|
|---|
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
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20065D5821990-09-19019 September 1990
Forwards Rev 25 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20059L3431990-09-13013 September 1990
Forwards Application for Amends to Licenses DPR-42 & DPR-60, Revising Tech Spec Section 6.7.A.6.b
ML20064A6411990-09-0606 September 1990
Amends 900724 Certification for Financial Assurance for Decommissioning Plant,Per Reg Guide 1.159.Util Intends to Seek Rate Relief by Pursuing Rehearing & Appeal of Rate Order by Initiating New Rate Proceeding
ML20059E8671990-09-0606 September 1990
Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20028G8401990-08-29029 August 1990
Forwards Effluent & Waste Disposal Semiannual Rept for Jan- June 1990 & Revised Effluent & Waste Disposal Semiannual Rept for Second Half of 1989,which Includes Previously Omitted Fourth Quarter Analyses Results of Sr-89 & Sr-90
ML20058Q4021990-08-0202 August 1990
Informs NRC of Potentially Generic Problem Experienced W/Westinghouse DB-50 Reactor Trip Breaker.Info Being Provided Due to Potential Generic Implications of Deficiencies in Westinghouse Torquing Procedues
ML20056A3371990-07-31031 July 1990
Forwards Rev 2 to, ASME Code Section XI Inservice Insp & Testing Program,Second 10-Yr Insp Interval of Operation
ML20055J4441990-07-26026 July 1990
Submits Supplemental Info to Violations Noted in Insp Repts 50-282/89-26 & 50-306/89-26.Training of Supervisory Personnel Not Completed Until 900719 Due to Time Constraints Encountered During Feb 1990 Unit 1 Refueling Outage
ML20055G3981990-06-28028 June 1990
Forwards Annual Rept of Changes,Tests & Experiments for 1989 & Rev 8 to Updated SAR for Prairie Island Nuclear Generating Plant
ML20043F7341990-06-11011 June 1990
Responds to NRC 900420 Ltr Re Violations Noted in Insp Repts 50-282/90-04 & 50-306/90-04.Corrective Actions:Operations Procedure D61 Will Be Revised to More Clearly Identify Requirements for Logging Openings
ML20043D5681990-06-0505 June 1990
Rev 23 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043C7731990-05-25025 May 1990
Informs That on 900425,yard Fire Hydrant Hose House 7 Declared out-of-svc Due to Const in Area,Per Tech Spec 3.14.F.2.Const in Area Will Prevent Return to Svc of Hydrant Hose House 7 Until Approx 900630
ML20043A4451990-05-0909 May 1990
Responds to NRC 900319 Ltr Re Violations Noted in Insp Repts 50-282/89-29 & 50-306/89-29.Corrective Actions:Changes Will Be Made to Review & Approval Process for Work Packages
ML20043A4531990-05-0202 May 1990
Responds to NRC 900319 Ltr Re Violations Noted in Insp Repts 50-282/89-29 & 50-306/89-29.Corrective Actions:Incoming Workers Will Be Specifically Trained in Fire Prevention Practices & Permanent Workers Will Be Reminded at Meetings
ML20042F8681990-04-30030 April 1990
Submits Supplemental Info on Response Time Testing of Instrumentation,In Response to Concerns Raised in Insp Repts 50-282/88-12 & 50-306/88-12.No Addl Changes to Current Response Time Testing Program Necessary
ML20042E8081990-04-27027 April 1990
Forwards Radiation Environ Monitoring Program Rept 1989.
ML20012E4261990-03-28028 March 1990
Forwards Inservice Insp-Exam Summary 900103-0219 Refueling Outage 13,Insp Period 2,Second Interval. Exam Plan Focused on Pressure Retaining Components & Supports of RCS & Associated Sys,Fsar Augmented Exams & Eddy Current Exam
ML20012D9131990-03-22022 March 1990
Forwards Rev 0 to Core Operating Limits Rept Unit 1 - Cycle 14 & Rev 0 to Core Operating Limits Rept Unit 2 - Cycle 13.
ML20012E0091990-03-21021 March 1990
Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey.
ML20006G1931990-02-26026 February 1990
Forwards Rev 22 to Security Plan & Advises That Changes Do Not Decrease Effectiveness of Plant Security Plan & May Be Implemented W/O Prior NRC Review & Approval.Rev Withheld (Ref 10CFR73.21)
ML20012A3131990-02-26026 February 1990
Forwards Rev 0 to Effluent Semiannual Rept,Jul-Dec 1989, Supplemental Info, Amend to Effluent & Waste Disposal Semiannual Rept for First Half of 1989 & Rev 11 to Odcm. Analyses for Sr-89 & Sr-90 Will Be Included in Next Rept
ML20006F8631990-02-22022 February 1990
Provides Steam Generator Tube Plugging & Sleeving Info,Per Tech Spec 4.12.E.1.Following Recent Inservice insp,15 Tubes Plugged for First Time & 37 Tubes W/New Indications Sleeved
ML20042E1871990-02-19019 February 1990
Forwards Response to NRC 900118 Ltr Re Violations Noted in Insp Repts 50-282/89-30 & 50-306/89-30.Response Withheld (Ref 10CFR73)
ML20006E8031990-02-16016 February 1990
Forwards Request for Relief from Schedule Requirements of NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Valves.
ML20011E4991990-02-0606 February 1990
Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested
ML20006B9291990-01-29029 January 1990
Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Procedure Will Be Developed to Periodically Inspect Emergency Intake Crib Located in River
ML20006B9041990-01-29029 January 1990
Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Boron Concentration Will Be Calculated W/Provisions for One Shuffle Alteration
ML20006B9951990-01-0303 January 1990
Suppls Response to Violations Noted in Insp Repts 50-282/89-14 & 50-306/89-15 Re Containment Airlock Local Leak Rate Testing.Corrective Actions:Changes to Local Leak Rate Testing Procedures Approved on 891229
ML20005E4881989-12-28028 December 1989
Responds to Generic Ltr 89-10 Re motor-operated Valve Testing & Surveillance.Listed Actions Will Be Performed in Order to Meet Recommendations of Generic Ltr
ML20011D6941989-12-15015 December 1989
Forwards Addendum 1 to Sacm Diesel Generator Qualification Rept & Diesel Generator Set Qualification Rept.
