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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E0451990-11-13013 November 1990 Discusses 901106 Meeting Re Alternative Tube Plugging Criteria for Facility Steam Generators ML20062D6911990-11-0909 November 1990 Forwards SER Re Response to Generic Ltr 88-11 Concerning NRC Position on Radiation Embrittlement of Reactor Vessel. Compliance w/10CFR50,Appendix G,For Min Upper Shelf Energy Could Not Be Verified.Operation for 16 EFPY Acceptable ML20058F7931990-11-0606 November 1990 Forwards Summary of NRC Understanding of Current Status of Unimplemented Generic Safety Issues for Plant,Per Util 900627 Response to Generic Ltr 90-04 ML20058B4021990-10-19019 October 1990 Forwards Summary of 900913 Mgt Meeting Re Emergency Preparedness Program & Onsite Technical Support Ctr ML20058B1391990-10-16016 October 1990 Forwards Insp Repts 50-348/90-28 & 50-364/90-28 on 900911-1012.No Violations or Deviations Noted ML20058B2581990-10-12012 October 1990 Ack Receipt of 900807 & 0904 Ltrs Transmitting Objectives & Scenario Package for Exercise Scheduled on 901024 ML20062B7031990-10-12012 October 1990 Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20062C6601990-10-0909 October 1990 Ack Receipt of 900913 Response to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19 ML20059N6721990-10-0909 October 1990 Responds to Util 900702 Request for Authorization to Use ASME Boiler & Pressure Vessel Code Case N-395.Request Acceptable IR 05000348/19900181990-10-0909 October 1990 Ack Receipt of 900926 Response Re Violations Noted in Insp Repts 50-348/90-18 & 50-364/90-18 ML20059N3481990-09-24024 September 1990 Forwards Insp Repts 50-348/90-24 & 50-364/90-24 on 900827-31.No Violations or Deviations Noted ML20059K1311990-08-28028 August 1990 Confirms Mgt Meeting on 900913 to Discuss Timeliness of Activation of Emergency Response Facilities ML20059B3421990-08-23023 August 1990 Advises That Util 900131 Response to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations,Satisfactory ML20059H0921990-08-23023 August 1990 Forwards Insp Repts 50-348/90-20 & 50-364/90-20 on 900711-0810.No Violations or Deviations Noted ML20056B3721990-08-21021 August 1990 Forwards Order Imposing Civil Monetary Penalty in Amount of $450,000 Re Violations,Per 870914-18,1102-06 & 16-21 Insps. Violations Include Failure to Demonstrate Splice Qualification & Failure to Maintain Environ Qualification ML20058M9441990-08-0303 August 1990 Forwards Insp Repts 50-348/90-19 & 50-364/90-19 on 900711-13 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21) ML20058P8661990-07-31031 July 1990 Forwards Insp Repts 50-348/90-21 & 50-364/90-21 on 900709-13.No Violations or Deviations Noted ML20055H4251990-07-13013 July 1990 Forwards Insp Repts 50-348/90-16 & 50-364/90-16 on 900611-0710.Violations Noted,But Not Cited ML20055H6501990-07-13013 July 1990 Forwards Insp Repts 50-348/90-17 & 50-364/90-17 on 900618-22.No Violations or Deviations Noted IR 05000348/19900121990-07-10010 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12.Part (a) of Violation Agreed with Denial & Withdrew This Portion & Revised Records Accordingly ML20059M8061990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3961990-02-23023 February 1990 Forwards Insp Repts 50-348/90-04 & 50-364/90-04 on 900129-0202.No Violations or Deviations Noted ML20248B0201989-09-18018 September 1989 Forwards Summary of 890912 Mgt Meeting in Region II Ofc Re Configuration Mgt Program & Findings of self-initiated Safety Sys Assessment of Svc Water Sys.List of Attendees & Meeting Agenda Also Encl ML20247K0821989-09-15015 September 1989 Forwards Amend 8 to Indemnity Agreement B-81,reflecting Revs to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Increasing Liability Insurance ML20248C2061989-09-15015 September 1989 Advises of Special Emergency Operating Procedure Insp Program Being Performed at Plant on 891127-1208 to Verify That Procedures Technically Accurate & That Actions Can Be Accomplished W/Equipment,Controls & Instrumentation ML20247G9511989-09-12012 September 1989 Forwards Insp Repts 50-348/89-18 & 50-364/89-18 on 890731-0804 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21) ML20247G5401989-09-12012 September 