Letter Sequence Other |
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MONTHYEARML20063P9311990-07-18018 July 1990 Technical Evaluation Rept Prairie Island Nuclear Generating Plant Units 1 & 2 Station Blackout Evaluation Project stage: Other ML20062C9101990-10-22022 October 1990 Advises That 890413 Schedule for Required Hardware & Associated Procedure Changes Re Station Blackout Rule Still Valid Project stage: Other ML20217A9561991-03-0101 March 1991 Forwards Request for Addl Info Re Station Blackout/ Electrical Safeguards Upgrade Project Project stage: RAI ML20070P5911991-03-20020 March 1991 Responds to NRC Questions on Design Rept for Station Blackout/Electrical Upgrade Project Submitted Via 901127 ltr.Marked-up Pages from Rept Re Diesel Generator Room Ventilation Sys & Diesel Engine Auxiliary Sys Encl Project stage: Other ML20072V5141991-04-16016 April 1991 Forwards Response to NRC 910301 Request for Addl Info Re Design Rept for Station Blackout/Electrical Safeguards Upgrade Project Project stage: Request ML20082B9211991-07-10010 July 1991 Responds to NRC 910611 Request for Addl Info Re Project to Add Two Addl Safeguards Edg,To Upgrade Safeguards Electrical Distribution Sys & Upgrade Cw Pump to Become Swing Safeguards Pump Project stage: Request 1991-03-01
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20195G4281999-06-0909 June 1999 Notifies That Amsac/Dss Mods Completed & TS 138/129 Has Been Fully Implemented 05000282/LER-1999-005, Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved1999-06-0707 June 1999 Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved ML20207F4301999-06-0101 June 1999 Forwards 1999 Unit 1 SG Insp Results,Per TS 4.12.E.1. Following Insp 84 Tubes Were Plugged for First Time ML20196L2461999-05-21021 May 1999 Forwards Rev 0 to COLR for Pingp,Unit 1 Cycle 20, IAW TS Section 6.7.A.6 ML20195C6861999-05-21021 May 1999 Forwards Rev 17 to USAR for Prairie Island Nuclear Generating Plant.Attachment 1 Contains Descriptions & Summaries of SEs for Changes,Tests & Experiments Made Under Provisions of 10CFR50.59 During Period Since Last Update ML20206U6781999-05-17017 May 1999 Forwards Revised Emergency Response Plan Implementing Procedures,Including Rev 15 to F3-3,rev 15 to F3-16,rev 14 to F3-22 & Table of Contents ML20206U7131999-05-17017 May 1999 Forwards Revised EOF Emergency Plan Implementing Procedures, Including Table of Contents & Rev 2 to F8-10, Record Keeping in Eof. with Updating Instructions ML20206T2461999-05-17017 May 1999 Forwards Off-Site Radiation Dose Assessment for Jan-Dec 1998, Rev 0 to Annual Radiactive Effluent Rept for 980105- 990103 & Effluent & Waste Disposal Annual Rept Solid Waste & Irradiated Fuel Shipments,Jan-Dec 1998 ML20206R0401999-05-13013 May 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Removing Plant Organization Requirement,Imposed in Amend 141/132 That Plant Manager,Who Has Responsibility for Overall Safe Operation of Plant,Report to Corporate Officer ML20206Q0871999-05-13013 May 1999 Forwards Result of Evaluation Re Ultrasonic Exams of SG Number 22 Performed in Accordance with ASME Boiler & Pressure Vessel Code Section Xi.Procedure Used for Evaluation Contained in WCAP-14166,submitted for Review ML20206F9381999-05-0303 May 1999 Forwards Response to NRC 990304 RAI Re GL 96-05 Program at Pingp.Licensee Commitments Are Identified in Encl as Statements in Italics ML20206J3851999-05-0303 May 1999 Forwards 1998 Annual Radiological Environmental Monitoring Rept 05000282/LER-1999-004, Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics1999-05-0303 May 1999 Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics ML20206E1761999-04-28028 April 1999 Forwards Revised TS Pages for Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively,to Update Controlled Manual or File ML20205S3221999-04-20020 April 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements of TS 5.1 ML20205P9891999-04-12012 April 1999 Requests Approval for Proposed Alternatives to Liquid Penetrant Requirements of N-518.4 of 1968 ASME Boiler & Pressure Vessel Code.Results of Analysis & Summary of Tests Performed & Tests Results Are Encl ML20205Q0191999-04-12012 April 1999 Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR 05000282/LER-1998-010, Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER1999-04-0808 April 1999 Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER ML20205P9221999-04-0101 April 1999 Submits Relief Request 8,rev 0 Which Addresses Limited Exams Associated with Unit 2 Third ten-year Interval Inservice Insp Program.Util Requests Relief Per 10CFR50.55a(q)(5)(iii) Due to Impracticality of Obtaining 100% Exam Coverage ML20205E8371999-03-31031 March 1999 Submits Four Copies of Rev 38 to Prairie Island Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Security Plan.Encl Withheld,Per 10CFR73.21 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205Q5051999-03-30030 March 1999 Forwards Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327- 981229. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarized Results ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20204H3371999-03-19019 March 1999 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection 1999-09-07
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. 1 Northom States Power Company 414 Nicohet Mall Minneapoks, Minnesota 65401 1927 Telephone (617) 330 6500 March 20, 1991 10 CFR 50.63(c)(d)
U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR 60 Reply to Questions on Design Report for the Station Blacknut/ Electrical Safeguards Up. grade Project (TAC Nos. 6858n and 68589)
Reference:
Letter from Thomas M Parker to U S Nuclear Regulatory Commission dated November 27, 1990 titled " Design Report for the Station Blackout / Electrical Upgrade Project
On November 27, 1990 we submitted for NRC Staff review the design report for our project: 1) to add two additionni safeguards emergency diesel generators,
- 2) to upgrade the safeguards electrien1 distribution system, and 3) to upgrade
- 121 Cooling Water Pump to become a swing safeguards pump. Through phone discussions with NRR Staff personnel, Mr Armando Masciantonio and Dr Saba Saba, we received several questions. These questions can be answered by revising the pertinent pages of t.he referenced design report. Attached to this letter are marked up pages of that report. The indicated changes will be incorporated into the next formal revision to the design report.
/
9103270355 910320 . ^h PDR ADOfK 05000282 g I
P PDR {
k
Northem States Power Company Please contact us if you have any questions related to the responses to the questions, lNN)
Thomas M Parker Manager Nuc1 car Support Services c: Regional Administrator Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg
Attachment:
Marked up pages (pp. 22, 29, 34, 37, 39, 48, 53, and 100) of the Design Report for the Station Blackout / Electrical Upgrado Project t
x.
e
,. - J
- 5. Combustion Air and Exhaust System
- a.
- Intake Air Filter Safety Related ij
- b.
- Exhaust Silencer Safety Related !
- c. Interconnecting Safety Related Piping
- Supplied under Diesel Generator Specification M-870.
3.2.2 Diesel Generator Room Ventilation System The diesel generator room normal mode ventilation fans and associated-ductwork and controls will be non-safety p- 1 related. Th.> egue(m i-+ i5 7. v. b . s b A w c- Ad .
All other components of the diesel generator j related3 *~b Safr eTroom . (/ //,4 F
-ventilation opewnok of gastem ct,ewill s e sbe gn e**+*4 safetyser, 3.2.3 Electrical Power Distribution. Instrumentation and Controls f
The electrical power distribution and controls system necessary for operation of safety related equipment _ is classified as safety related (Class 1E). Diesel '
generator power is required in the event of a loss of of fsite power, _ and is required to be available when a 0- r tv ias ceioa (st) =tu etoa tea 1 i= initi t a- ,
Instruments, controls, .and- associated- sensir.g lines having the function to ensure operation of _the diesel generator. units, the engine room ventilation,- or to '
maintain-integrity of Class lE circuits, will be designed safety related. Those that are required for alarming,
-indication and monitoring will-be non-safety related.
1
- 3. 2. 4_ Fuel Oil Storace and Transfer System The electrical power supply equipment, including pump controls,- instrumentation and cable / raceway will be safety _ related class lE for the equipment associatJd with the four storage tanks and four transfer pumps. Controls i and instrumentation associated with-1-level and:' leak detection of fuel oil for the purpose of indication, I monitoring and alarm will- be- designated as non-safety related.- ..