ML19351A5281989-12-13013 December 1989
Forwards Supplemental Response to NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors. Thimble Tube Insp Program Will Be Formalized by 901231
ML20005G4861989-12-11011 December 1989
Updates Response to Insp Repts 50-282/86-07 & 50-306/86-07 Provided by 860819 Ltr.Listed Actions Taken as Result of Task Force Evaluation,Inlcluding Implementation of Work Control Process for Substation Maint
ML19332F3621989-12-0101 December 1989
Responds to Generic Ltr 89-21 Re Implementation Status of USI Requirements at Facilities.Pra to Address USI A-17, Sys Interactions in Nuclear Power Plants Will Be Completed in Feb 1993
ML19332E9371989-12-0101 December 1989
Forwards Executed Amend 9 to Indemnity Agreement B-60, Reflecting Changes to 10CFR140
ML20006E3301989-11-20020 November 1989
Forwards Fee in Amount of $25,000,in Response to 891019 Notice of Violation & Civil Penalty Re Commercial Grade Procurement,Per Insp Repts 50-282/88-201 & 50-306/88-201. Responses to Violations Also Encl
ML19332D1761989-11-17017 November 1989
Forwards Application for Amends to Licenses DPR-42 & DPR-60, Deleting cycle-specific Core Operating Limits from Tech Specs & Creating New Core Operating Limits Rept,Per Generic Ltr 88-16
ML19332C8341989-11-13013 November 1989
Responds to NRC 891012 Ltr Re Violations Noted in Insp Repts 50-282/89-23 & 50-306/89-23.Corrective Actions:Procedure Changes Implemented to Require Placement of Yellow Tags on Fire Detection Panel Bypass Switches in Bypass Position
ML19324C4031989-11-0606 November 1989
Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Supply Breaker to Unit 2 Feedwater Isolation Valve Replaced W/Qualified & Traceable Replacement Circuit Breaker
ML19332B6131989-11-0606 November 1989
Forwards Rev 4 to Safeguards Contingency Plan & Implementing Procedures,Per Generic Ltr 89-07.Rev Withheld
ML19324B3321989-10-13013 October 1989
Submits Supplemental Info in Response to Violations Noted in Insp Repts 50-282/88-16 & 50-306/88-16.Corrective Actions: Air Test Connections Will Be Added to Allow Pressurization of Containment Spray Piping Between Stated Motor Valves
ML20246L5061989-08-31031 August 1989
Responds to Generic Ltr 89-12, Operator Licensing Exams
ML20246K2361989-08-28028 August 1989
Forwards, Effluent & Waste Disposal Semiannual Rept for Jan-June 1989, Revised Repts for 1988,1987 & 1985 & Revised Offsite Dose Calculation Manual
ML20246L3771989-08-23023 August 1989
Forwards Supplemental Response to NRC Re Violations Noted in Insp Repts 50-282/88-16 & 50-306/88-16. in Future,Outboard Check Valves Will Be Tested W/Upstream Vent & Motor Valves MV-32103 & 32105 Repositioned
ML20245L1911989-08-14014 August 1989
Submits Supplemental Info Re NRC Audit of Westinghouse Median Signal Select Signal Validation.Operability of Median Signal Select Function Will Be Demonstrated by Verifying That Failed Channel Not Selected for Use in Level Control
ML19332C8431989-08-11011 August 1989
Responds to NRC 890713 Ltr Re Violations Noted in Insp Repts 50-282/89-18 & 50-306/89-18.Corrective Actions:All Personnel Involved in Event Counseled on Importance of Following Procedures & Work Requests as Written
ML20246F4341989-08-11011 August 1989
Forwards Comments on SALP 8 Repts 50-282/89-01 & 50-306/89-01 Per 890629 Request.Addl Room Adjacent to Emergency Offsite Facility Ctr Classroom to Be Designated
ML20247Q8181989-07-31031 July 1989
Provides Supplemental Info in Response to 890612 Request Re NRC Bulletin 79-14, Consideration of Torsional Moments (Tms) Piping Mods. Future Mods Will Reflect Tms Where Calculations of Stresses Due to Occasional Loads Performed
ML20247H9111989-07-24024 July 1989
Forwards Response to Generic Ltr 89-08, Erosion/Corrosion- Induced Pipe Wall Thinning. Administrative Procedure, Defining Erosion/Corrosion Monitoring Activities,Issued on 890220 & NUMARC Recommendations Adopted
ML19332F3501989-07-20020 July 1989
Responds to NRC 890620 Ltr Re Violations Noted in Insp Repts 50-282/89-17 & 50-306/89-17.Corrective Actions:New Monthly Sampling Procedures Prepared Which Will Require Monthly Independent Samples Be Taken from Fuel Oil Storage Tank
ML20247D1851989-07-12012 July 1989
Provides Addl Info Re Molded Case Circuit Breaker Replacement,Per Insp Repts 50-282/88-201 & 50-306/88-201. Util Has Concluded That Replacement Breakers from Bud Ferguson Co Suitable for safety-related Purposes
1990-09-06
[Table view] |
Text
_____ __
o_ .
1 Northern States Power Company
(
414 Nicollet Mall Minneapoks. Minnesota 55401 Telephone (612) 330-5500 f
June 2, 1986 Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 LICENSE NOS. DPR-42 50-306 DPR-60 Information Related to Implementation of Generic Requirements - Plant Specific Review The purpose of this letter is to provide information reques-ted by the NRC Staff in s letter dated April 30, 1986 from Mr Dominic C DiIanni, Project Manager, Project Directorate
- 1, Division of PWR Licensing-A, USNRC.
Attached is the plant-specific list for the Prairie Island Nuclear Generating plant with the status of each item noted.
In some cases additional notes have been provided to provide more detailed status information. In other cases, additio-nal information is needed for us to identify the table entry. We will discuss these items with the NRR Project Manager for Prairie Island, Mr Dominic Dilanni, and attempt to get more detailed information concerning them.
Please contact us if you have any questions related to the information we have provided.
Dd du s David Musolf Manager Nuclear Support Services c: NRR Project Manager, NRC Hesident Inspector, NRC Regional Administrator, Region III, NRC G Charnoff sgae12888:8t8tlie2 Q **'
P J
. -r
~.
R-1208731-001 REGULAT0RY I !! F 0 R H A T I O N TRACKING SYSTEH PAGE N3.s .382 FACILITY IHPLENENTATICH 05/31/84 FACILITY: PRAIRIE ISLAND 1 PLAtlT LOCATI0tle 28 HI SE OF HIllNEAP'0LIS, HINN LICEllSED POWER: 1650 MHT PROJECT MANAGER: D. DIIAtlHI .