1989 Forwards Insp Repts 50-348/89-19 & 50-364/89-19 on 890821-25.No Violations or Deviations Noted.Licensed Operator Performance During Simulator Training Did Not Meet Expectations ML20247G6611989-09-0707 September 1989 Confirms 890906 Telcon W/J Garlington & D Verrelli Re Mgt Meeting Scheduled for 890912 in Region II Ofc to Discuss Results of Licensee self-initiated Safety Assessment ML20247F4881989-09-0606 September 1989 Ack Receipt of Responding to Violations Noted in Insp Repts 50-348/89-13 & 50-364/89-13.Implementation of Corrective Actions Will Be Examined During Future Insps ML20246N7041989-08-25025 August 1989 Forwards Insp Repts 50-348/89-17 & 50-364/89-17 on 890724-28.No Violations or Deviations Noted ML20246P3561989-08-17017 August 1989 Forwards Insp Repts 50-348/89-16 & 50-364/89-16 on 890711-31.No Violations or Deviations Noted ML20246G3921989-08-11011 August 1989 Confirms Util Participation in NRC Regulatory Impact Survey on 890911,per 890808 Telcon.Agenda Encl ML20245K5571989-08-0909 August 1989 Advises That 890601 Rev 16 to Emergency Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20245H9851989-08-0303 August 1989 Requests Responses to Encl Questions Re Requests for Relief from ASME Code Requirements of Second 10-yr Inservice Insp within 45 Days of Ltr Receipt ML20245H1201989-08-0202 August 1989 Requests That Encl Ref Matls Be Furnished to NRC by 890825 for Requalification Program Exam Scheduled for Wk of 891023 ML20248C8061989-08-0101 August 1989 Forwards Insp Repts 50-348/89-10 & 50-364/89-10 on 890424-27 & 0508-12 & Notice of Violation.Unresolved Item Identified ML20247R9781989-07-28028 July 1989 Forwards Final FEMA Rept on 881102 Emergency Response Exercise.Identified Deficiency Promptly Corrected.Resolution of Weaknesses,Identified by Fema,Should Be Corrected Prior to Next full-scale Emergency Preparedness Exercise ML20247R5141989-07-26026 July 1989 Forwards Insp Repts 50-348/89-13 & 50-364/89-13 on 890509-10 & Notice of Violation.Fact That Two Independent Actions Involving Unauthorized Use of Radioactive Matls Occurred within Short Time Indicates Disrespect for Radioactivity ML20245F1971989-07-26026 July 1989 Forwards Insp Repts 50-348/89-14 & 50-364/89-14 on 890611-0710.No Violations or Deviations Noted.Matter Re Apparent Excessive Work Hours for Licensed Operators Will Be Discussed W/Util at 890731 Meeting in Region II Ofc ML20247E2691989-07-20020 July 1989 Forwards Exam Rept 50-348/OL-89-01 Administered During Wks of 890619 & 26.Concerns Noted Re Operator Performance & Exam Admin.Concerns Will Be Discussed at 890731 Mgt Meeting at Region II Ofc IR 05000348/19890111989-07-18018 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-11 & 50-364/89-11 ML20246L8101989-07-13013 July 1989 Forwards Antitrust Settlement Notice Submitted for Fr Publication ML20246B2391989-06-27027 June 1989 Forwards Insp Repts 50-348/89-12 & 50-364/89-12 on 890511-0610.No Violations or Deviations Noted ML20246B0051989-06-16016 June 1989 Forwards Insp Repts 50-348/89-11 & 50-364/89-11 on 890411- 0510 & Notice of Violation ML20245G3171989-06-13013 June 1989 Requests Completion of Radiochemical Analyses of Liquid Samples Spiked W/Radionuclide within 60 Days of Receipt of Samples ML20245A8551989-06-13013 June 1989 Forwards SER Supporting Util 831104 & 850422 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20245F5031989-06-13013 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-07 & 50-364/89-07 ML20248A1751989-06-0202 June 1989 Ack Receipt of 890407 Response to Violations Noted in Insp Repts 50-348/89-03 & 50-364/89-03.Violation Occurred as Stated in Notice of Violation.Written Statement Describing Corrective Actions Requested.Encl Withheld (Ref 10CFR2.790) ML20247L6451989-05-25025 May 1989 Requests That Licensee Follow Instructions of 890328 Order & Either Request Hearing or Submit Payment of Civil Penalty Re Operation of Safety Injection Pump W/Gas from Crossover Piping.Hydrogen Accumulation Discovered on 880226 Not 06 ML20247L4481989-05-25025 May 1989 Comments on Licensee 881229 Response to Generic Ltr 88-17 W/Respect to Expeditious Actions for Loss of Dhr.Response Appears to Meet Intent of Ltr But Lacks Details for Listed Items 