Similar Documents at Perry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20217E7111999-09-30030 September 1999 Documents Telcon Conducted on 990929 Between M Underwood of Oh EPA & D Tizzan of Pnpp,Re Request to Operate Pnpp Sws,As Is,Until Resolution Can Be Obtained ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 ML20210Q7981999-08-10010 August 1999 Informs That Intention to Utilize Sulfuric Acid in Pnpp Circulating Water Sys to Lower Ph Is Anticipated to Be Completed in Nov ML20210Q5831999-08-10010 August 1999 Requests Permission to Chemically Treat CWS for Algae Due to Cooling Water Basin Becoming Infected with Algae of Various Types PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records PY-CEI-NRR-2404, Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology1999-06-0707 June 1999 Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology ML20195E4561999-05-25025 May 1999 Submits Petition Per Other Actions Provision of 10CFR2.206,requesting That Radiation Protection Manager at Perry NPP Be Banned by NRC from Participation in Licensed Activities at & for Any NPP for at Least Five Yrs PY-CEI-NRR-2401, Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars1999-05-20020 May 1999 Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars PY-CEI-NRR-2402, Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs,1999-05-18018 May 1999 Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, PY-CEI-NRR-2394, Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested1999-05-0505 May 1999 Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested PY-CEI-NRR-2397, Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.51999-04-30030 April 1999 Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.5 PY-CEI-NRR-2396, Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-en1999-04-28028 April 1999 Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-end Weld 05000440/LER-1999-002, Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available1999-04-26026 April 1999 Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available PY-CEI-NRR-2388, Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits1999-04-22022 April 1999 Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits PY-CEI-NRR-2371, Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted1999-04-21021 April 1999 Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl PY-CEI-NRR-2392, Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette1999-04-19019 April 1999 Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette PY-CEI-NRR-2387, Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 1051999-04-14014 April 1999 Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 105 PY-CEI-NRR-2386, Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing1999-04-0606 April 1999 Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20206N3361999-04-0505 April 1999 Informs NRR of Continued Events Re Transfer of Generation Assets Between Duquesne Light Co & Firstenergy.No Negotiated Settlement Between Firstenergy & Local 270 Pertaining to Generation Asset Swap Has Been Reached PY-CEI-NRR-2384, Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC1999-04-0101 April 1999 Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC PY-CEI-NRR-2383, Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed1999-04-0101 April 1999 Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed L-99-052, Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding1999-03-30030 March 1999 Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding ML20205H6171999-03-29029 March 1999 Forwards Util Consolidated Financial Statements for Twelve Month Period Ending 981231 & Internal Cash Flow Projection, Including Actual 1998 Data & Projections for 1999 PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) PY-CEI-NRR-2380, Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure1999-03-25025 March 1999 Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure 1999-09-09
[Table view] |
Text
-
a J. p*"*; ,
CENTERf0R
. ENERGY D
- PEGRY NUCLEAR POWER PLANT il Mdress:
Michael D. Lyster
' 10 CENTER ROAD ' PERRY, OHIO 44081 VICE PRESIDENT NUCLEAR PERRY, OHIO 44081 (216) 259 3737 -
October 22, 1991 PY-CEI NRR-1401 L U.S. Nuclear Regulatory Commission
- Document-Control Desk Vashington, D.C. 20555 Perry Nucle'.r Power Plant Docket No. 50-440 ERDS Implementation Program Plan Pursuant to 10CFR50, Appendix E Gentlemen
-This letter satisfies the requirement to submit an implementation program plan for' linking _the Perry Nuclear Power Plant (PNPP) Unit 1, to the NRC's Emergency Response Data System (ERDS) pursuant to 10CFR50 Appendix E, Section VI.4.a.
Perry's ERDS Implementation Plan is contained in Attachment 1. Attachment 2 contains the completed questionnaire from NUREG-1394, Rev. 1, for the Perry Plant.