DOCKET flut1BER: 050-00282 DESIGN Poller: 0530 Mile BkANCN CHIEF: G. LEAR ARCN/ EllGIllEER : FPI NSS3 VENDORS llEST LIC. ASSISTANTS P. SHUTTLEHORTH IE IllSPECTOR: C. FEIERABEllD LIC ACT LICENSEE TAC No. HPA 8 TITLE COMPLETE STATUS DAIE H06336 A-01 10 CFR 50.55 A(G) - ISI 11/14/80C Note 1 11/80 (Complete)
MO8289 A-01 to CFR 50.55 A(G) - ISI 01/01/70C Note 2 --
H08151 A-02 APPENDIX I - ALARA 10/21/82C Note 1 1/83 (Complete)
H06949 A-03 SECURITY REVIEllS-HODIFIED AMENDHENT PLANS 03/14/79C --
3/79 (Complete)
H05250 A-04 APFEllDIX J - CollTAltlHElli LEAK TESTING 02/23/830 --
2/83 (Complete)
H06853 A-08 ECCS EVALUATI0ll-GEllERIC PER 50.46 COMPLIANCE 12/01/81C --
12/81 (Complete)
H11387 A-09 PRESSL'RE VESSEL BELTLIllE MATERIAL SURVEILLANCE 02/27/81C Note 2 --
M10398 A-10 CONTINGEllCY PL AtillIllG 02/25/81C Note 1 2/81 (Complete)
H10402 A-11 GUARD TRAINING PLAlis 02/25/81C Note 1 2/81 (Complete)
H10400 A-12 VITAL AREA AllALYSIS 04/12/82C Note 2 --
H11429 A-14 10CFR 50.55 A(G) - IllSERVICE TESTING 01/04/83C Note 1 1/83 (Complete)
H47399 A-16 QUALIFICATI0tlS OF EXAMINATION, INSPECTI0tl, TESTING 08/12/82C --
12/83 (Complete)
H51122 A-17 IllSTRUMEllTATION TO FOLLOH THE COURSE OF AN ACCIDEN 10/18/85C --
6/87 (Proj ected)
H55731 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 06/25/85C Note 1 6/85 (Complete)
H59130 A-20 10 CFR 50.62 OPERATIllG REAC10R REVIEHS N//S / --
5/87 (Projected)
H59974 A-21 10 CFR 50.61, PRESSURIZED THERHAL SHOCK RULE Note 3 1/86 (Complete)
- Mo&587 B-02 FIRE PROTECTIO!I 09/16/79C Note 4 6/85 (Complete)
H08394 B-03 PilR H0DERATOR DILUTIO!! 11/26/80C Note 2 --
N06620 B-04 REACTOR VESSEL OVERPRESSURE PROTECTIO.?! 01/01/70C Note 2 --
H06807 B-04 REACTOR VESSEL OVERPRESSURE PROTECTIO!I 08/03/79C Note 1 8/79 (complete)
NSP PAGE 1 OF 14 L
R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO.s .383 FACILITY IHPLEMENTATION 03/31/86 PRAIRIE ISLAtID 1 (CollTINUATION)
LIC ACT LICENSEE TAC t10. MPA e TITLE COMPLETE STATUS 'EalE N07278 B-07 STEAM GENERATOR FEEDilATER FLOH INSTABILITY 09/13/79C --
9/79 (Complete)
M08752 B-14 CEA GUIDE TUBE IIEAR 05/04/81C --
5/81 (Complese)
- M12348 B-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C Note 2 --
M08754 B-17 TECH SPEC SURVEILLAtlCE FOR HYDRAULIC SNUBBERS 10/28/81C Note 1 10/81 (Complete)
M10269 B-20 CollTAIllMENT LEAKAGE DUE 10 SEAL DETERIORATION 08/25/80C Note 2 --
M10333 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCIA 02/28/82C Note 2 --
M08756 B-22 TECH SPEC SURVEILLAtlCE REQUIREMENTS FOR MECHANICAL 08/14/81C Note 1 8/81 (Complete)
M08734 B-23 DEGRADED GRID VOLTAGE 07/28/31C Note 1 7/81 (Complete)
M10045 B-23 DEGRADED GRID VOLTAGE 01/01/70C Note 2 --
M10156 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 08/25/80C Note 2 --
M10157 B-24 VEllTIllO AllD PURGIllG CONTAIt4MENTS HHILE AT FULL PCH 01/01/73C Note 2 --
l M42592 B-24 VEllTING AND PURGING CONTAIllMENTS HHILE AT FULL PDH ' 09/09/82C --
9/84 (Complete)
M10231 B-26 INADVERTANT SAFETY IllJECTION DURING C00LDOHti 12/28/79C -- 12/79 (Complete)
B-32 BLOCKED SI SIGNAL DURING C00LD0llN 02/23/83C Note 2 --
M49429 B-39 PilR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C Mote 2 -
N08665 M49949 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 04/09/84C Note 2 --
B-41 FIRE PROTECTI0ll - FIllAL TECH SPECS (INCLUDES SER S 05/04/83C Note 5 5/83 (Conplete)
M11094 M13126 B-42 TMI FOLLDH UP - ALL PLANTS 06/15/81C Note 2 --
M11694 B-42 THI FOLLOH UP - ALL PLAtlTS 06/15/81C Note 2 -
'M11773 B-43 PilR FEEDHATER LIllE CRACKS 02/06/80C Note 2 --
M43147 B-43 PHR FEEDHATER LIllE CRACKS 05/25/82C Note 2 --
M30708 B-44 LESSONS LEARilED IMPLEMENTATION 04/18/80C Note 6 4/80 (Complete)
H30709 B-44 LESSails LEARilED IMPLEMEt4TATION 04/18/80C -- 4/80 (Complete)
I NSP PAGE 2 0F 14 1
R-1208731-001 REGULAT0RY INF0RHATION TRACKINO SYSTEM -
. PA2E NO.s .34 FACILITY IMPLEMENTATION 03/31/t6 PRAIRIE ISLAND 1 (CONTINUATION) !
LIC ACT LICENSEE TAC No. MPA 9 TITLE COMPLETE STATUS RME M30710 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
M30711 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
M30712 B-44 LESS0!IS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
M30713 B-44 LESSONS LEARNED IMPLEMENTATI0ft 04/18/80C --
4/80 (Complete)
M30714 B-44 LESS0lls LEARNED IMPLEMENTATION 04/18/80C -
4/80 (Complete)
M30715 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
M30716 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
M30717 B-44 LESSONS LEARilED If1PLEMENTATION 04/18/80C --
4/80 (Complete)
M30718 B-44 LESSONS LEARNED It1PLEMENTATION 04/18/80C --
4/80 (Complete)
M30719 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
M30720 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 (Complete) i M30721 B-44 LESSONS LEARNED IMPLEMENTATION 04/18/80C --
4/80 -(Complete)
M12932 B-45 llASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C Note 1 4/81 (Complete)
M42116 B-46 ANALYSIS OF TURBINE DISC CRACKS 04/01/81C Note 2 --
M12591 B-46 ANALYSIS OF TURBINE DISC CRACKS 09/01/81C --
10/81 (Complete)
M12683 B-47 ECCS; CLAD SHELLIllG AND RUPTURE 07/30/80C Note 2 --
M12966 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 10/29/82C --
10/82 (Complete)
M13038 B-49 PilR CONTROL ROD HISALIGNMENT 07/28/81C Note 1 7/81 (Complete)
- M11874 B-52 REVIEH OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10/23/80C Note 2 --
M42898 B-59 MASONRY HALL DESIGN 09/12/83C --
9/83 (Complete)
M42500 5-60 ENVIR0llMEllTAL QUALIFICATION 03/25/85C --
11/85 (Complete)
M42699 B-61 LOSS OF NON CLASS IE ISC PDHER 07/28/82C Note 2 --
M42770 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 04/30/81C Note 7 --
NSP PAGE 3 0F.14 L
R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO.s 385 FACILITY IMPLEMENTATION 03/31/85 PRAIRIE ISLAND 1 (CONTINUATIDH)
LIC ACT LICENSEE TAC 130. MPA 8 TITLE COMPLETE STATUS PAlf M43927 B-63 INTERIM PROCEDURES FOR Sii0RT TERM BLACK 0UT 01/22/82C --
1/82 (Complete)
M47150 B-66 flATURAL CIRCULATION C00LD0liti 07/18/83C -- 7/83 (Complete)
M46853 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDil 10/25/82C -- 10/82 (Complete)
M46630 B-70 FATIGUE TRANSIEllT LIMIT TS 05/25/82C Note 2 --
M49750 B-72 flUREG 0737 TECN SPECS (GENERIC LETTER 82-16) 01/15/83C Note 8 4/83 (Complete)
MS2789 B-76 ITEM 1.1 - POST TRIP REVIElls PROGRAM DESCRIPTION & 06/01/84C Note 9 8/85 (Complete)
M52870 B-77 ITEM 2.1 - EQUIPMElli CLASSIFICATION & VENDOR INTER 06/01/84C Note 2 --
M52951 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAlllTENAllCE TEST PROCEDU 06/01/85C Note 10 5/85 (Complete)
M53032 B-79 ITEM 3.1.3 - POST MAINTEllANCE TESTING - CHANGES TO 06/01/84C Note 11 10/85 (Complete)
M53089 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VEllDO 06/01/85C Note 10 5/85 (Complete)
M53142 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAIllT PROG FOR R 10/17/85C -- 10/85 (Complete)
M53188 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SNUNT TRIP ATTAC 06/01/84C --
3/85 (Complete)
M53622 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/01/84C Note 12 -- .
