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MONTHYEARML20087C6941992-01-0808 January 1992 Responds to Questions on Design Rept for Station Blackout/ Electrical Safeguards Upgrade Project Project stage: Other ML20126C0541992-12-11011 December 1992 Forwards Responses to Questions on Design Rept for Sbo/ Electrical Safeguards Upgrade Project.Operations Manual Section H7.3, Integral Welded Attachment Evaluation Criteria... Also Encl Project stage: Other ML20126A8981992-12-15015 December 1992 Responds to NRC Telcon Request for Addl Info on Design Rept for Station Blackout/Electrical Safeguards Upgrade Project, Transmitted Via Util 901127 & s.Bldg D5/D6 Designed to Preclude Postulated Fire Exhaust Project stage: Request ML20126D7991992-12-21021 December 1992 Forwards Response to NRC Request for Info on Station Blackout/Electrical Safeguards Upgrade Project,Proposing Addition of Two Safeguards EDGs to Upgrade Safeguards Electrical Distribution Sys Project stage: Request ML20126G9311992-12-29029 December 1992 Responds to NRC Request for Info on Station Blackout/ Electrical Safeguards Upgrade Project to Add Two Safeguards EDGs to Upgrade Safeguards Electrical Distribution Sys & Upgrade Cooling Water Pump 121 to Swing Safeguards Pump Project stage: Request ML20127C0001993-01-0404 January 1993 Forwards Listed Safety Evaluations in Support of Review of Station Blackout/Electrical Safeguards Upgrade (Sbo/Esu) Design Rept,Rev 1 Project stage: Approval ML20128A3181993-01-25025 January 1993 Discusses Status of Preoperational Load Testing of DGs for Sbo/Electrical Safeguards Upgrade Project Project stage: Other 1992-12-21
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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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Northern States Power Company 414 Nicollet Mall Minneapohs, Minnesota 55401 1927 Telephone (612) 330-5500 January 8, 1992 10 CFR Part 50 Section 50.63(c)(d)
U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR CENERATING PIANT Docket Nos. 50 282 License Nos, DPR 42 50-306 DPR-60 Reply to Questions on Design Report for the Station Blackout / Electrical Safeguards Upgrade Project (TAC Nos. M80659/80660)
References:
- 1) Letter from Thomas M Parker, Northern States Power Company, to U S Nuclear Regulatory Commission dated November 27, 1990 titled " Design Report for the Station Blackout / Electrical Safeguards Upgrade Project"
- 2) Letter from Armando Masciantonio, U S Nuclear Regulatory Commission, dated November 29, 1991 titled " Request for Additional Information-Station Blackout / Electrical Safeguards Upgrade Project (TAC Nos. M80659/80660)"
- 3) Letter from Thomas M Parker, Northern States Power Company,to U S Nuclear Regulatory Commission dated December 23, 1991 titled " Design Report for the Station Blackout / Electrical Safeguards Upgrade Project," Revision 1 On November 27, 1990 we submitted for NRC Staff review the design report (Reference 1) for our project to add two safeguards emergency diesel generators, to upgrade the safeguards electrical distribution system, and to upgrade the #121 cooling water pump to become a swing safeguards pump. On November 29, 1991 the NRC Staff requested additional information (Reference 2).
On December 23, 1991 ve submitted for NRC Staff review Revision 1 of the design report (Reference 3). This revision contains most'of the responses to NRC's November 29, 1991 request for additional information. In the attachment to this letter we are providing the remaining responses and a cross reference to responses contained in the design report revision.
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i Northem States Power Company USNRC January 8, 1992 Page 2 of 2 Please contact un if you have any questions related to these responses.
/ '
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//$Y fy Thomas M Parker Manager Nuclear Support Services c: Regional Administrator - Region III NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg
Attachment:
Response to Request for Additional Information
- . __ . . ~ _ . - - . - = ._ . . .. . . . - ~ ... - -
I NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR CENERATING PLANT STATION BLACKOUT / ELECTRICAL SAFEGUARDS UPGRADE PROJECT RESPONSE TO NOVEMBER 29, 1991 REQUEST FOR ADDITIONAL INFORMATION (TAC NOS, M80659/80660)
References:
- 1. " Design Report for the Station Blackout / Electrical Safeguards Upgrado Project," Northern States Power Company, November 27, 1990.
- 2. " Design Report for the Station Blackout / Electrical Safeguards Upgrade Project," Northern States Power Company, December 23, 1991.