Preliminary review indicates that the Perry-Nuclear Power Plant-can
- provide the majority of the requested-parameters, with the exceptions of Dryvell/ Containment Oxygen Concentration (by design, Perry's containment is not inerted) and Intermediate Range Nuclear Instruments. However, the data is distributed _on two computer systems which would be heavily utilized during (Emergency Events. :A satisfactory solution vill require hardware modifications E _vhich have been factored into the implementation plan.-
In addition, we have factored Perry's 1992 Refuel Outage into the schedule, as
- vell as allotted _ time for modifying the Emergency Response Instructions and
._ Software. Control Procedures, and for training Emergency Response personnel' prior;to. final implementation of ERDS at Perry. Nevertheless, adherence to the proposed JRDS Implementation Plan schedule contained in Attachment 1 is necessarily' dependent on the NRC staff and its ERDS contractor with respect to ~
timely reviev and approval of Perry's Data. Point Library (DPL) and Plant Attribute Library (P- :, once submitted, and timely completion of ERDS acceptance testing.
l C110290408 911022 0 lPDR ADOCK 05000440 l F- PDR t k
Ocercerg Co%c es C ewed figf ac Nmw ~g TMc Ed san
4 Document Control Desk PY-CEI/NRR-1401 L October 22, 1991-Our point of contact for ERDS, as provided in Attachment 2, is Mr. Keith J. Nelson. Mr. Nelson can be reached by telephone at (216) 259-3737 ex:ension 5687. If you have any questions, please_ feel tree to call.
Sincerely,
/ , 1 Michael D. L ter MDL:CJftse Attachment-cc NRC Project Manager NRC Resident-Inspector Office NRC Region III C.-E. Norelius, NRC Region III
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kJ; ,
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d Attachment l' PY-CEI/NRR'1401 L-
.Page 1 of 1-1 PERRY NUCLEAR POWER PLANT IMIT 1
.i ERDS IMPLEMENTATION SCHEDULE
- Milestone Completion. . Milestone Description Date:
, l November 15,(1991- Engineering Design Change Request
<Jr (EDCR) for hardware modifications -
submitted to Perry Nuclear Engineering ~ "
Department for' review and approval.
-December 15, 1991 - Data Point Library-(DPL) and Plant--
- Attribute Library _(PAL) submitted to
- NRC and to NRC contractor.
7
' April 1,L1992: Design Change Package (DCP) completed .
- (hardware modifications installed).
l September 30, 1992 Utility and NRC contractor software tready-for' testing.
+
October.15, 1992 Preliminary transmission testing..
October 30D 1992: . Emergency Response Instruction changes ,
and' Software Control'ProcedureLehanges-
, subs.itted foriproject review and
' approval.-
, g November.130,fl992 Finalntest.
i '
g December-15,71992 Procedure changes and Emergency .
-personnel trainingfcomplete and'ERDS F
P ON-LINE.
n 1
,- i h
SC/ CODED /3181 _
L 4
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PY-CEI/NRR-140i L Attachment 2
.. APPENDIX B Pane I of 10 -
. ERDS COMMUNICATIONS DESCRIPTION AND SURVEY QUESTIONNAIRE ne following is a questionnaire pertaining to the Nuclear Regulatory Commission's (h7C)
Emergency Response Data System (ERDS). It consists of a series of questions concerning plant 1/0 points, software protocols, data formats, transmission frequencies, and other plant com-puter specific information to be used in the ERDS computer databas: files. Also, included hpigi are desenptions and examples of data streams that the NRC la expecting to see transmitted over the communication line. %
Re purpose of collecting the data is to develop a plant specific database that will be retrieved into the ERDS once the system is activated by a utility. It will also be used to design and imple-ment ERDS software that can receive the utility's data transmission. In essence, this informa-tion will provide the basis for building a profile of the plant in the ERDS database.
In some cases, the 1/0 point data may be distributed over several computers.ne EROS consid-ers this situation a multi feeder site and Section IV must be filled out for each feeder.
(
B-1 I
PY-CEI/NRR-140 i L Attachment 2 -
'Page 2 of 10 ...
- 1. Contacts .t Note: Please provide name, title, mailing addrosa, and phone number.