M53705 B-86 SALEM ATHS 2.2 S-R COMP 0HEllTS 06/01/84C Note 13 --
M53788 B-87 SALEM ATils 3.2.1 & 3.2.2 S-R COMPONENTS 05/13/85C --
5/85 (Complete)
M53871 B-88 SALEM AIlls 3.2.3 T.S. S-R COMPONENTS 06/01/84C --
10/85 (Complete)
M53929 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 10/31/86 Note 14 --
M55370 B-90 SALEM AlliS 4.3 H AND B&H T.S. 06/26/85C Note 2 6/85 (Complete)
, M54098 B-92 SALEM ATils 4.5.1 DIVERSE TRIP FEATURES 05/13/85C -- 5/85 (Complete)
'M54015 B-93 SALEM ATHS 4.5.2 3 4.5.3 TEST ALTERNATIVES 06/01/84C Note 14 M06486 C-01 PHR SECONDARY llATER CHEMISTRY MONITORING REQUIREME 03/28/78C Note 2 --
M07614 C-01 PilR SECollDARY llATER CHEMISTRY MollITORING REQUIREME 11/13/81C Note 2 11/81 (Complete)
M08748 C-06 PUMP SUPPORT-LAMELLAR TEARING 09/15/81C Note 15 --
A NSP PAGE 4 OF 14
REGULAT0RY INF0RHATION TRACKING SYSTEH PAGE No.: 386 R-1208731-001 FACILITY IHPLEHENTATION 03/31/86 .
, PRAIRIE ISLAND 1 (CONTINUATIDH)
LIC ACT LICENSEE i TAC HO. HPA 8 TITLE C0f1PLETE STATUS EAlf H08750 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINHENT 02/02/82C -- 2/82 (Complete)
N07298 C-09 PHR AUX FH PUHPS 08/14/80C Note 16 --
H08075 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 06/06/83C Note 17 6/83 (Complete)
+
H43657 C-14 AUXILIARY FEEDilATER SEISHIC QUALIFICATION 06/16/83C --
12/84 (Complete)
H52260 C-15 CONTROL OF HEAVY LOADS - Pl!ASE II (FOLLOHUP OF HPA 06/28/85C Note 18 6/85 (Complete)
H58080 C-16 UTILITY RESPONSES TO STAFF RECOHHENDATIONS CONCERN - Note 2 --
H07872 D-02 ECCS ZIRC CLAD H0 DEL ERROR-COMPLIANCE HITH 10 CFR- 04/20/79C Note 2 --
H07854 D-03 PRESSURIZ'R 2 HEATUP RATE ERROR 11/01/78C Note 1 11/78 (Complete)
H08351 D-05 PLANT UPI H0 DEL PROBLEH l t[j /j/Fj"c ***+ **** Note 2 --
H08751 D-10 ASYHHETRIC LOCA LOADS g-/g 42r24 469 Note 2 --
H08995 D-11 FISSION GAS RELEASE 02/22/80C Note 2 --
H12273 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEH FAIL 12/01/80C Note 2 --
H43033 D-17 DEFINITI0H OF OPERABLE 07/28/81C Note 1 7/81 (Complete)
H55892 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/06/85C Note 2 --
H10727 E-03 CORE RELOADS REQUIRIllG PRIOR HRC APPROVAL 04/27/79C Note 2^ --
H44050 F-01 I.A.1.1 SilIFT TECittlICAL ADVISOR 07/06/82C --
1/80 (Complete)
H44119 F-02 I.A.1.3 SHIFT HAHHING 04/06/83C -- 4/83 (Complete)
H44190 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 12/14/82C --
12/82(Complete)
H44261 F-04 I.C.1.2/3.A EHERGEllCY OPERATING PROCEDURES GENERIC 06/07/84C --
6/84 (Complete)
'H44331 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREO 04/61/86 Note 19 --
6 3 //o/ 9']
M47244 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 01/04/82C --
1/82 (Complete)
H47316 F-07 I.C.6 CORRECT PERFORHANCE OF OPERATING ACTIVITI 01/04/82C -- 1/82 (Complete)
H51192 F-08 I.D.1.1 DETAILED CONTROL R00H DESIGN REVIEH PROGRA 10/10/84C Note 20 --
l NSP PAGE 5 OF -14
/
R-1208731-001 REGULAT0RY INF0RHATION TRACKINO SYSTEH PA!E N0.8 387 FACILITY IHPLE!!ENTATION 03/31/86 PRAIRIE ISLAND 1 (CONTINUATIOH)
LIC ACT LICENSEE TAC fl0. HPA 8 TITIE COMPLEH STATUS PAH H51272 F-09 I.D.2 SAFETY PARAHETER DISPLAY SYSTEM 07/15/85C Note 21 12/86 (Projected)
H44398 F-10 II.B.1 RCS HIGH POINT VENTS 09/19/83C --
9/83 (Complete)
H47967 F-11 II.B.2 PLANT SHIELDING 10/12/83C --
10/83 (Complete)
H44469 F-12 II.B.3 POST ACCIDENT SAMPLING 11/23/83C Note 22 11/83 (Complete)
M44540 F-13 II.B.4 TRAINING FOR HITIGATING CORE DAMAGE 12/14/82C -
12/82 (Complete)
H44610 F-14 II.D.1 RV AND SV TRAINING 01/30/86 Note 23 --
H44647 F-15 II.E.1.1 AFH SYSTEH EVALUATION 03/22/82C Note 24 3/82 (Complete)
M42541 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 03/22/82C --
3/82 (Complete)
M44726 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 03/22/82C --
3/82 (Complete)
H44808 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 06/01/82C --
6/82 (Complete)
H44879 F-19 II.E.4.2 CollTAINHENT ISOLATION DEPENDABILITY 09/09/82C -- 9/82 (Complete)
H44950 F-20 II.F.1.1 NOBLE GAS H0HITOR 11/09/81C --
4/82 (Complete)
H45021 F-21 I I . F.1. 2 IODINE / PARTICULATE SAMPLING 11/09/81C --
9/82 (Complete)
H45092 F-22 II.F.1.3 C0ilTAIHHEHT HIGH RANGE MONITOR 01/28/82C --
2/82 (Complete)
M47628 F-23 II.F.1.4 CONTAlllHEHT PRESSURE INSTRUMENT 04/21/83C --
1/82 (Complete)
M47699 F-24 II.F.1.5 CONTAINHENT HATER LEVEL INSTRUMENT 04/21/83C - 12/81 (Complete)
H47770 F-25 II.F.1.6 CONTAIIIHEHT HYDROGEN HONITOR 04/21/83C --