Power supply'. equipment, controls, instrumentation and circuits / raceway associated with the receiving tank and' recirculating pump will be designated as non-safety related.
t O 22 NSP*06'
, Rev. A /
A 3-way thermostatic valve regulates flow through the oil cooler based on outlet temperature. Any excess oil from the discharge valve and cylinder block internal bearings ,
are returned to the oil cump.
The lube oil system will be provided with a pre-lube system to maintain constant flow of lubricating oil to ,
critical areas during standby mode to minimize wear during engine starts. To enhance quick engine starts, the pre-lube system maintains lube oil in the " keep warm" temperature through the lube oil standby heat exchanger, heated by the koopwarm portion of the HT cooling water system. The pre-lube system design will include provision for draining lube oil from the engine crankcase. An AC motor-driven pump will be used normally for pre-lube system operation with a DC motor-driven pump for backup operation. Both pumps and the standby heat exchanger will be located in the auxiliarios desh.
A sufficient quantity of lube oil to permit 7 days of continuous operation at rated load will be maintained on site'for e Ldiesel generator. The stored in drums cr a lube oil storage tank. lube oil will be l I?cv /
l oe/de 4f ese own The lube oil storage tank provided for each diesel generator will be located at an elevation to permit filling of each engine crankcase by means of gravity flow, which will be controlled by a manually-operated fill valve.
3.3.4.2 Diesel Lube Oil System Installation Installation requirements for the lube oil system will include providing interconnecting piping for the following equipants
- a. From the lubo oil storage tank to the manually-operated fill valvo.
- b. Reservoir fill line (funnel) to the luLe oil reservoir.
- c. From the engine prolubrication outlet to the auxiliarios desk.
- d. From the auxiliarios desk outlet to engine prelubrication inlet connection.
Miscellaneous piping will be required by the diesel engine. This includes providing crankcase relief valve l
discharge piping to be routed to the building sump.
up46 g"
-c'-+=r- w t-----M-r aw or-e-eu- ee- e' e ww*'-y -
+ u--' ~'r*- =-+7
i
/
Rev. 4 The intake and oxhaust louver frames and blades will be steel, and will be tornado missile proof. The intake and exhaust openings will be located at an elevation higher than the maximum probable flood level.
All components of each ventilation t stem will be protected from tornado generated missiles. ,
1 The diesel generator room vent fans will be vane axial-type with direct-drive totally-enclosed-air-over (TEAO) motors.
Fan-developed pressures will be based on the pressur'e ,
drop through ductwork, concrete plenuma and distribution accessories.
All equipment will be f actory inspected and tested in accordance with the applicable equipment specification.
Erection and inspection of equipment will be in
- accordance with the design drawings and manufacturer's recommendation.
System testing and balancing will be performed and j evaluated prior to system turnover. Controls on each system will be checked, adjusted and tested to ensure the proper sequence of operations. A final, integrated preoperational test will be conducted with all equipment and controls in operation to verify operation.
])icinulesec 55.6.5 1
ram ~i Aua,/iaag Matat4+-1s 3.3.7 P -Recu+rementa-and /2ev l All interconnecting piping unless otherwise noted herein, 4
will be A!ISI 150 lb pressure class. All miscellaneous piping such as for drain and vent will be rated for 150 lbs. or greater.
All piping joints ar.d connectionc will be we' %d. Where required, such as at pump suction, discharge cunections, and flexible connections, flanges will be acceptable.
All piping material will be carbon steel except the following systems:
- Material
- a. Starting Air System Stainless Steel j 304 or 304L
- b. Combustion Air and Galvanized Carbon Steel
- c. Exhaust System Carbon Moly Alloy Steal l
Nsp.06 }$ &
k Rev. DI e
- d. Interconnecting ASME Section III Piping (except Manu- (1986), Class 3**
facturer's Standard Piping Sections) ,l' 1
- e. Vent & Drain Linen AliSI B31.1-1967 l (for air receiver, ,
beyond First Isolation Valve)
- 4. Lube Oil System .
- a. Lube Oil Storage API-650-1984
~
Tank
- b.
- c. AC Motor Driven Transfer Pump AliSI BSl.1-1967
- d. Tank Vent &
Drain Lines AllSI B31.1-1967 (beyond First Isolation Valve)
- e. Engine / Aux. Desk ASME Section III !