A. Survey Coordinator (i.e., contact for later clari5 cation of questionnaire answers) -
Keith J. Nelson - (216) 259-3737 ext. 560/
Ccmputer Engineer - d Mail Stop SBB30 P.O. Box 97- '".
Perry, Ohio 44081 B. Computer Hardware Specialist (s)-
Clint Weirich (216) 259-3737 ext. 5263 Cmputer Engineer Mail Stop SBB30 P.O. Box 97 Perry,. Ohio 44081 C. Systems Software Specialist (s):
Keith J. Nelson D. Application level Software Specialist (s)-
Keith J. Nelson
. E. ~ Telephone Sysams Specialist (s)-
Sharon Flaning (216) 259-3737 ext. 5553 Telecomunications Asst.
Mail Stop S210 P.O. Box 97 Perry, Ohio 44081 B-2
l'Y-CEI/NRR-1401 L
- Attachment.2 II. ERDS Ccmmunications Descripti:n l'88e 3 of 10 3 y *
.,' A. Hanbrare De following hardware will be supplied:
- for a single feeder site:
Codex 2234 modem - V.22 2400 bps, asynchronous, auto-dialing, auto-answer, .
error correcting, using the AT command set j
- for a multiple feeder site:
Codex 6015 multiplever, Codex 2260 modem V32 9600 bps, asynchronous, auto-dialing, auto-answer, error-correcting, using Sie AT command set he modems are intended to be operated in the auto reliable link mode (referred to as MNP in the modem manuals)nith speed conversion and flow control enabled. Speed conversion allows the computer to communicate with the modem at a baud rate which is independent of the baud rate the modem is using to communicate with the remote modem, his feature is important C because the modems have the ability to adjust their transmission rate downwaid if the remote modem is operating at a lower speed. However,in order to use speed conversion, the site com-puter must support some form of flow control.Bree types of flow control are supported by the modems: XON/XOFF, RTS/ CTS, and DTR/ CTS. All of the above features are discussed in the modem manuals.
B. Software
- 1. Data Transmission
-(
All transmissions, from both the site and the ERDS, will be terminated with a carriage return
- ( < CR > ).
- a. Site willinitiate a link request in ASCII using-
- the three character site designator,
- the word LINK.
- local site time and date in the format MM/DD/YY/HH:MM:SS, and
- a < CR > ,
if the site does not receive a response from the ERDS within one minute,it should send another link request message and continue sending them at one minute intervals, if more than five minutes elapses without a response, site personnel should notify the NRC before disconnecting the line.
- b. ERDS will respond in AECll with:
- the three character site designator,
- the word ACCEPTED or DENIED, and
- a < CR > .
If the ERDS responds with the denied message, the site should wait one minute and then send a link request message and continue sending them at one minute intervals. lf B-3 l
PY-CEI/NRR-140l L Attachment 2 more than five minutes elapses without a response, site personnel should notify the ^" 4!.10 P
{
NRC before disconnecting the line.
- c. When the ERDS is ready to receive data, it will send an initiate message in ASC3 using:
- the three character site designator.
- the word INinATE, and
- a < CR > , e if the ERDS does not send an inititte message within one minute of the accept mes-sage, the site should send the link request message (described in Section H.B.1.a.).
d.- Upon receipt of the initiate message, the plant begins transmission of data at a 15-second rate. The data string consists of:
- a header containing the three character site designator and date and time in the format MM/DD/YY/HH.MM:SS,
- the data packet sequenced with point identifier, value, and quality tag.
- a trailer containing the checksum value of the data packet, aad a < CR >.
- e. Wh:n the site or ERDS wishes to termi". ate the mnnection, an ASCII nessage will be sent containing:
- the three-character site desit uator.
- the word TERMINATE, anc
- a < CR > .
- f. If a site is inadvertently terminate 1(due to loss of communications or receipt of termi-nate message) and the incident it still underway, the site should reconnect with the ERDS by redialing and using the reconnee'. iink requen :n-ss:,ge. This message is in
. ASCII and will contain:
- the three-character site designator,
- the word RECONNECT,
- local site time and date in the format MM/DD/YY/IDH0tSS, and
- a < CR > .
