Letter Sequence Request |
---|
|
|
MONTHYEARML19253C8481979-11-30030 November 1979 Forwards Evaluation of Electrical & Mechanical Penetration Seals & Fire Detectors Required by 790906 Fire Protection Safety Evaluation Rept Project stage: Request ML20125B9811979-12-26026 December 1979 Forwards Addl Info in Form of Design Details,Test Results Acceptance Criteria in Response to Section 3.1 of NRC 790906 Fire Protection Safety Evaluation to Assure Acceptability of Mod Design.Requests NRC Comment by 800301 Project stage: Other ML20051J6051982-05-0404 May 1982 Monthly Operating Repts for Apr 1982 Project stage: Request ML20054K8731982-06-30030 June 1982 Forwards Fire Protection Safe Shutdown Analysis Compliance w/10CFR50,App R Section Iii.G & Substantive Basis for Exemption Requests Project stage: Other ML20063E6481982-08-23023 August 1982 Provides Addl Info in Support of Util 820520 Request for Relief from Schedule for Completion of 10CFR50,App R, Section Iii.J Re Emergency Lighting Mods.Mods Will Be Implemented by 830101 Project stage: Request ML20063M1371982-09-0202 September 1982 Highlights Fire Protection Safe Shutdown Analysis in Compliance W/10CFR50,App R Section Iii.G & Substantive Basis for Exemption Request, Submitted on 820630.Equivalent Protection Issue Clarified to Expedite NRC Review Project stage: Other ML20070C7041982-12-0606 December 1982 Requests Exemption,Under 10CFR50.48(c)(b),from Automatic Suppression Requirement of App R,Section III.G.3 for Control Room Project stage: Other ML20072C8491983-02-17017 February 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.10 Re Offsite Surveys,Epip 1.1.11 Re Accident Assessment & EPIP 1.1.14 Re Vendor & Consultant Svcs Project stage: Request ML20069B7661983-03-11011 March 1983 Requests Relief from Fixed Suppression Sys Installation Requirement of 10CFR50.48,Paragraph B,For Fire Areas 58,59, 73 & 74 Project stage: Other ML20076D6331983-05-16016 May 1983 Forwards Clarifying Info in Support of 830311 Exemption Requests for 10CFR50.48,App R Re Fire Areas 58,59,73 & 74 Project stage: Other ML20077N3151983-09-0202 September 1983 Confirms 830823 Telcon Info Re Exemption Request for Fire Areas 58,59,73 & 74.Train a Safe Shutdown Cable Trays Will Be Wrapped W/Approved 1 H Rated Matl.Util Reviewing Matls for Use as 1 H Fire Barrier Project stage: Request 1982-08-23
[Table View] |
|
---|
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* a Northern States Power Company 414 Nmokt Man Minneapoks. Minneseta 55401 Telephone (612) 330 5500 August 23, 1982 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washingtna, DC 20555 PRAIRIE ISLAND NUCLEAR CENERATING PLA?TT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Additional Information Provided in Support of May 20, 1982 Request for Relief from the Specified Schedule for Completion of 10 CFR Part 50, Appendix R, Section III.J Emergency Lighting Modifications In our letter dated May 20, 1982 we requested additional schedule relief from the requirements of 10 CFR Part 50, Section 50.48(c), for the instal-lation of emergency lighting required by Section III.J of Appendix R. An extension until January 1, 1983 was requested for both units. In a letter dated July 29, 1982 from Mr Robert A Clark, Chief, Operating Reactors Branch
- 3, Division of Licensing, we were informed that the requested extension could not be granted because an inadequate explanation ~was offered for "...
why it was not determined much earlier in the process that plant shutdown would not be required to complete this requirement for emergency lighting".
We were asked to submit a complete and detailed chronology of our efforts to implement Section III.J, commencing with the publication of the Fire Protection Rule on November 17, 1980 to the present, and justify, in detail, the schedule requested in our thy 20, 1982 letter. The purpose of this letter is to provide additional information in support of our exemption request, including a detailed chronology of our efforts to implement Section III.J of Appendix R.
Appendix R Rulemaking The Commission published on November 19, 1980 a revised Section 50.48 and a new Appendix R to 10 CFR Part 50 pertaining to fire protection require-ments at operating nuclear generating plants. Two categories of require-ments were contained in the new regulation. One category dealt with requirements that were applicable only if the NRC Staff had not previously reviewed and found acceptable the action taken by a licensee to meet estab-lished fire protection positions. The other category dealt with three re-quirements that were to be backfit by all licensees, regardless of whether 11
{
{)() ,
or not alternative plant features were in place and found acceptable by the ffRC Staff. Appendix R,Section III.J, 8208300326 820823 PDR ADOCK 05000282 F PDR
\
e* e Dircctor of NRR August 23, 1982 Page 2 Emergency Lighting, was in the category of requirements to be backfit by all licensees. Appendix R, Sections III.G, Fire Protection of Safe Shut-down capability, and Section III.0, 011 Collection System for Reactor Coolant Pump, were the other requirements to be backfit.