Interconnecting (1986), Class 3** l Piping
- f. Lube Oil Storage AliSI B31.1-1967 -
Ttnk Fill Line l
- 5. Combustion Air and Exhaust System
- a.
- Intake Air Filter Manufacturer Std. l
- b.
- Exhaust Silencer Manufacturer Std. !
- c. Pipino --- -
1 fl. Exhaust AM&B M (1986),
fabricated per SA 691 Class i G M. Stress annlyzed per ASME Section III Class 3 components using ANSI B31.1 (1986) stress allowables, kN I AM G kc.R Ccass 3
- 2. Intake AJ " ' - "'
1 (1986), j fabricated per SA 134 .
Stress analyzed- per ASME Section III Class 3 components using B31.1 3
(1986) stress allowable i Asm G Sf M %
- Supplied under Diesel Generator Specification M ,
- With exceptions as listed in Section 3.3.8.1.
NSP D6 37
. _ - - .,_ __ _ _ .m.-.__. _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ - - _ _ _ _
i i s
I o The auxiliary desk (one for each engine), located near the diesel generator unit, will include gauges to indicate engine temperatures and pressures. .
The bench board control panel, located in the diesel generator control room, will include instruments and !
controls for the diesel generator and auxiliaries plus -
the fuel oil transfer pumps, engine room ventilation, and control room ventilation fans.
- A vertical panel, located in the diesel generator control room, will be provided to include additional instruments and controls for the diesel generator and auxiliaries.
- A generator exciter panel, located in- the diesel generator _ control room, will include excitation, voltage regulation, and field flashing equipment, and current and voltage transformers for protective relays and power measuring instruments.
3.3.10.2 Trips and. Interlocks l
All protective trips other than engine overspeed and generator differential overcurrent will be bypassed upon '
receipt of an automatic emergency start signal in response to a safety injection signal and will be aaauaciated in th- ==in coatrot roo=- "o Prot ctiv-O trips will be bypassed upon receipt of an automatic bus undervoltage start signal.
Protective trips will be provided to automatically. shut down the diesel engine and/or trip the diesel generator breaker, and protect the diesel generator units from possible damage or degradation during routine testing.
Protective trips Awill be in accordance with vendor recommendations and will consist of, but not be limited to the following: -
Ao Logu 44 eAcH e rac
^
o Overspeed '/2 Engine Lube Oil Low-Low Pressure VJ o
o Jacket Water High-High Temperature %
o Jacket Water Los Pressure W o Crankcase High Pressure </i o Lube Oil Sump Low Lev d m fe High Temperature Y' fI.2-o Generator _ Bearing o Engine Bearing High-H gh Lube 011 Temperature %
o Reverse Power 'h
-o Generator Differential current '//
o Generator Phase overcurrent </, s o Generator Overvoltage e/f o- Loss of Excitation </,
O o w s~~</a w,cz ,,
NSPa06 39 l
l u- . . . . . _ . _ _ _ . _ _ _ _ _ .
l l .
Rev. D' f i
Fill inlet connection and vent outlet connection will be protected from flood conditions and will bo positioned above the maximum probable flood level. ,
3.4.2,2 Underground Storage Vault The emergency storage tanks will be installed it. a ,
Seismic Category I reinforced concreto vault enclosure located below seismic grade lovel and adjacent to the west wall of DS/D6 Diccol Generator Building. The vault will provide the required 3-hour rateci firo protection barrier, including D5/D6 west wall penetrations, for enclosed fuel supply tanks, and in addition, will withstand the effects of tornado generated missiles, site flood, and buoyancy force considerations. The vault will be a vital area.
The vault will be divided into two compartments by a concrete partition wall to separate each pair of tanks serving a single diesel generator cet and provide fire and flood protection between each diesel generator sets fuel supply equipment.
The vault will be sized to provido a minimum clearance of 15 inches from all tank surfaces, as well as allowing convenient accessibility to the tanks for inspection and repair. Leakproof hatches will be provided on top of the vault for tank internal and external inspection access and to allow removal of tank internal strainers and baffles and other appurtenances. Level instrumentation will be bottom mounted.
