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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20195G4281999-06-0909 June 1999 Notifies That Amsac/Dss Mods Completed & TS 138/129 Has Been Fully Implemented 05000282/LER-1999-005, Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved1999-06-0707 June 1999 Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved ML20207F4301999-06-0101 June 1999 Forwards 1999 Unit 1 SG Insp Results,Per TS 4.12.E.1. Following Insp 84 Tubes Were Plugged for First Time ML20196L2461999-05-21021 May 1999 Forwards Rev 0 to COLR for Pingp,Unit 1 Cycle 20, IAW TS Section 6.7.A.6 ML20195C6861999-05-21021 May 1999 Forwards Rev 17 to USAR for Prairie Island Nuclear Generating Plant.Attachment 1 Contains Descriptions & Summaries of SEs for Changes,Tests & Experiments Made Under Provisions of 10CFR50.59 During Period Since Last Update ML20206U6781999-05-17017 May 1999 Forwards Revised Emergency Response Plan Implementing Procedures,Including Rev 15 to F3-3,rev 15 to F3-16,rev 14 to F3-22 & Table of Contents ML20206U7131999-05-17017 May 1999 Forwards Revised EOF Emergency Plan Implementing Procedures, Including Table of Contents & Rev 2 to F8-10, Record Keeping in Eof. with Updating Instructions ML20206T2461999-05-17017 May 1999 Forwards Off-Site Radiation Dose Assessment for Jan-Dec 1998, Rev 0 to Annual Radiactive Effluent Rept for 980105- 990103 & Effluent & Waste Disposal Annual Rept Solid Waste & Irradiated Fuel Shipments,Jan-Dec 1998 ML20206R0401999-05-13013 May 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Removing Plant Organization Requirement,Imposed in Amend 141/132 That Plant Manager,Who Has Responsibility for Overall Safe Operation of Plant,Report to Corporate Officer ML20206Q0871999-05-13013 May 1999 Forwards Result of Evaluation Re Ultrasonic Exams of SG Number 22 Performed in Accordance with ASME Boiler & Pressure Vessel Code Section Xi.Procedure Used for Evaluation Contained in WCAP-14166,submitted for Review ML20206F9381999-05-0303 May 1999 Forwards Response to NRC 990304 RAI Re GL 96-05 Program at Pingp.Licensee Commitments Are Identified in Encl as Statements in Italics ML20206J3851999-05-0303 May 1999 Forwards 1998 Annual Radiological Environmental Monitoring Rept 05000282/LER-1999-004, Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics1999-05-0303 May 1999 Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics ML20206E1761999-04-28028 April 1999 Forwards Revised TS Pages for Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively,to Update Controlled Manual or File ML20205S3221999-04-20020 April 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements of TS 5.1 ML20205P9891999-04-12012 April 1999 Requests Approval for Proposed Alternatives to Liquid Penetrant Requirements of N-518.4 of 1968 ASME Boiler & Pressure Vessel Code.Results of Analysis & Summary of Tests Performed & Tests Results Are Encl ML20205Q0191999-04-12012 April 1999 Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR 05000282/LER-1998-010, Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER1999-04-0808 April 1999 Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER ML20205P9221999-04-0101 April 1999 Submits Relief Request 8,rev 0 Which Addresses Limited Exams Associated with Unit 2 Third ten-year Interval Inservice Insp Program.Util Requests Relief Per 10CFR50.55a(q)(5)(iii) Due to Impracticality of Obtaining 100% Exam Coverage ML20205E8371999-03-31031 March 1999 Submits Four Copies of Rev 38 to Prairie Island Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Security Plan.Encl Withheld,Per 10CFR73.21 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205Q5051999-03-30030 March 1999 Forwards Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327- 981229. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarized Results ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20204H3371999-03-19019 March 1999 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection 1999-09-07
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1 l Northern States Power Company l 1 l Prairie Island Nuclear Generating Plant ;
l 1717 Wakonade Dr. East Welch, Minnesota 55089 l
August 19,1999 10 CFR Part 50 Section 50.55a U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 I
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos.50-282 License Nos. DPR-42 50-306 DPR-60 j Request for Relief No. 8 for the Unit 13rd 10-year interval inservice inspection Program On August 5,1994 we submitted for review our third 10-year Inservice Inspection Examination Plan for Unit 1 and, on March 28,1995, a response to a request for additionalinformation to that plan. The NRC issued its evaluation of the 3rd 10-year Interval Program Plan on February 22,1996 The purpose of this letter is to submit a relief request for " limited examinations" associated with that plan. Attached is Unit 1 Relief Request No. 8, Revision 0 which addresses those limited examinations. We are requesting relief pursuant to 10 CFR Part 50, Section 50.55a(g)(5)(iii) due to the impracticality of obtaining "100%"
examination coverage for the affected items.