12/81 (Complete)
H45162 F-26 II.F.2 INSTRUMEllTS FOR DETECTION ON INADEQUATE 07//f/(h Note 25 --
H46899 F-30 II.K.2.13 THERHAL-HECHANICAL REPORT 06/06/84C - 6/84 (Complete)
- l147813 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 12/30/83C --
12/83 (Complete)
H45244 F-36 II.K.3.1 AUTO PORV ISOLATION 09/16/83C --
9/83 (Complete)
H45290 F-37 II.K.3.2 REPORT OH PORV FAILURES 09/16/83C --
9/83 (Complete)
H45372 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 03/03/82C --
3/82 (Complete)
NSP PAGE 6 0F 14
/
TRACKINO SYSTEM PAGE NO. ',388 R-1208731-001 REGULATCRY INF0RHATION FACILITY IMPLEHENTATION 03/31/8)
PRAIRIE ISL AND 1 (CollTIllUATI0il)
LIC ACT .
LICENSEE COMPLETE STATUS PAIE TAC HO< MPA 8 TITLE .
02/08/83C Note 19 --
M45407 F-39 II.K.3.5 AUID TRIP OF RCPS 11/30/81C --
11/81 (Complete)
M45456 F-40 II.K.3.9 PID C0flTROLLER 11/30/81C -- 11/81 (Complete)
M45486 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 11/30/81C --
11/81 (Complete)
M45516 F-42 II.K.3.12 ANTICIPATORY TRIP DN TURBIllE TRIP 08/11/83C --
8/83 (Complete)
M45658 F-47 II.K.3.17 ECCS OUTAGES 06/17/82C -- 6/82 (Complete) l M48428 F-53 II.K.3.25 PONER ON PUMP SEALS 06/06/85C -- 6/85 (Complete)
M45855 F-57 II.K.3.30 SB LOCA METHODS 01/15/87 Note 27 4/86 (Complete)
M48194 F-58 II.K.3.51 COMPLIAllCE HITH to CFR 50.46 Note 28 12/83 (Complete M45974 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER y/f/f(CN 12/83 (Complete)
M46045 F-64 III.A.I.2 OPERATIONAL SUPPORT CENTER g&86 --
y /f/rtc 084fP86 Note 28 12/83 (Complete)
M46117 F-65 III.A.1.2 EMER0EllCY OPERATIDHS FACILITY NUCLEAR DATA LIllK 07/30/82C Note 2 --
M45189 F-66 III.A.1.2 05/13/83C -- 5/83 (Complete)
M46261 F-67 III.A.2.1 EMERGEllCY PLAN UPGRADE TO MEET RULE 12/83 (Complete)
M46333 F-65 III.A.2.2 METEOROLOGICAL DATA UPGRADE j/g(earsiiss --
03/02/82C -- 3/82 (Complete)
M46404 F-69 III.D.3.3 IMPLANT RADIATION MONITORING (Complete) 2/84 CONTROL ROOM HABITABILITY 04/09/82C __ .
M46473 F-70 III.D.3.4 4MW Note 29 --
M56154 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FDLLOllVP TO of//J~/7"C REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 44,4984 Note 19 --
M49663 G-01 M/1//rG NSP PAGE 7 0F 14 p
INF0RHATION TRACKINO SYSTEH PAGE N0.8 .389 R-1208751-001 REGULATORY IMPLEMENTATION 03/31/86 FACILITY FACILITY: PRAIRIE ISLAtID 2 LICENSED P0HER: 1650 MHT PROJECT MAtlAGER: D. DII AllNI PLAtli LOCATI0!l: 28 HI SE OF HINHEAPOLIS, HIHit 0530 Mile BRANCH CHIEF: G. LEAR 050-00306 DESIGN P0HER: P. ShUTTLEHORTH DOCKET NUllBER: NSSS VENDOR: HEST LIC ASSISTANT:
ARCH / EllGIllEER s FPI IE INSPECTOR: C. FEIERABEND LIC ACT LICENSEE TAC No, TITLE COMPLETE STATUS MIE MPA B A-01 10 CFR 50.55 A(G) - ISI 03/31/81C Note 2 --
H08309 10/21/82C Note 1 1/83 (Complete)
H08152 A-02 APPENDIX I - ALARA 03/14/79C --
3/79 (Complete)
H08758 A-03 SECURITY REVIEllS-HODIFIED AMENDHENT PLANS 02/23/83C --
2/83 (Complete)
H08729 A-04 APPENDIX J - CONTAINHENT LEAK TESTING 12/01/81C --
12/81 (Complete)
H08746 A-08 ECCS EVALUATION-GEllERIC PER 50.46 COMPLIANCE A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 05/19/80C Note 2 --
H11370 02/25/81C Note 1 2/81 (Complete)
H10399 A-10 CONTINGENCY PLANNING A-11 GUARD TRAINING PLANS 02/25/81C Note 1 2/81 (Complete)
H10403 A-12 VITAL AREA ANALYSIS 04/12/82C Note 2 --
H10401 A-14 10CFR 50.55 A(G) - INSERVICE TESTING 01/04/83C Note 1 1/83 (Complete)
H11223 QUALIFICATIONS OF EXAHINATION, INSPECTION, TESTING 08/12/82C --
12/83 (Complete)
H47400 A-16 10/18/85C --
6/87 (Projected)
H51123 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 06/25/85C Note 1 6/85 (Complete)
H55732 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43)
N//S / --
3/88 (Projected)
H59131 A-20 10 CFR 50.62 DPERATING REACTOR REVIEHS 10 CFR 50.61, PRESSURIZED THERHAL SHOCK RULE Note 3 1/86 (Complete)
H59975 A-21 09/16/79C Note 4 6/85 (Complete) i N08730 B-02 FIRE PROTECTI0li B-03 11/26/80C Note 2 --
- 08395 H PHR MODERATOR DILUTION 08/03/79C Note 1 8/79 (Complete)
H08338 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION B-07 STEAM GENERATOR FEEDHATER FLOH INSTABILITY 09/13/79C H07829 B-14 CEA GUIDE TUBE HEAR 05/04/81C H08753 NSP PACE 8 0F 14 b --*
SYSTEM PAGE H3.s.390 R-1208731-001 REGULAT0RY I N F 0 R H A T I O fl TRACKINO 03/31/86, FACILITY IMPLEMEilTATION PRAIRIE ISLAllD 2 (CollTIllUATIOff)
LIC ACT LICENSEE TTTLE COMPLETE STATUS I!Alf.