1990-09-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20206R4741999-05-13013 May 1999 Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC ML20206M2321999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created ML20206G7341999-05-0404 May 1999 Forwards Safety Evaluation Re Completion of GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206G2411999-04-30030 April 1999 Forwards Revised RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Farley.Requests to Be Notified of Rev to Original Target Date of 990521 ML20206R2031999-04-29029 April 1999 Forwards Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted ML20205T1931999-04-0909 April 1999 Informs That on 990316,J Deavers & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Farley NPP for Y2K.Initial Exam Dates Are Wks of 000508 & 22 for Approx 12 Candidates.Chief Examiner Will Be C Ernstes ML20205Q1541999-04-0606 April 1999 Forwards Insp Repts 50-348/99-09 & 50-364/99-09 on 990308-10.One non-cited Violation Identified ML20205M2831999-04-0202 April 1999 Forwards Errata Ltr for Farley Nuclear Power Plant FEMA Exercise Rept.Page 19 of Original Rept Should Be Replaced with Encl Corrected Page 19 ML20196K4881999-03-19019 March 1999 Forwards Insp Repts 50-348/99-01 & 50-364/99-01 on 990110- 0220.One Violation of NRC Requirements Occurred.Violation Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20205A2611999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Farley Plant Performance Review on 980202.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20204C9561999-03-17017 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Plant,Units 1 & 2.Response Requested by 990521 ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207M2181999-03-11011 March 1999 Advises That Info Contained in 990125 Application CAW-99-1318 & Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20207M1991999-03-0808 March 1999 Partially Withheld Info Re Meeting Held on 990129 at Region II Ofc in Atlanta,Ga to Discuss Physical Protection Measure for Svc Water Intake Structure Located at Facility (Ref 10CFR73.21).List of Attendees Encl ML20206U1831999-02-0909 February 1999 Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed ML20203G5541999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 940407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203G3921999-02-0202 February 1999 Forwards Insp Repts 50-348/98-08 & 50-364/98-08 on 981129- 990109 ML20199L4451999-01-25025 January 1999 Forwards for Review & Comment Revised Draft Info Notice Re Inservice Testing of A-4 Multimatic Deluge Valve for Farley NPP Units 1 & 2.Informs That Comments Submitted on 981120 Were Reviewed & Incorporated Where Appropriate ML20199K7351999-01-21021 January 1999 Responds to 981123 Request by Providing Copy of Latest Draft of Info Notice Being Prepared Which Discusses Failure of Several Preaction Sprinker Sys Deluge Valves.Requests Submittal of Comments by 981120 ML20199K7231999-01-20020 January 1999 Confirms 990119 Telcon Re Informational Meeting Scheduled for 990129 to Be Held in Atlanta,Ga to Discuss Security Related Issues at Plant.Meeting Will Be Closed to Public,Due to Sensitive Nature of Issues ML20199D8541999-01-12012 January 1999 Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20199C9361999-01-0808 January 1999 Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted ML20198S2741999-01-0606 January 1999 Informs That Staff Reviewed SG 90-day Rept, Farley Unit 2 1998 Voltage Based Repair Criteria 90 Day Rept, & Found Assessment to Be Acceptable.Staff Review Encl 1999-09-09
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ARANTA.GEoRotA 30303 JUN 2 91981 7
Alabama Power Company
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L-9 ATTN: Mr. R. P. Mcdonald i
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Vice President-Nuclear Generation i
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Gentlemen:
Subject:
Docket Nos. 50-348 and 50-364 t
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Immediately following the accident at Three Mile Island, the Nuclear Regulatory Commi'ssion installed a nationwide Emergency Notification System (ENS or System) to facilitate notification to the NRC of events and conditions at licensed nuclear power plants.