At Prairie Island the NRC Staff had reviewed and found acceptable all plant fire protection measures and planned modifications necessary to meet their eatablished positions, with the exception of the safe shutdown analysis and alternate shutdown capability. New requirements contained in Appendix R,Section III.G, supersede these requirements (Reference 1). This shows an early appreciation at Prairie Island for an effective fire protection pro-gram and a willingness to cooperate fully with the NRC Staff in implementing necessary improvements.
Requirements of Section III.J As noted above, the requirements of Appendix R,Section III.J. Emergency Lighting, were backfit to all licensees regardless of any other provisions included in the original plant design or added later to meet the require-ments of the NRC Staff.
Section III.J of Appendix R requires:
Emergency lighting units with at least an eight-+our battery power supply shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes thereto.
The backfit provisions contained in the final rule for items previously found acceptable by the NRC Staff were completely unexpected by Northern States Power Company and other licensees. No notice was given of the in-tention of the Commission to include this feature in the regulation and no opportunity was provided to offer comments on this action.
During their review of the lighting systems provided at Prairie Island, the NRC Staff had found that "...the existing lighting system, when aug-mented by the portable handlights to be provided in the centralized fire equipment storage locker, satisfies the objectives identified in Section 2.2 of this report, and is therefore, acceptable" (Reference 2). In addi-tion to normal plant lighting, an emergency lighting s" stem was provided in the original plant design to light major areas of the plant except for the control room. This emergency lighting system is supplied from 120/208-volt minumum interruptible bus with automatic transfer to one of the 125-volt batteries upon failure of the AC supply. Batteries are main-tained fully charged by the diesel generators and can supply emergency lighting for an indefinite period. Separate battery powered lighting was provided in the control room as well as AC lighting supplied by the diesel generators, k
Dir:ctor cf NRR August 23, 1982 Page 3 Action Taken Following Publication of Appendix R For several months following the publication of Appendix R, we believed the existing emergency lighting system, with minor modifications, would satisfy the requirements of Section III.J. As noted above, the existing emergency lighting is automatically transferred to the plant DC system. The diesel generators, via the battery chargers, provide well in excess of the required eight-hour capability.
In a letter dated March 19, 1981 (Reference 3) we stated:
The existing system will be evaluated and modifications made to provide each area needed for operation of safe shutdown equipment, including access and egress routes, with DC lighting. For each light, the DC source will either be the station battery and its associated battery charger (which can supply essential lighting indefinitely) or another eight-hour battery source. The auxiliary building special ventilation zone airlocks are small (four to ten feet in length and four feet wide). They do not constitute an access or egress route within the meaning of Section III.J.
On April 9,1981 a review by the plant electrical group concluded that the installed emergency lighting system met the requirements of Appendix R,Section III.J, as interpreted by the group.
In a letter dated July 13, 1981 (Reference 4) we received additional infor-mation related to the NRC Staff's interpretation of the requirements of Section III.J. In responding to an exemption request submitted for our Monticello Plant (Monticello has a limited DC lighting system and an es-sential AC lighting system, all ultimately supplied from the diesel genera-tors), the NRC Staff stated that such a system was not acceptable unless it could be shown that "a postulated fire in one area of the plant could not cause the loss of lighting in another area which would aid access to or permit operation of equipment and components necessary to effect safe plant shutdown". This interpretation of the Section III.J requirements makes it impractical for any permanently wired emergency lighting system to meet the requirements of the regulation.
Efforts to comply with Section III.J were redirected to procuring and in-stalling satisfactory local battery powered lighting units.
Installation of Lighting Units and Request for Schedule Relief On August 10, 1981 the plant engineer, assigned the responsibility of in-stalling the lighting units required by Section III.J, contacted the local representative of Teledyne Company to determine the availability of equip-ment meeting the eight-hour requirement. A catalog was received on August 17, 1981 and followup contacts with the vendor were made. Discussions
Dir&ctor of NRR August 23, 1982 Page 4 centered on the requirement for seismic qualification of the units. On September 11, 1981 a copy of a Wyle Laboratories seismic simulation test was received for Teledyne lighting units which appeared to meet our require-ments. In September, an appropriation request was submitted for Capital Budget Review Committee approval to complete the installation of Section III.J and other Appendix R backfit modifications.
Work continued through September, October, and November on the Section III.G evaluation to identify equipment and cables needed for safe shutdown in the event of fire in any area of the plant. A review of the routing of emergency lighting cables at this time confirmed our earlier belief that the system was vulnerable to damage from fire in certain plant areas.