In this letter we have made no new Nuclear Regulatory Commission commitments.
Please contact Jack Leveille (651-388-1121, Ext. 4142) if you have any questions l
related to this letter. '
- W Joel P. Sorensen l Site General Manager x .)
Prairie Island Nuclear Generating Plant ,
ND g
\
c: (see next page) 7 gg 9908250103 990819 PDR ADOCK 05000282 G PDR i
l
. 4 USNRC NORTHERN GTATES POWER COMPANY l August 19,1999 Page 2 - l l
l c: Regionai Administrator- Region 111, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silbarg
Attachment:
ISI Relief Request No. 8 (Rev. 0) l l
I U2RP8RO. DOC l
NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN ISI Relief Request No. 8 (Rev. 0)
Limited Examination SYSTEM: Various Class: 1 and 2 Category: Various item: Various impractical Examination Reauirements:
ASME Section XI (1989 no addenda) Code requires full examination of inservice inspection (ISI) components per Table IWB-2500-1, and lWC-2500-1. Reg. Guide 1.147 endorses Code Case N-460,"Altemative Examination Coverage for Class 1 and Class 2 Welds." This code case allows greater than 90% coverage of a weld to meet the " essentially 100%" requirement.
NRC Information Notice 98-42 " Implementation of 10 CFR 50.55a(g) Inservice inspection requirements" Dec.1,1998, states "The NRC has adopted and further refined the definition of "" essentially 100 percent"" to mean greater than 90 percent " in 10 CFR 50.55a(g)(6)(ii)(A)(2) for required examination coverage of reactor pressure vessel welds. This standard has been applied to all examination of welds or other areas required by ASME Section XI.
The Prairie Island construction permit was issued in 1967. This facility was designed and constructed with limited accessibility due to component configurations and/or physical barriers for which 100% coverage is not achievable on some ISI components examined for the Third Ten Year Interval.
Basis for Relief: l The following 10 CFR 50.55a paragraphs apply to the inservice inspection of components in accordance with the ASME Section XI code:
50.55a(g)(1): For a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued prior to January 1,1971, components (including supports) must meet the requirements of paragraphs (g) (4) and (5) of this section to the extent practical.
50.55a(g)(4): Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and pre-service examination requirements, set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code . . to the extent practical l within the limitations of design, geometry and materials of construction of the components.
50.55a(g)(5)(iv): Where an examination requirement by the code or addenda is determined to be impractical by the licensee and is not included in the revised inservice inspection program as permitted by 4 paragraph (g)(4) of this section, the basis for this determination must be demonstrated to the satisfaction i of the Commission ... j l
Page 1 of 20 L .
' NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Prairie Island was designed and constructed prior to development of ASME XI ,
therefore design for accessibility and inspection coverage is not in many cases, sufficient to permit satisfying the current Code requirements. Limitations to inspections are primarily due to obstructions and interference.
Summary of the limited examinations are described below and also included in Table 1.
1 Part A: Category B-J, " Pressure Retaining Welds in Piping" For 12" Accumulator Discharge, the UT coverage for Valve to Elbow Weld W-1 is l 75.00%. additional volumetric coverage can not be obtained due to valve I configuration which prevents examination from upstream side of valve.(See Figure 1.)