The ENS is a dedicated telephone system connecting selected nuclear facilities to the NRC Operations Center. The ENS currently in use experiences a number of operational problems including false rings, lack of circuit assurance indication, and reduced voice quality when multiple extensions are in use. A system modification has been developed by the NRC and AT&T to overcome these difficulties and, additionally, to provide ringing in the Resident Inspector's office when the ENS circuit is activated by licensee personnel. This modification will be installed and provided by the NRC.
In order to facilitate scheduling of the system upgrade, the NRC needs informa-tion on logistic support which will be available at licensed activity sites prior to actual implementation of the upgrade.
In addition, NRC staff members wish to coordinate the planned actions to upgrade the system with appropriate licensee telecommunication planning personnel. Accordingly, licensees are requested to notify, by written response, Mr. Stuart Cohen, USNRC, Office of Administration, Telecommunications Branch, Washington, D.C. 20555, as soon as possible but no later than August 1, 1981, of the availability of the following logistic support (further details are contained in the two enclosures):
o timely access for telephone company representatives to make a site survey and subsequently for installing station packages for the upgrade; o
power for the station packages; o
adequate cable facilities (cable pairs);
telecommunications planning personnel to serve as primary contacts during o
the modification; o
a listing of each existing and proposed ENS station location based on generic name (e.g. Control Room, TSC, EOF, and Resident Office), building name and address, room number (NOTE: Stations not identified by the NRC as required in Enclosure 1 may be removed or not installed);
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1 Alabama Power Company 2
indication of any planned station moves or installation to be completed at o
the time of the ENS modification; indication of any temporary ENS station locations and the expected date and o
building / room number for relocation to permanent locations; indication of anticipated problems in meeting a system upgrade start date of o
approximately August 1, 1981.
NRC will schedule actions to upgrade the ENS on a priority basis for those _
facilities where support is available and will coordinate closely with licensee contact personnel in resolving problems where the support is not planned to be available at the beginning of the upgrade implementation. outlines in greater detail the nature of the upgrade and also the support facilities, which-the NRC Staff presently considers necessary to implement the proposed changes in the ENS.
A graphical representation of the configuration of the ENS upgrade is in Enclosure 2.
In view of the upgrade modification of the ENS, changes to the current ENS configuration should be held to an absolute minimum until the proposed upgrade is actually implemented. Requests for modifications to the current system confi-
.guration should be accompanied by a detailed justification and forwarded to the NRC Regional Office. Such modifications may be approved at the discretion of the NRC.
For your information, the NRC staff is developing a recommendation to revise NRC regulations to require use of the ENS as the primary means of reporting events and conditions specified in 10 CFR Part 50.72. This is already current practice.
This information collection is authorized by law under Section 161 of the Atomic Energy Act of 1954, as amended. While you are not required to respond, your cooperation is needed to facilitate the upgrade of the ENS to make it a more reliable system.
Note: The reporting requirement 3 contained in this letter have been approved by the Office of Management and Budget; OMB Approval No. 3150-0068 expires December 31, 1981.
Should you have any questions concerning this matter, please contact G. T. Gibson (404-221-4178) of my staff.
Since'ely, i h,.f d-t
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James P. O'Reilly Director
Enclosures:
(See Page 3) 4
Jun 2.o 1581 4.;
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' Al'abama Power Company 3
Enclosures:
1.
ENS Specifications 2.
ENS Upgrade Configuration cc w/ encl:
W. O. Whitt, Executive Vice President F. L. Clayton, Jr., Senior Vice President H. O'. Thrash, Manager-Nuclear Generation
- 0. D. Kingsley, Jr., Manager, Nuclear Engineering and Technical Services J. W. McGowan, Manager-Operations Quality Assurance W. G. Hairston, III, Plant Manager W. C. Petty, Manager-Quality Assurance (Design and Construction)
R. E. Hollands, Jr., QA Supervisor e
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ENCLOSURE 1 SPECIFICATIONS FOR PROPOSED UPGRADING OF THE EMERGENCY NOTIFICATION SYSTEM A.