Upon receipt of this message, the ERDS will respond with the accept and initiate mes-sages as described in Sections U.B.1.b and II.B.1.c. If the ERDS responds with a link deny message (described in Section D.B.1.b) the site should stop trying to reconnect and send a link request message (described in Section II.B.1.a). If the ERDS does not respond to the site's reconnect request within one minute. the site should send another reconnect request and continue sending reconnect requests once a minute. If more
- than five minutes elapses without a response, site personnel should notify the NRC before disconnecting the line. it is the responsibility of the site to monitor the outgoing line for loss of communications.
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PY-CEI/NRR-1401 LL-A . - , s-Attachment-!2- ;
4 L i Data Format :
Page 5 of 10' . 4 p
y n R- . he following three delimiters have been identified:
L(1); Sold delimiter ('k ,
"- L(2) data set delimiter (\),~and
- L(3); carriage return (<CR>). . ,
- Note: ne Ogth of the messages sent by the ERDS (e.g., ACCEPTED, DENIED,C INITIATE, TERMINATE) are variable and it is recommended that the site soft' *.
ware use the data set delimiter as the message delimiter for messages received.
from the ERDS.
p ^
'.a.1 Link requests will be in ASCH as described in II.B.1.a. with each field separated by a -
- Seld delimiter and the request terminated with a data set delimiter. For example, ;
pal
- LINK'01/12/89/11:48:50\ < CR >~.
b) : The ERDS response will be in ASCH as described in H.B.1.b. with each field sepa-
- rated by a Seld delimiter and the response terminated with a data set deliraiter. For exampic, pal *ACCErtr.1A<CR>, ~
- c. - When the ERDS is ready to receive data it will respond in ASCH as described in:
ILB.I.c with 'ench Seld separated by a field delimiter and the response terminated with -
~
y, ~a data set delimiter. For example, pal
(d. . Data streams will be in ASCH and will consist of thre parts (header, data, and trailer) as described in H.B.I.d. with each Seld separated by a field delimiter and each of the three parts separated by a data set delimiter. For. example, 3 Header:; pal *01/12/89/11:50:30\-
Data: - B21CP004*-0.1234E+00*3* .(for each parameter)\
Trailer: 0000056000\ < CR>
- e. The point identiSer may be up to 12 characters in length.--
L ,
f.' ?The value may be up to 20 characters in length.
g." -
The following quality tags will be accepted by the ERDS: 3 I, '~_
Good E =0- Value is within range tolerance for discreet points or in-
. put points are within tolerance for composed points.
L
. Off scan =1 . Point is currently out-of-senice.
Suspect =2 ?Value is not bad yct should not be considered good.This
- quality will occur primarily on composed values when
? ;
enough good inputs are present to allow the calculation l
to be made yet a bad quality on other inputs may make f .
the result questionable.
l -
Bad -3 Value is not within tolerance for discreet points or calcu.
lation of a composed point may not be made due to.the -
qualities 'of its inputs.
l-B-5 i
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1
Pf-CE//NRR-14011L:
At t chmei.: 2
,[-.
'- Unknown =4- _ No quality indicator available. Page 6 of 10 ...
N
. : Operator Entered = 5- ' Value has been manually entered, overriding the_ dis- -
creet or composed value.
High Alarm- .=6- Value is in high alarm.
I.ow Alarm =7 Value is in low alann, 2<
- h. The checksum which accompanies each update set will be an integer value calculated by summing each of the bytes of the transmission, up to and including the dataset de * *. "
limiter following the body of the update set (the body of the update set being the por.
tio'n containing the parameter, value, and quality indications). "Ihis integer checksum -
value' will then be encoded into the update set as a 10-digit value, left padded with zeros as required to fill the 10 digit field. The checksum is the sum of the transmitted
- bytes.
- i. The reconnect link request message will be in ASCH as described in Section H.B.1.f !
with each field separated by a field delimiter and the request terminated with a data set delimiter. For example, pal
- RECONNECT *01/12/89/11:48%<CR>.
