. If instrument is placed in test, does the preferred host location recognize instrument in test?
)
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- I C. Numbar of coparato locations conitored (i.o. Icop 1, loop j -
2, loop 3, etc)?
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D. How many ranges of instrumentation are provided for each l) 1 location monitored?
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- A E. For each of these ranges, describe instrument range
- 1 1 i! 1
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- j F. Reference point of each instrument range (e.g. BWR level; 1 ref. to bottom head or feedwater sparger or steam separator shroud; PWR RVLIS; etc.)? .
. J.m l 'i,)
.1 1
G. Number of instruments within each range for each location fj monitored (e.g. PWR loop 2; Th; 2 NR & 1 WR etc.)?
-i
, .l.
u
-j H. For those cases where data does not read out at the host W location in final required units, what is the engineering conversion factor for each range (i.e. tank' level measured J l in feet, factor to convert to gallons)?
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NOTE: If convorcion fcctor 10 not c oinplo cenotant, ycu c y rGquire a copy of the curve. (For example, in the case .
of an irregularly shaped RWST tank where level data is ,
j provided in feet, you must obtain a copy of the tank {
~
capacity to gallons).
curve to allow the ERDS system to convert levels
- }
] Not applicable.
. .l j
, Conversion is a constant, value is:
j l
Conversion is not a constant, curve attached.
Conversion is not a constant, curve not required or
.. not obtained.
H -
1 H 1 i
il' 1. Engineering units for each range? ,
r)
- l 4.
-I If parameter is a processed value, describe the following
-}
attributes arrive at of how the above instrument inputs are processed to a single value:
i 1 b
A.
Does the processed variable take inputs from more than one
.; j_~,
instrument range?
K: 1 t
l.
If yes, then describe method used to switch between
, ranges.
- t,
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.! i 54 B. For each range of the parameter available, identify the Q instruments whose signals are combined to provide the
'j processed parameter?
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. C. Dacerib2 tho validction ochsca used for renga chseking" lj
error checking and averaging the input parameters?
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1 PARAMETER: ATMOSPHERIC STABILITY
.~s SPECIFIC CHECKLIST:
li (O U IF THE SITE EMPLOYS MORE THAN ONE METEOROLOGICAL TOWER FOR l} 1.
l] REASONS OF TERRAIN (AS OPPOSED TO REDUNDANCY), THEN COLLECT THE DATA BELOW FOR BOTH TOWERS. j ljl t i U
'l ii i4 '
1 ij
!j!
, 2. WHAT IS THE LOCATION OF EACH OF THE TOWERS WITH RESPECT TO THE '
j PLANT POWER BLOCK?
It i
i d' i il l lj 3. WHAT IS THE HEIGHT OF THE LOWER TEMPERATURE DETECTOR? j
\a '
1
- 4. WHAT IS THE HEIGHT OF THE UPPER TEMPERATURE DETECTOR?
l+
1 i
1
.l
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- 5. WHAT IS THE DISTANCE IN METERS BETWEEN THE LOWER AND UPPER TEMPERATURE DETECTORS? >
- .3 T
l
'l 6. DOES THE HOST COMPUTER CONVERT THE DELTA T INTO A DEGREES 5! CENTIGRADE PER 100 METERS VALUE? ;
1 ,
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PARAMETER: BWR - LPCI FLOW
- (
SPECIFIC CHECKLIST:
i -
l 1. HOW MANY TRAINS OF RHR ARE AVAILABLE?
l
.m r g%
-.v .e :)
j 2. HOW MANY RHR PUMPS PER TRAIN?
i
- i s
s
']
- 3. WHAT IS THE DESIGN CAPACITY OF EACH RHR PUMP 7 .
f
- 4. WHAT IS THE SHUTOFF HEAD OF THE RHR PUMPS?-
1
] .?
- 5. WHAT IS THE TOTAL DESIGN RHR FLOWRATE IN THE LPCI MODE?
4
..q 1
1 t? 6. IS THE RER SYSTEM SHARED WITH ANOTHER UNIT? .
( -
A. IF So, DESCRIBE LINEUP?
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g* .
2 J ATTACHMENT 3 i
OVERVIEW OF COMPUTER AND i TELECOMMUNICATIONS SYSTEM INFORMATION NEEDS d
l1 l1 13 o
p iJ it j Computer Systems Related
- The computer systems related portions of the survey instrument focus on the following general areas of investigation
1
- Characterization of each utility computer system that is p, a potential data feeder to ERDS:
-- its hardware and system sof tware environment its data communication technical details 14 1 - Characterization of the potential siting locations for j tlRC-provided hardware.
A l' -
Characterization of the documentation available that ll describes the plant-specific details of the engineering II ,
evolution of a parameter value (as it travels from a b (s'j sensor through analog and digital logic and computer systems to a reactor operator's eyes) .
J Telephony Related i
i The telephony-related portions of the survey instrument focus H on the following general areas of investigation:
1 j - Characterization of potential site-related engineering ri dif ficulties associated with the utility providing a l.j dial-up phone line accessible to, and suitably configured
'./, for, the NRC provided ERDS computer hardware.
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