Station Locations: ENS stations are to be located as follows:
Power Plants Control Room Shift Supervisor's Office (Optional)
Technical Support Center (TSC)
Emergency Operations Facility (E0F)
Resident Inspector's Office Specific locations may vary due to site-specific conditions. The primary loca-tion at each power plant is the Control Room.
The station package for the Control Room ENS will normally serve the TSC and may serve other extensions.
This station package also serves the auxiliary packages for the site.
It is designated the Main Control Package and is described in further detail in a subsequent paragraph.
B.
Facility, Cable and Wiring:
1.
Facilities: A four wire facility (two cable pairs) will interconnect the serving Central Office to the main control package on site.
An additional two cable pairs will interconnect the main control package to each onsite and offsite auxiliary package.
2.
Station Wiring: Six cable pair will interconnect with package (main or auxiliary) with each station.
One additional wire will support each station equipped with an alarm or monitoring system (spokesman). This cable is to be terminated on a 25 pin amphenol connector.
C.
Capacities:
1.
Main Control Package:
To insure maximum system integrity, the main control package should be' installed in the same building, and as close as possible, to the Control Room's ENS instrument.
A maximum of four stations can be fed off this package.
Extension stations are limited to a cable distance of 100 ohms or approxi-mately 1,000 feet from the main control package.
Typical stations--Control Room (s), TSC, Shift Supervisor's Office.
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Auxiliary Packages (except ALT EOF):
A maximum of four stations can be fed by each auxiliary package:
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Normally, stations shou 1d be within 1000 ohms or 10,000 feet of main control package.
3.
Emergency Operations Facility (EOF or ALT EOF):
A maximum of three stations can be fed off this package.
No resistance or distance limits.
D.
Physical / Hardware Considerations:
1.
Main Control Packages:
Equipment will be encased in an apparatus cabinet (16C case). '
Dimensions: 18 inches high 9h inches deep 26 in:hes wide Weight: approximately 80-90 lbs.
2.
Auxiliary Packages -- EOF, Resident Inspector's Office, alternate or interim EOF:
Equipment will be encased in an apparatus cabinet (16C case).
Dimensions: 18 inches high 9 inches deep 26 inches wide Weight: approximately 50 lbs.
E.
Power:
1.
The upgrade equipment cannot be powered at any licensed facility by the telephone company central office and requires access to local power.
2.
Main control package:
Two 110 volt, 60 cycle, 4 amp, A/C power a
outlets.
3.
Auxiliary packages: One 110 volt, 60 cycle,1 amp, A/C power outlet.
4.
Protective Power: The Main Control Package will be located as near as feasible to the Control Room and will be served with critical power of the same reliability as the Control Room itself. All other packages
1
-Enclosure 1 3
will be provided reliable power to the same degree as the facility which they. support. No ENS station can cperate unless the Main Control Package and (where applicable) the Auxiliary Package serving that station has power. Therefore, the power reliabi.lity, including back-up systems, should be the same _ for each ENS station package' as for the continued operation of the facility itself.
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EMERGENCY NOTIFICATION SYSTEM UPGRADE SAMPLE CONFIGURATION (TSC) - TECHNICAL SUPPORT CONTROL AEOF (EOFI - EMERGENCY OPERATIONS FACILITY REMOTE l (AEOF)-ALTERNATE EMERGENCY OPERATIONS FACILITY AUX (Ills) - RESIDENT INSPECTOR SERVICE
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-J SouthCentralBell May 19, 1981 Mr. Johnny Vann Gra Ceba Telephone Company P. O. Box G Ashford, Alabama 36312 De~ar Johnny:
Attached is c letter and memorandum from AT6T Long Lines requesting information on prospects for upgrade of service at Farley Nuclear Plant for the Nuclear Regulatory Commission.
Our office has already discussed this request with you via telephone.
Please furnish us the information by letter as soon as possible so that we may notify Long Lines by May 29, 1981 of your capability to furnish this service and any possible restrictions you may have.
If you have any questions, please call us at 321-8744.