The underground storago vault will be insulated suf ficiently to protect the fuel oil from reaching a minimum system operating temperature. The vault temperature will be indicated y an6 monitored by / ge y J operationc. y yte y ,4 ,aj a,% l The vault will be provided for containing leakage of the tank contents and any accumulated seepage wa r. The
, vault floor will slope to a sump, which will t 'tain a leak detector., Leak detection instruments wail be \
provided to alert presence of fuel or water in the sump. ,/
1M n y,w be
% mon lo 6,n.
w . cm/u n o eb A~b 4 5<~ rm %u ble n. oa,.. < a The detailed structural design requirements for the concreto vault structure will be as specified in Section 4.0 The vault's walls and bottom will be provided with a waterproof membrane. All hatches and penetrations on the top slab will be leak-tight, use.cs j'l 48 \
4 * .
iJ o 17
3.4.2.6.2 Design and Fabrication Codes i )
- Desian & Fabrication Code .
- 1. Tanks j
- _ a. Emergency Storage Tanku ASME,Section III (1986), Class 3** ,
j b. Receiving Tank API 650-1984 1 -
- 2. Pumps
- a. Transfer Pumps Viking Pump -
Manufacturer's Std.
- b. Recirculating Pump Viking Pump Manufacturer's 5td t
- 3. Piping, Pipe Support Components and Valves
- a. Fuel 011 Transfer Piping ASME Section III System (except vent and (1986), Class 3**
drain lines)
- b. Receiving Tank Piping & ANSI B31.1-1967 Recirculating Piping Q
System
- c. Storage Tank Vent ASME Section III i (1986), Class 3**
Drain Lines
- d. ANSI B31.1-1967 o
after First Isolation >
Valve
~** With cxceptions as listed in Section 3.4.2.6.1.
! 3.5 DESIGN STANDARDS In addition to the codes and standards listed in the ,
design-requirements givenNUREG above 0800, in SectionA 2.4.2.6.IEEE standards, (gg pnd-g 2.'.0 7 the following and I regulatory guides are adopted in whole as design criteria requirements for the DS and 06 Diesel Gen 0rator and-Auxiliary Systems as described in Section 3.0.
Within the existing plant- boundary the existing design
! criteria as defined- in the USAR will apply except u noted otherwise in this document.
O W1P*D6 53 w...._......_,._..a__,....-_..___._._,___--___._____._____-___________
-. ~ . .- - - - . . - - - - - - - - . . - - - . - - - - _ - - - . - - - -
l
. .. l 6
l Rev. 6 5.3.6 Emeraency Resoonse Comnuter System 1
T.5e Emergency Response Computer System (ERCS) will serve .'
as an aid to the control room operator in monitoring the status of the DS and D6 diesel generators. It may replicate some functions of the engine monitoring system, local control panels or the hard-wired control room -
instrumentation. Instead, it will only monittr specific inputs and provide data to fulfill a specific need for the operator. Areas identified to date include o Annunciator system support to identify, on demand, a spezific input that generated a group alarm.
o operations data logging of turveillance testing events.
o Provide analog process information of parameters occasionally required.
523.7 D5/D6 Control Scheme Tie-In with Existina Plant Whenithe local Generator Control Mode switches, located in the D5 and D6 Control Rooms, are in the remote position, control of the D5 and D6 cmergency diesel '
generators is transferred to the Main Control Room.
Emergency start, manual start and stop, voltage adjust, speed control, main breaker control and synchronizing are among the controls that will be available in the Main control Room.
Tho design of the control circuitry between the DS and D6 Control Rooms and the Main Control Room will include the intermediate termination of all control cables at terminal cabinets located in the Relay Room and then circuit continuation to the Main Control Room.
The DS and D6 tie-in to the existing plant will also include all appropriate alarm circuits to the annunciator cabinets.
5.1.8 Main control Room "G" Panel Modification The existing controls for the safeguards diesel generators and 'their associated 4160V buses located-on the Main Control Room "G" Panel will he replaced and additional controls for the new diesel generators will be installed. The existing panel will be replaced and smaller controls wi? I be installe/ to accommodate the additional controls in the origir- sace. o Annunciator Revi alarms for the new diesel gene installed concurrently with the "GtLpanel,r;M--d work. be
,( HL $9 eJ .
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