OUESTION 1:
With respect to all emergency diesel engine ~ auxiliary support systems, i.e., the fuel oil and transfer system, the cooling system, the air starting system, the lubrication systom, and the combustion air intake and exhaust system;
- a. Provide information regarding the quality assurance requirements to which the system components are designed, manufactured, and inspected,
- b. Provide information regarding the design provisions for isolating the safety related portions of the system from the non safety-related portions in the case of emergency operation,
- c. Provide information regarding the extent of compliance of the system-to the recommendations of NUREC/CR 0660, " Enhancement of On-Site Emergency Diesel Generator Reliability,"
- d. Provide information regarding the protection of the safety 1related portions of the system from internally generated missiles, pipe whip, and jet impingement forces associated-with pipe breaks,
- c. Provide information regarding compliance of the system to Regulatory Guide 1.9, Position C 7, as it relates to the system protective interlocks.
RESPONSE TO OUESTION 1.a:
The response to question 1.a is provided in Design Report Revision 1 Sections 1,7, 3.3.8, 3.4.2.1, 3.4.2.4 and 3.4.2.6.1.
RESPONSE TO OUESTION 1.b!
Isolation capability for- each of the emergency diesel engine auxiliary support ~
systems is-described below:
l-
_ arege v-gyy-+--eg-, y s9v-'-- 6w* 4-rmp .m vr ey
4 Attachment Page 2 of 6 Puel 011 and Transfer System Isolation between the non safety related fuel oil receiving tank and the safety related fuel oil storage tanks is provided by a normally closed safety related manual valve.
Isolation between the non safety related fuel oil recirculation pump and filter and the safety related fuel oil storage tanks is provided by safety related manual valves.
Isolation between the non safety related fuel oil cleanup filters and the ,
safety related fuel oil transfer pumps is provided by normally closed safety related manual valves.
All non safety related instruments (indicators, switches, etc.), vents, and drains can be isolated by a safety related manual valve.
Cooline Water System All non-safety related instruments (indicators, switches, etc.), vents, and drains can be isolated by a safety related manual valve.
Starting Air System Isolation between the non-safety related air compressors and dryers and the safety related air receiver skid is provided by_ double safety related check valves and a manual valve at the air receiver inlet.
All non safety related instruments (indicators, switches.-etc.), blowdowns, vents, and drains can be isolated by a safety related manual valve.
Lube Oil System Isolation between the_non-safety related lube oil makeup 1 tank and the engine is provided by normally closed safety related manual valves.
All non safety related instruments (indicators, switches, etc.), vents, and drains can be isolated by a safety related manual valve.
Combustion Air Intake and Exhaust System All non-safety related instruments (indicators, switches, etc.) can be isolated by a safety related manual valve.
RESPONSE TO OUESTION 1.c:
Prairie Island is not committing to compliance with NUREG/CR 0660 (or NURSG/CR 5078) concerning reliability and maintenance of D5/D6 diesel generators.
Therefore the reference to NUREG/CR 0660 has been deleted from_ Design Report-Section 4.6. Prairie Island is monitoring industry progress with regard to
Attachsent Page 3 of 6 development of guidance for implementing NUMARC 87 00, Appendix D, and resolving Generic Iss'e B56. Prairie Island intends to implement final industry guidance. Further, Prairie Island's present operating procedures and practices have successfe'.ly maintained D1/D2 within Appendix D's reliability target of .975, and it is anticipated that actiono for D5/D6 would provide similar results, RESPONSE TO OUESTION 1.d:
The response to Question 1.d is provided in Design Report Revision 1, Sections 4.3.1.11 and 4.3.2.2.3.b.
RESPONSE TO OUESTION 1.g'.
The response to Question 1 e Js provided in Design Report Revision-1, Section 3.3.10.2.
OUESTION 2 With respect to the fuel oil storage and transfer system:
- a. Provide the appropriate assurance that the design of the system conforms to the provisions cf ANSI-195 regarding fuel quality. In addition, provide the commitment that the fuel' quality and tests will conform with the guidelines of Regulatory Guide 1,137, positions C.2.e through C.2.h.
- b. Provide information regarding the availability of sources of fuel oil including the means of transporting and recharging the fuel storage tank,
- c. Provide th, specific measures used to minimize the creation of i turbu'.ence of the sediments at the bottom of the fuel oil storage tank, l I
- d. Provide information regarding the design provisions for removing accumulated water from the day tank, the receiving tank, and the fuel-storage tanks.
RESPONSE TO OUESTION 2.n:
l Part 1: The project design complies with ANSI N195-1976, with the following l exceptions:
Subsection 6.3: There are no duplex-(or simplex) fuel strainers on the ;
engine preceding the fuel filters (to preclude clogging). However, there '
are fuel oil strainers in the transfer lines to the day tanks, and the on-engine filters are duplex so that routing can be switched in-case of clogging (see Design Report Revision 1, Section 3.3.2.1).
Subsection 7.3: There is no illumination, heating or ventilation
o' Attachment Page 4 of 6 provisions in the fuct oil storage tank vault. However, the vault is adequately insulated and instrumentation is provided for monitoring vault temperatures, as discussed in Design Report Revision 1. Section 3.4.2.2.