TAC HO. tif1_1 Note 2 --
EMERGENCY PL AHilIllG AtID REVISI0lis 04/01/81C H12349 B-16 10/28/81C Note 1 10/81- (Complete)
H08755 B-17 TECH SPEC SURVEILLAtlCE FOR llYDRAULIC SilUBBERS 10/02/80C Note 2 --
H10270 B-20 C0HTAIHMENT LEAKAGE DUE TO SEAL DETERIORATION 02/28/82C Note 2 --
H10334 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANHUllCIA 08/14/81C Note 1 8/81 (Complete)
H08757 B-22 TECH SPEC SURVEILLAllCE REQUIREMENTS FOR HECHANICAL 07/28/8tC Note 1 7/81 (Complete) .
M08755 B-23 DEGRADED GRID VOLTAGE 01/01/70C Note 2 --
M10044 B-23 DEGRADED GRID VOLTAGE 03/05/81C Note 2 --
M11330 B-24 VEHilllG AHD PURGIllG CONTAIHMEllTS HHILE AT FULL Poll 09/09/82C --
9/84 (Complete)
H42622 B-24 VEllTIllG AllD PURGIllG C0llTAIllMENTS HHILE AT FULL P0li 12/28/79C Note 2 --
H10232 B-26 IHADVERTANT SAFETY INJECTIDH DURIllG C00LDollH 02/23/83C Note 2 --
M49430 B-52 BLOCKED SI SIGilAL DURING C00LD0Hil 11/13/80C Note 2 --
M08680 B-39 Pi!R PRESSURE - TEMPERATURE LIMIT TECH SPECS 01/09/84C Note 2 --
M49950 B-41 FIRE PROTECTI0li - FIEAL TECH SPECS (IllCLUDES SER S 05/04/83C Note 5 5/83 (Complete)
Hf1095 B-41 FIRE PROTECTIDH - FIllAL TECH SPECS (INCLUDES SER S TMI FOLLOH UP - ALL PLAllTS 06/15/81C Note 2 --
M13127 B-42 THI FOLLOH UP - ALL PLANTS 06/15/81C Note 2 --
M11695 B-42 02/06/80C Note 2 --
M11774 B-43 PHR FEEDilATER LINE CRACKS PIIR FEEDHATER LINE CRACKS 05/25/82C Note 2 --
1143148 B-43 04/18/80C Note 6 4/80 (Complete)
H30722 5 44 LESS0!IS LEARilED IMPLEMEllTATI0li 04/18/80C --
4/80 (Complete
- l150723 B-44 LESSOUS LEARilED IMPLEl1EHTATIDH LESSONS LEARilED IMPLEMENTATI0tl 04/18/80C --
4/80 (Complete)
M30724 B-44 04/18/30C gg H30725 B-44 LESSONS LEARNED IMPLEMENTATION __
LESSullS LEARilED IMPLEMENTATION 04/18/80C 4/80 (Complete)
H30726 B-44 --
NSP PAGE 9 OF 14 O
s
R-1208731-001 REGULAT0RY INF0RHATION TRACKINO SYSTEH PAGE NO. - 391 FACILITY IHPLEHENTATION 03/31/8Ti PRAIRIE ISLAllD 2 (C0HTIllUATI0ti)
LIC ACT LICENSEE T A C 110. HPA 8 TITLE COMPLETE STATUS MIf, H30727 B-44 LESS0tlS LEARilED IMPLEMEllTATI0tt 04/18/80C --
4/80 (Complete)
H30728 B-44 LESS0!!S LEARilED IllPLEHENTATI0tt 04/18/80C --
4/80 (Complete)
H30729 B-44 LESSONS LEARHED IMPLEMEllTATION 04/18/80C --
4/80 (Complete)
H30730 B-44 LESS0HS LEARilED IMPLEMEllTATION 04/18/80C --
4/80 (Complete)
H30731 B-44 LESS0HS LEARllED IMPLEllEllTATI0li 04/18/80C --
4/80 (Complete)
H30732 B-44 LES50tlS LEARHED It1PLEf1ENTATI0!l 04/18/80C --
4/80 (Complete) 1130733 B-44 LESS0llS LEARHED IMPLEMEllTATIDH 04/18/80C --
4/80 (Complete)
H30734 B-44 LESS0llS LEARHED IMPLEMENTATION 04/18/80C --
4/80 (Complete)
H30735 B-44 LESS0tlS LEARilED It1PLEHEHTATION 04/18/80C (Complete) 4/80 H12933 B-45 IIASH 1400 EVEllT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C Note 1 4/81 (Complete)
H42117 B-46 AHALYSIS OF TURBIllE DISC CRACKS 04/01/81C Note 2 --
H12592 B-46 ANALYSIS OF TURBIllE DISC CRACKS 09/01/81C --
10/81 (Complete)
H12684 B-47 ECCS; CLAD SilELLIllG AtID RUPTURE 10/02/80C Note 2 --
H12947 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 10/29/82C --
10/82 (Complete)
H13039 B-49 PHR C0!ITROL ROD HISALIGilHENT 07/28/81C Note 1 7/81 (Complete)
H11875 B-52 REVIEH OF SAFETY ASPECT OF IllADVERTENT SAFETY ACTI 10/23/80C Note 2 --
H42899 B-59 MAS 0tlRY HALL DESIGH 09/12/83C --
9/83 (Complete)
H42501 B-60 EllVIR0tlHENTAL QUALIFICATION 03/25/85C --
11/85 (Complete)
H42700 B-61 LOSS OF 11011 CLASS IE I&C P0llER 07/28/82C Note 2 --
- H42771 B-62 ESF RESET CONTROL DESIGN DEFICIEllCY 04/30/81C Note 7 --
H43928 B-63 INTERIH PROCEDURES FOR Sil0RT TERM BLACKOUT 01/22/82C --
1/82 (Complete)
H47151 B-66 NATURAL CIRCULATI0il C00LD0HH 07/18/83C --
7/83 (Complete)
H46854 B-69 IEB 80-4 MAIHSTEAM LINE BREAK HITH CONTINUED FEEDH 10/25/82C --
10/82 (Complete)
NSP PAGE 10 0F 14
REGULAT0RY INF0RHATION TRACKING SYSTEH PAGE No.: 392 R-1208731-001 FACILITY IHPLEHEilTATION 03/31/86-PRAIRIE ISL AllD 2 (CONTIllUATION)
LIC ACT LICENSEE TITLE COMPLETE STATUS EALE TAC 110. HPA 8 M46631 B-70 FATIGUE TRANSIEllT LIMIT TS 05/25/82C Note 2 --
H49751 B-72 IlUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 01/15/83C Note 8 4/83 (Complete)
H52790 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 06/01/84C Note 9 8/85 (Complete) 1152871 B-77 ITEM 2.1 - EQUIPHENT CLASSIFICATION & VEllDDR INTER 06/01/84C Note 2 --
H53952 B-78 ITEMS 3.1.1 & 3.1.2 -POST HAINTEllANCE TEST PROCEDU 06/01/85C Note 10 5/85 (Complete)
H53033 B-79 ITEM 3.1.3 - POST HAINTENAllCE TESTIllG - CilANGES TO 06/01/84C Note 11 10/85 (Complete)
H53090 B-80 ITEM 4.1 - REACTOR TRIP SYSTEH RELIABILITY - VENDO 06/01/85C Note 10 5/85 (Complete)
H53143 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE HAINT PROG FOR R 10/17/85C --
10/85 (Complete)