-3. Protocol
- a. ERDS will use XON/XOFF to stop, resume, or suspend data transmission for the site. :
4
- b. Communication parameters:
- eight data bits
- 1 stop bit - (
parity = none i
- 4. Exceptions Please note any' exceptions which must be taken to Section H and explain why, i
-ERDS data frcm Perry will be transmitted at a 60 second rate l due to the current loading of the Camputer Systans at Perry.
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PY-CEI/NRR-140 i L
' Attachment 2
' ""8' 7 *' -
III. . Selection Of Data Feeders C l(; ;;
A. How many data feeders are there (six maximum)?
l' This data feeder will collect data frm 2 plant camputers and then transtit the plant data to the NRC via a Imdem. 4.
.j i
B. Identify the selected data feeders and provide the following for each:
(1).-- a short description of the categories of data points it will provide (e.g., met, rad, or
. plant data points, by unit) and
. (2) the rationale for selecting it if another system can also provide its categories of data points.
-(1) . All required points except Oxygen Concentration'and Intennediate Range Nuclear Instruments.
-(L (2) Only plant cmputer with sufficient CPU capacity to handle comunication program.
C. Which data feeder is the site time determining feeder? His should be the feeder which is providing the majority'of the data pomts.
3 ERIS (Emergency Response Information System) will provide the time ,
stamp on plant data.
B-7 y
- PY-CEI /NRR- 140 i L -
i
Attachm'ent 2 Page 8 of 10
-IV. Data Feeder Informati:n
'J
=. Note: A new Section IV must be filled out for each feeder system selected.
- General.Quotions
- 1. IdentiSestion of Data Feeder
- a. What is the name in local parlance given to this data feeder (e.g., Emergency Response .
Information System)? Please give both the acronym and the words forming it.
Aladin Lt' '
~ b. ~ Is this the site time determining feeder?
No c.- What is the upd te frequency of this feeder (in seconds)?
Data will be updated every 60 seconds.
- 2. Hardware / Software Environment a.: Identify the manafacturer and model number of the data feeder hardware.
VAX 11/780
- b. Identify the operating system.
VMS 4.4
- c. What method of timekeeping is implemented on this feeder system (Daylight Savings, Standard, Greenwich)?
Daylight Savings
- d. 'In what time zone is this feeder located?
Eastern 1
B-8
PY-CEI/NRR-1401 L
Page 9 of 10 .
.3 -
Data'Commumcation Details .
- ' . . a. Can this. data foeder provide asynchronous serial data communication (RS-232-C) '
with full-modem control?
~
~Yes-
- b. Will this feeder transmit m ASCII or EBCDIC 7 [
ASCII
- c. Can this feeder transmit at a serial baud rate of 2400 bps? If not, a:what baud rate can it transmit?
Yes
- d. Does the operating system support XON/XOFF flow control?
Yes
- 1. Are any problems foreseen with the NRC using XON/XOFF to control the trans-mission of data? -
No
(-
A
^
- e. slf it is not feasible to reconfigure a serial port for the ERDS linkup (i.e., change the baud rate, parity, etc.), please explain why.1 ,
N/A
- f. Can the serial port dedicated to the ERDS be configured so that the NRC need not emulate a specific brand of terminal (i.e., can-it be configured to be a " vanilla" terminal)?
Yes B-9
PY-CEI/NRR-140i L F
,. Attachment 2 .
Pne 10 of 10 ,,
Do any ports cenently saist for the ERDS linkup?
g.
.Yes
- 1. If not, is it possible to add additional ports?
l N/A J
- 2. If yes. will the port be used solely by the ERDS or chared with other non.
l emergencv time users 7 Give deta'Is. '
Only for ERDS.
- 4. Data Feeder Physical Environment and Management 1
- a. Where is the data feeder located in terms of the TSC, EOF, and control toom?
' TSC
(
- b. the data feeder protected from Lss of supply of electricity?
Yes
- c. Is there a hunun operator for this d t feeder? -
5 Yes
- 1. If so, how many hours a day is the feeder attended?
Mon - Pri 10 hrs / day (7:00 - 17:30)
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