On November 16, 1981 (Reference 5 and 6) Northern States Power Company informed the NRC that the plans ou lined in our March 19, 1981 letter for using the installed emergency lighting _ system to meet the requirements of Section III.J were being abandoned. It was stated that "...we will pro-ceed with the purchase and installation of eight-hour battery powered lighting units to satisfy the requirements of Appendix R,Section III.J".
An exemption request was included in this submittal to extend the time allowed to complete this work until the 1982 refueling outage of each unit.
When we prepared our November 16, 1981 exemption request, the safe shut-down analysis had not progressed to the point where all locations for operation of safe shutdown equipment (in accordance with the new require-ments of Appendix R,Section III.G) had been finalized. It was felt that several areas requiring emergency lighting would be in parts of the plant where radiation levels or the presence of critical plant equipment made it imprudent to perform modification work during plant operation.
On December 18, 1981 NSP submitted the Section III.G safe shutdown analysis for Prairie Island (Reference 7). In January, 1982 we were informed through utility group contacts and discussions with our Project bbnager in the Division of Licensing that recurring deficiencies in safe shutdown submittals were being noted by the NRC Staff. Several such deficiencies in the Prairie Island report wsre identified during a telephone conference call with members of the NRC Staff. On February 5,1982 (Reference 8) we requested additional schedule relief for the purpose of re-submitting the Section III.G safe shutdown report to permit these deficiencies to be corrected.
It should be noted that, strictly speaking, locations for emergency lighting units cannot be finalized until the Section III.G analysis has been com-pleted and found acceptable by the NRC Staff.
On February 24, 1982 representatives from Teledyne toured the plant and, based on criteria available at that time, concluded that 43 lighting units were needed in the main portion of the plant and five units were needed in the screen house.
L
DirOctor of NRR August 23, 1982 Page 5 Work continued through February, March, April, and May on the revised Section III.G safe shutdown report (actually the fourth such report prepared and sub-mitted to the NRC to address evolving requirements). On April 28, 1982 funding for Prairie Island Appendix R modification projects, including emergency lighting, was approved by the Board of Directors. Total modifi-cation costs were expected to be several million dollars.
In April, 1982 in discussions with our Project Manager in the Division of Licensing we learned that the NRC Staff would soon approve the schedule exemp-tions we had requested to complete modifications required by Sections III.G and III.J. It was clear at this point that the original schedule we proposed for completing Section III.J modifications in unit 2 (1982 refueling outage) could not be met. This information was conveyed to our Project Manager.
Through further discussions we were told that the Appendix R schedule exemp-tion approval would be issued as written (requiring Unit 2 Section III.J modifications to be completed during the June, 1982 refueling outage) and that Northern States Power Company could reouest additional schedule relief following receipt of the exemption request approval. The Appendix R schedule exemption approval was issued by the commission on May 4, 1982 (Reference 8).
Accompanying the !by 4,1982 approval was the most definitive guidance re-ceived to date for performing the safe shutdown analysis required by Section III.G.
On May 20, 1982 (Reference 9) Northern States Power Company submitted a second schedule exemption request for completing the Section III.J Emergency Lighting Modifications. At this time the Section III.G Safe Shutdown Analysis was nearing completion and areas of the plant needing emergency lighting were well defined. The plant staff determined that all of these areas could be worked in during plant operation with acceptable risk of disruption of critical plant equipment and acceptable radiation exposures. The May 20, 1982 exemption request asked for an extension in the time allowed for com-pleting Section III.J modifications to January 1, 1983 in accordance with Section 50.48(c)(3) in both units. There was no longer a need to coordi-nate the completion schedule with a refueling outage.
Early in May we had discussions with the lighting equipment vendor related to difficulties with obtaining seismic batteries for the lights. The foreign supplier of batteries used in the seismically qualified units was no longer a reliable source. The decision was made at this time to purchase standard lead-acid batteries with the option to later replace them with seismically qualified batteries. The rest of the unit would be seismically qualified (i.e. it would not fall off its mounting during a seismic event and possibly damage safety-related equipment located below it). Fully qualified seismic lighting units, while desirable, were not required by Section III.J.
Dirsctor cf NRR August 23, 1982 Page 6 On June 1, 1982 the final location and mounting of each of the lighting-units was established by the plant technical staff. An order'was placed with the vendar on June 8,1982. Earliest possible delivery was requested.
On June 29, 1982 the vendor's representatives, again, toured the plant and finalized installation specifications. The first shipment of. mounting brackets was received on July 14,.1982. On July 22, 1982 markup drawings were prepared for installation activities. Several changes were required -
due to mounting interferences. On July 23, 1982 batteries and the second-
' shipment of mounting brackets were received and nine additional lighting units ordered that were determined necessary from detailed review of mounting areas. -Final work on the design change package is now in progress.- This package should -be completed, reviewed, and approved by the Operations Com-mittee by the end of the month. Depending on manpowe; tvailability, instal-lation work could begin in Unit 2 as early as the first week in September.