H53189 B-82 ITEM 4.3 - AUTOMATIC ACTUATI0li 0F SilUNT TRIP ATTAC 06/01/84C -- 10/85 (Complete)
H53623 B-85 SALEM ATHS 1.2 DATA CAPABILITY 12/31/85 Note 12 --
H53706 B-86 SALEM ATils 2.2 S-R COMPollEllTS 06/01/84C Note 13 --
H53789 B-87 SALEH ATils 3.2.1 & 3.2.2 S-R COMPollEllTS 05/13/85C --
5/85 (Complete)
SALEH ATilS 3.2.3 T.S. S-R COMPONEllTS 06/01/84C -- 10/85 (Complete)
H53872 B-88 H53930 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMP 0llENTS 10/31/86 Note 14 --
B-90 SALEM ATHS 4.3 H AllD B8H T.S. 06/26/85C Note 2 6/85 (Complete)
H55371 B-92 SALEH ATHS 4.5.1 DIVERSE TRIP FEATURES 05/13/85C --
5/85 (complete)
H54099 H54016 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERilATIVES 06/01/84C Note 14 --
C-01 PilR SECollDARY HATER CllEHISTRY HONITORIl10 REQUIREME 11/13/81C Note 2 11/81 (Complete)
H08733 H08749 C-06 PUNP SUPPORT-LANELLAR TEARIl10 09/15/81C Note 15 --
2/82 (Complete)
H08751 C-07 FUEL IIAllDLIl10 ACCIDEllT INSIDE CONTAINHENT C-09 PilR AUX FH PUNPS 03/05/81C Note 16 --
H08747 06/16/83C Note 17 6/83 (Complete)
H08076 C-10 CollTROL OF llEAVY LOADS OVER SPENT FUEL POOL (PilASE AUXILIARY FEEDilATER SEISHIC QUALIFICATI0ll 06/16/83C --
12/84 (Complete)
H43658 C-14 NSP PAGE 11 0F 14
R-1208731-001 REGULAT0RY I !! F 0 R H A T I O N TRACKING SYSTEH PAGE No.s.393 FACILITY IHPLEHENTATION 03/31/46 PRAIRIE ISLAND 2 (CONTINUATION)
LIC ACT LICENSEE TAC H0. HPA 8 TITLE COMPL ETE STATUS EAlf H52261 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF HPA 06/28/85C Note 18 6/85 (Complete)
H58081 C-16 UTILITY RESP 0HSES TO STAFF RECOHHENDATIONS CONCERN Note 2 --
H07873 D-02 ECCS ZIRC CLAD H0 DEL ERROR-COMPLIANCE HITH 10 CFR- 04/20/79C Note 2 --
H07855 D-03 PRESSURIZER llEATUP RATE ERROR 11/01/78C Note 1 11/78 (Complete)
H08471 D-05 PLANT UPI H0 DEL PRUILLEM f 2 /.)//7.52* 997Hr84 Note 2 --
H08732 D-10 ASYMMETRIC LOCA LOADS ,fpf/pg -tAwaar Note 2 --
H08996 D-11 FISSIDH GAS RELEASE 02/22/80C Note 2 --
H12274 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 12/01/80C Note 2 --
H55893 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/06/85C Note 2 --
a H10904 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 04/20/79C Note 2 --
) H44051 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 07/06/82C --
1/80 (Complete)
H44120 F-02 I.A.1.3 SHIFT MANNING 04/06/83C --
4/83 (Complete)
H44191 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 12/14/82C --
12/82 (Complete)
M44262 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/07/84C --
6/84 (Complete)
H44332 F-05 I.C.I.2/3.B PROCEDURES GENERATION PACKAGES (NUREG th . Note 19 --
H47245 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 01/04/82C --
1/82 (Complete) 2 H47317 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVIII 01/04/82C --
1/82 (Complete)
H51193 F-08 I.D.1.1 DETAILED C0llTROL R00H DESIGN REVIEN PROGRA 10/10/84C Note 20 --
) H51273 F-09 I.D.2 SAFETY PARAHETER DISPLAY SYSTEM 07/15/85C N(.te 21 12/86 (Project 4d)
] 'H44399 F-10 II.B.1 RCS HIGil POINT VENTS 09/19/83C --
9/83 (Complete)
H47968 F-11 II.B.2 PLANT SHIELDING 10/12/83C --
10/83 (Complete)
H44470 F-12 II.B.3 POST ACCIDENT SAMPLING 11/23/83C Note 22 11/83 (Complete)
H44541 F-13 II.B.4 TRAINIllG FOR HITIGATING CORE DAMAGE 12/14/82C --
12/82 (Complete) l NSP PAGE 12 0F'14
4 R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE N0.8 . 394 FACILITY I M P L E M E N T A T I O 11 03/31/86 PRAIRIE ISLAllD 2 (CollTIllUATI0ll)
LIC ACT LICENSEE TAC 110. MPA 3 TITLE COMPLETE STATUS DAIE M44611 F-14 II.D.1 RV AllD SV TRAlllIllG 01/30/86 Note 23 --
M44648 F-15 II.E.1.1 AFH SYSTEM EVALUATION 03/22/82C Note 24 3/82 (Complete)
M44688 F-16 II .E.1.2.1 Afil SYSTEM IllITI ATI0li 03/22/82C --
3/82 (Complete)
M44727 F-17 II.E.1.2.2 AFil SYSTEl1 FLOll IllDICATIDH 03/22/82C --
3/82 (Complete)
M44809 F-18 II.E.4.1 DEDICATED llYDROGEN PEHETRATION 06/01/82C --
6/82 (Complete)
M44880 F-19 II.E.4.2 CollTAlllMEllT ISOL ATI0ll DEPENDABILITY ~09/09/82C --
9/82 (Complete)
M44951 F-20 II.F.1.1 fl0BLE GAS M0llITOR 11/09/81C (Complete) 4/82 M45022 F-21 II.F.1.2 IODINE /PARTICUL ATE SAMPLIllG 11/09/8tC (Complete) 9/82 M45093 F-22 II.F.1.3 CollTAIllMEllT HIGil RAllGE M0llITOR 01/28/82C (Complete) 2/82 M47629 F-23 II.F.1.4 CollTAIllMENT PRESSURE IHSTRUMENT 04/18/83C- --
1/82 (Complete)
M47700 F-24 II.F.1.5 CONTAIllMEllT llATER LEVEL IllSTRUMEllT 04/18/83C --
12/81 (Complete)
M47771 F-25 II.F.1.6 C0HTAIllHEllT HYDROGEN MONITOR 04/18/83C --
12/81 (Complete)
M45163 F-26 II.F.2 IllSTRUMEldTS FOR DETECTI0li 011 IHADEQUATE 87[/ N fI Note 25 --
M46900 F-30 II.K.2.13 TilERMAL-MECilANICAL REPORT 06/06/84C --
6/84 (Complete)
M47814 F-33 II.K.2.17 POTEllTI AL FOR VOIDIllG Ill RCS 12/30/83C --
12/82 (Complete)