Yours very truly, sistant St ff Ma ager Attachments Copy to:
Mr. Bill Wall Genera 1 Telephone Company m
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J. P. McQuillan 1120 20th Street, N.W.
Washington, D.C. 20036 Manager DOE, NRC EPA, National Accounts (202)457 3620 May 11,.1981 Ms. Marilyn Cope Bell Independent Relations South Central Bell 1706 2nd Avenue N., Room 301 Birmingham, AL 35202
Dear Ms. Cope:
Our purpose in writing is tri-fold:
1.
To determine Gracebo Tel Co's ability to implement a non-standard arrangement in an interval of approximately 3 1/2 months.
2.
To assess local facilities and make appropriate persons in your company aware of cable requirements.
3.
To suggest a prompt order, directly to the manufacturer, (Wescom Inc.) to expedite supply and allow your installation force adequate time.
The Nuclear Regulatory Commission (NRC) has ordered an upgrade to their existing two point " hotline" network, called " Emergency Notification System." This upgrade will employ specially designed station equipment to improve and enhance the service of this 72-circuit system.
These circuits represent a critical link between each nuclear power plant or fuel facility and the NRC Operations Center, Bethesda, Maryland.
This network is no.t only the first line in ' defense of public safety, but represents a long-term revenue source with high growth potential for our companies.
This project alone will return $750K in first year
- revenue, o
NRC must satisfy budgetary constraints by charging the initial costs for this upgrade to the current fiscal year's allocations.
Therefore, installation must complete by the end of September, 1981. We feel sure you will support our efforts to meet. our responsibility -to provide quality service and protect a $1.35M network.
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May 11. 1981 z4
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The following circuit (s) are within your area of responsibility:
GP01490 Please respond by May 29, 1981.
The above mentioned information is necessary before an eqinitable and valid USO can be issued In the event Gracebo Tel Co. is unable to participate in this project please consider a joint effort with South Central Bell and inform me as to your decision.
We are willing to assist, in ary way necessary, to ensure a successful implementation.
Yours veEy'truly, J
P. McQuillan, Manager E, NRC, EPA - National Accounts Attachments (2) e l
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MEMORANDUM FOR (Federal Government)
FROM:
P. Tavormina, LL MA-NRC Account Project #9044 NRC Network Upgrade RE:
Circuit (s): GP01490 SSO f: 3961-1750 I.
Major Enhancements:
SF tone-on in idle Elimination of the need for constant A.
condition thereby eliminating false rings.
frequency handshake of B.
Circuit assurance is provided by a
one at each circuit location.
the two control packages; Failure of the circuit produces visual / audible alarms at each point.
l-Ability to have multiple of f-hook stations without degrading C.
transmission.
D.
Special lighting and ringing patterns for power plant stations.
stations with full indication.
E. Ability to have off-site 1-II.
Engineering Consideration:
A. Circuits will require four-wire local loop, four-wire on-site cabling, and four-wire tel sets.
(See Attached should be red, without Diagram)
Sing-le lines tel sets rotary dial or touch-tone pad.
e B.
Twelve-leads are required between any package and tel set.
f acilities associated with the C.
Duplication of all on-siteis desirable wherever possible to minimize above circuits, This would allow for switching back to old system down time.
if problems arise.
facility status to D.
Stevens, NAEM as soon Please report
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Project Information A.
Long Lines:
1.
Pat Tavormina, Market Administrator (202) 457-3545 2.
Don Stevens, NAEM (703) 691-6263 3.
Bob Koontz, ISC (202) 479-5189 B.
WESCOM, Inc. (Downer's Grove, Illinois) 1.
Marlene Willemsen, Project Coordinator (312) 985-9000 X2323 2.
Bob Ptasek, Engineer (312) 985.-9000 X2318 Note:
- Please order direct from WESCOM, M. Willemsen.
At least one spare card for each type used on-site is re-quired.
Tariff charges were developed to comoensate local companies for their investment.
Spare cards are necessary to maintain and repair equipment within an acceptable response time.
- Due dates have been scheduled so that the Silver Spring Plant Control Office can offer technical assistance and perform complete tests.
Changes in these dates will impair the PCO's ability to perform these functions by unbalancing the work-load.
Please accept dates assigned whenever possible.
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