Additional workers will be available during the Unit 1 outage later this year and all battery powered lighting units in both units will be-installed and tested by January 1, 1983.
Summary In summary, we believe Northern States Power Company has made a good faith effort to comply with all of the backfit requirements of Appendix R to 10 CFR Part 50, including Section III.J, Emergency Lighting. Our requested schedule exemption request for completion of Section III.J modifications by January 1, 1983 is a reasonable and necessary request and should'be granted by the Commission. As noted above,'the primary reasons why an extension in completion schedule is justified are:
- a. The backfit provisions of Appendix R were totally unexpected, and many portions.of the regulation were difficult to understand and subject to differing interpretation. For several months we believed our installed DC emergency lighting system, pre'viously found accep-table by the NRC Staff, satisfied the requirements of Section III.J.
- b. The safe shutdown analysis performed to meet the requirements of Section III.G of Appendix R was continually delayed by problems in interpreting the requirements of the regulation. . Definitive guidance from the NRC Staff evolved over an 18-month period.
Locations and numbers of lighting units could not be established until the Section III.G analysis was nearing ccnpletion.
- c. Difficulties in defining qualification requirements were experienced with the lighting unit vendor.
'.7u w c+-' +t-+n-- +-
5:~ y e-- -- T- r --
s w
Director of NRR-August 23, 1982 Page 7'
-Actions are now underway to complete the modifications required by.Section-III.J by January 1, 1983 in accordance.with our May 20, 1982 exemption request.
Please contact us if you require further information related to the infor-mation we have provided, ni David Musolf Manager of Nuclear Suppo t Services DMM/ dab cc Secretary of the.._ Commission Regional Administrator - III, NRC NRC Resident Inspector NRR Project Manager, NRC G Charnoff i
s 3
Director of NRR August 23, 1982 Page 8 References
- 1. Letter dated November 24, 1980 from Darrel G Eisenhut, Director, Divi-sion of Licensing, to /.11 Power Reactor Licensees with Plants Licensed Prior to January 1, 1979.
- 2. Letter dated September 6, 1979 from A Schwencer, Chief, Operating Reactors Branch #1, Division of Operating Reactors, to L 0 Mayer, Northern States Power Company, (Amendment 39 to DPR-42 and Amendment 33 to DPR-60); Fire Protection Safety Evaluation Report.
- 3. Letter dated March 19, 1981 from L 0 Mayer, Northern States Power Company, to Director of Nuclear Reactor Regulation, USNRC, " Plans and Schedules for Meeting the Provisions of Paragraphs 50.48(c)(2),
(c)(3), and (c)(5) of 10 CFR Part 50; Fire Protection Modifications".
- 4. Letter dated July 13, 1981 from Thomas M Novak, Assistant Director for Operating Reactors, Division of Licensing, Office of Nuclear Reactor Regulation, USNRC, to L 0 Mayer, Northern States Power Company.
- 5. Letter dated November 16,1981 from L 0 Mayer, Northern States Power Company, to Director of Nuclear Reactor Regulation, USNRC, " Request for Relief from the Requirements of 10 CFR Part 50, Sections 50.48(c)(2),
(c)(3), and (c)(5); Schedule for Completion of Appendix R,Section III.J, Emergency Lighting Modifications".
- 6. Letter dated December 1,1981 f rom L 0 Mayer, Northern States Power Company, to Director of Nuclear Reactor Regulation, USNRC, " Correction to Request for Relief dated November 16, 1981".
- 7. Letter dated December 18,1981 from L 0 Mayer, Northern States Power Company, to Director, Of fice of Nuclear Reactor Regulation, USNRC,
" Fire Protection Safe Shutdown Analysis and Compliance with Section III.C of 10 CFR Part 50, Appendix R, Including Requests for Relief".
- 8. Letter dated May 4, 1982 from Dominic C Di Ianni, Project Manager, Operating Reactors Branch #3, USNRC, to L 0 Mayer, Northern States Power Company, " Exemption Request - Fire Protection Rule Schedular Requirements of 10 CFR 50.48(c) - Prairie Island Nuclear Generating Plant, Units 1 and 2.
- 9. Letter dated May 20, 1982 from L 0 Mayer, Northern States Power Company, to Director, Office of Nuclear Reactor Regulation, USNRC, " Request for Relief from the Requirements of 10 CFR Part 50, Section 50.48(c)(3),
Schedule for Completion of Appendix R Section III.J, Emergency Lighting Modifications.
E ;