M45245 F-36 II.K.3.1 AdTO PORV ISOL ATI0ll 09/16/83C --
9/83 (Complete)
M45291 F-37 II.K.3.2 REPORT Dil PORV FAILURES 09/16/83C --
9/83 (Complete)
M45373 F-38 II.K.3.3 REPORTIllG SV AllD RV FAILURES AND CHALLE 03/02/82C (Complete) 3/82 M45408 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/08/83C Note 19 --
M45457 F-40 II.K.3.9 PID C0!! TROLLER 11/30/81C --
11/81 (Complete)
M45487 F-41 II.K.3.10 AllTICIPATORY TRIP MODIFICATI0lis 11/30/81C --
11/81 (Complete)
M45517 F-42 II.K.3.12 AH'TICIPATORY TRIP DN TURBINE TRIP 11/30/81C --
11/81 (Complete)
M45659 F-47 II.K.3.17 ECCS OUTAGES 08/11/83C --
8/83 (Complete)
NSP PAGE 13 0F 14
R-1208731-001 REGULAT0RY INF0RHATIOH TRACKING SYSTEH PAGE No.:.391 FACILITY IflPLEHENTATION 03/31/8T PRAIRIE ISLAND 2 (CONTIllUATI0ll) s LIC ACT LICENSEE TAC H0. MPA 8 TITLE COMPLETE STATUS RAlf M48429 F-53 II.K.3.25 P0llER ON PUNP SEALS 06/17/82C --
6/82 (Complete)
M45856 F-57 II.K.3.30 SB LOCA METHODS 06/06/85C --
6/85 (Complete)
H48195 F-58 II.K.3.51 CollPLI ANCE lIITH 10 CFR 50.46 01/15/87 Note 27 4/86 (Complete) o k for /9'4 0 98f'-5tred M45975 F-63 III.A 1.2 TECilllICAL SUPPORT CENTER g g C, Note 28 12/83 (Complete)
H46046 F-64 III.A.1.2 OPERATI0llAL SUPPORT CENTER 48 4 g f.- ,
12/83 (Complete)
M46118 F-65 III.A.I.2 ENERGEllCY OPERATIONS FACILITY 96 1766 --
12/83 (Complete)
H46190 F-66 III.A.1.2 flUCLEAR DATA LIllK 07/30/82C Note 2 --
05/1 / C (Complete)
H46262 F-67 III.A.2.1 EMER0EHCY PLAll UPGRADE TO HEET RULE p (, --
5/83 H46334 F-68 III.A.2.2 NETEOROLOGICAL DATA UPGRADE 4 im --
12/83 (Complete)
H42405 F-69 III.D.3.3 IMPLANT RADIATI0ll MONITORING 03/02/82C --
3/82 (Complete)
H46474 F-70 III.D.3.4 CONTROL ROOH HABITABILITY 04/09/82C --
2/84 (Complete)
H56155 F-71 I.D.1.2 DETAILED CollTROL R00H REVIEll (FOLLOHUP TD p(se40xtsw ag /fr/y & NOLe 29 --
i H49664 G-01 REACTOR COOLANT PUIiP TRIP (D660 - II.K.3.5) GW t*19" N*** l9 ~~
of,lt./)'f(
NSP PAGE 14 0F 14
Notes:
- 1. This item was a license amendment, ASME Code Section XI relief request approval, or other required NRC approval item. The item can be considerer " complete" on the date licensing action was complete (i.e. the date in the "Lic Act Complete" column is also appropriate for the " Licensee Date" column.
- 2. Not enough information is provided for this item and we cannot readily identify it.
- 3. Required action completed. Awaiting NRC review.
- 4. Correct date is 9/6/85.
- 5. This item is NRC SER on Appendix R exemption requests.
- 6. It is not clear if these are separate requirements. All Category A TMI Short Term Program Items complete by 4/80, however.
7.
to beThe date of the NRC SER related to this issue is believed 8/23/82. By letter dated 3/7/86, NSP requested a deviation from the NRC Staff findings in this SER. NRC Staff review in ongoing. Other requirements related to this issue are complete.
- 8. Generic Letter 82-16, 9/20/82, Technical Specification changes requested on 1/14/83 and issued by NRC on 4/6/83.
- 9. NRC SER date is 8/5/85.
10.NRC SER date is 5/13/85.
11.NRC SER date is 10/18/85.
- 12. Action is complete. Additional commitments to computer logging made by NSP to be completed by 1989. No NRC SER issued yet.
13.INPO NUTAC report issued. We believe no further actions are needed. NRC review not completed.
- 14. Undergoing NRC Review.
15.The date cannot be identified. Generic Issue A-12 has been resolved by the Commission and this item is considered complete with no backfit requirements (NUREG-0577, Revision 1).
16.It is unclear what this item specifically refers to. The auxiliary feedwater system was thoroughly reviewed under the TMI Action Plan at a later date. Required action was
completed or sceduled for integration with control board human factors modifications.
- 17. Phase I only.
- 18. Phase II dropped by NRC.
- 19. Awaiting NRC review. Procedures complete and in use at plant.
- 20. Detailed Control Room Design Report submitted 12/85.
Awaiting NRC review. Modifications scheduled out to 1990.
- 21. Safety Parameter Display System to be installed by 12/86.
- 22. Complete. Procedures and training being improved based on quality assurance audit.
- 23. Analyses and modifications complete. Awaiting NRC review.
- 24. Complete with exception of control board indicator improvements being integrated human factors modifications.
- 25. Complete with exception of upgraded display units.
- 26. SER is dated 6/11/84 not 6/6/84.
- 27. Small break LOCA analysis found acceptable in SER dated 4/3/86 based on previously approved model (NOTRUMP SER dated 6/6/85).
- 28. Complete with exception of enhancement with SPDS and Regulatory Guide 1.97, Revision 2, instrumentation.
- 29. Report Submitted. Undergoing NRC Staff review.