The vaults are not intended to accommodate habitation by plant personnel; special provisions will be made for illumination and ventilation _during isolated periods when the vaults need to be accessed.
Subsection 7.4: -There are exceptions to piping system compliance with ASME Section III, as discussed in Design Report Revision 1. Fulfillment of ASME Section XI will parallel the existing Prairie Island in service inspection plan.
Subsection 7.5: There are no strainers in the fill lines for the fuel oil receiving tank. However, received fuel oil will be circulated through filters prior to being transferred to the fuel oil storage tanks, as discussed in Design Report Revision 1, Section 3.4.
Subsection 7.5: There are no provisions for detecting and removing accumulated water from "each [F.O.) tank". See response to itam 2.d. '
below, Part 2: Prairie Island practices will comply with Reg Guide 1,13'/, parts i C.2.a. through g. (C.2.h does not apply), with the exception of C.2.a.
Prairie Island does not fulfill the-requirement of Appendix B of ANSI N195 l with regard to testing fuel oil for insolubles per ASTM D2274. Industry problems with this test are identified in NRC Information Bulletin 91-46.
Note: Design Report Revision 1, Section 3.5 references Reg Guide 1.137 and ANSI N 195 (and Standard Review Plan 9.5.4 which references Reg Guide 1.137) without discussing the above exceptions. -These exceptions will be noted-in-the next revision to the Design Report.
RESPONSE TO OUESTION 2.b!
Puel oil sources for Prairie Island are the following:
Amoco; Sauk Rapids, Minnesota Koch Refinery; Rosemount, Minnesota Ashland 011; South St. Paul, Minnesota The fuel oil is transported by truck. It is normally delivered within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, however for urgent cases it can be delivered within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
RESPONSE TO OUESTION 2.c:
The response to Question 2.c-is provided in Design Report Revision 1, Section 3.4.2.1.a.
RESPONSE TO OUESTION 2.d:
l The main provision for detecting and removing accumulated water from fuel oil I
I'
.- - .~. . -- - . _ . . -, ._ .- - . -. . , .~ . ..
Atte hnent Page 5 of 6 is the bell shaped appendage on the bottom of the fuel oil storage tank, as discussed in Design Report Revision 1, Section 3.4.2.1.a. This appendage wi..
be used for periodic checking of possible water contamination (Prairie Island Technical Specification 4.6.A.1.c.) and any necessary draining. Each of-the day tanks and the receiving tank have drain lines on the bottom of the tanks, which can be used for removing water; but principal controls for water contamination are through the fuel oil storage tanks.
OUESTION 3 With respect to the diesel air starting system:
- a. Given that the air t. tarting system is a high energy system, provide a high energy line break analysis.for the system. In addition, provide assurance that the piping and components pressurized to high energy pressures during standby, starting, and/or operation will be adequately restrained to prevent damage to other diesel generator piping, components, and equipment from pipe whip,
- b. Verify that the air system cranking capacity of cranking a cold diesel engine five times without recharging the receiver was determined in accordance with guidance contained in Standard Review Plan (SRP) 9.5.6,Section II, Item 4.g.
- c. Provide information regarding the design provision of alarms which would alert the operating personnel of a pressure drop in the air receiver, in accordance with guidance in SRP 9,5,6,Section II, Item 4.h.
- d. Provide information regarding the measures to be taken in the air starting system design to preclude the fouling of the air start valve or filter with moisture, oil, and rust carry over.
RESPONSE TO OUESTION 3.a:
l The response to Question 3.a is provided in Design Report Revision-1, Sections 4.3.1.11 and 4.3.2.2.3 b.
RESPONEE TO OUESTION 3.ht The response to Question 3.b is provided in Design Report Revision 1, Section
- 3.3.3.1.
. RESPONSE TO OUESTION 3.c:
The response to Question 3.c is provided in Design Report Revision 1, Section -
3.3.3.1.
. "'. l Attachment Page 6 of 6 RESPONSE TO OUFSTION 3.d:
The response to Question 3.d is ptovided in Design Report Revision 1, Section 1.3.3.1, OUESTION 4 With respect to-the diesel engine lubrication system:
- a. Provide the commitment that-the design values for operating pressure, temperature differentials, flow rate, and heat removal rates are in accordance with the manufacturer's recommendations.
RESPONSE TO OUESTION 4.a:
The reeponse to Question 4.a is provided in Design Report Revision 1, Section 3.3.4.1.
OUESTION 5 With respect to fire protection:
- a. Provide information regarding floor drainage provided for fire fighting water in the diesel generator area,
- b. Will local manual ventin6 be provided?
RESPONSE TO OUESTION 5.a:
The response to Question 5.a is provided in Design Report Revision 1, Section j 4.5.2.'
RESPONSE TO OUESTION'5.b:
The response to. Question 5.b is provided in Design Report Revision 1, Section
, 4.5.3.2, item 11.
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