For PLO-Cap "B", the UT coverage for Nozzle to Pipe Weld W-2 is 78.55%,
additional volumetric coverage can not be obtained due to nozzle configuration contour.
(See Figure 2.)
For Reactor Coolant Loop "A" , the UT coverage for Reducer 40 Elbow to Nozzle Weld W-5 is 48.00%, additional volumetric coverage can not be obtained due to Joint configuration limits access on downstream side of weld.
(See Figure 3.)
For Reactor Coolant Loop "B", The UT coverage for Nozzle to 40 Elbow W-1 is 60.0%, additional volumetric coverage can to be obtained due to nozzle configuration.
(See Figure 4)
For SIS High Head "A", the UT coverage for Elbow to Nozzle Weld W-10 is 84.1%, additional volumetric coverage can not be obtained due to nozzle configuration.
(See Figure 5.)
For SIS High Head "A", the UT coverage for Nozzle to Pipe Weld W-11 is 74.5%,
additional volumetric coverage can not be obtained downstream due to joint configuration. (See Figure 6.) ,
Part B: Category F-A, " Supports" & Category C-C " Integral attachments for Vessels, Piping, Pumps and Valves" Page 2 of 20
' NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN For Main Steam "A", the surface examination coverage for the Bearing Brake Assembly Restraint H-7 is limited to 84.6%, additional coverage can not be obtained because examination is restricted at six locations due to tack welded cover plate. (See Figure 7.)
For Main Steam B", the surface examination coverage for the seismic restraint H-2 is limited to 70.54%, additional coverage can not be obtained due to restraint configuration. (See Figure 8.)
For Main Steam "B", tho surface examination coverage for the seismic restraint H-1 is limited to 85.11% , additional coverage can not be obtained due to restraint configuration. (See Figure 9.)
For Main Steam "B", the surface examination coverage for the seismic restraint H-3 is limited to 85.11% , additional coverage can not be obtained due to restraint configuration. (See Figure 10.)
For Safety injection Pump 12, The surface examination coverage for support A is limited to 84.00% due to configuration of support.(See Figure 11.)
For Safety injection Pump 12, The surface examination coverage for support B is limited to 84.00% due to configuration of support.(See Figure 12.)
For Safety injection Pump 12, The surface examination coverage for support C is limited to 84.00% due to configuration of support.(See Figure 13.)
For Safety injection Pump 12, The surface examination coverage for support D is limited to 84.00% due to configuration of support.(See Figure 14.)
Additional Means of Establishina Intearity:
In addition, System pressure tests are performed during regular inspection intervals to ensure the piping system is capable of maintaining pressure integrity. System integrity is monitored continuously during normal operation by many direct and indirect methods, e.g., containment radiation monitoring, containment air monitoring, containment sump monitoring, containment temperature monitoring, system walk downs, etc.
Attemate Examination:
The limitations have been noted on the ISI examination reports and are included in the
- ISI Outage Summary Report. NSP will continue to document the limitations.
Page 3 of 20
NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN All in-service inspection at Prairie Island Unit 1 have been done to the greatest extent practical. When limitation to required inspections are encountered M&SP procedure ISI-LTS-1 is applied which requires alternative examination techniques be considered, or applied to gain the maximum obtainable inspection coverage practical. In all of the above items identified this procedure was used and the maximum inspection coverage was achieved.
Limitations are due to design, geometry, and materials of construction of the components or ALARA concems. NSP will continue to utilize the most current techniques available for future examinations.
Page 4 of 20
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' NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 1 I
Q3P MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION Limitation Data Sheet Initial Exam Report No: 99-0040 Procedure No. IS! UT-16 (Rev.12)
ISO No. ISI-17 (Rev.03) Item No. W 1 Description of Limitation:
Valve configuration prohibits examination from upstream side. obtained maximum coverage using 1-1/2 Vee exam.
Sketch of Limitation:
W-I Tm D ,.., ,
I l l Atve I
.f...
EL9ow
'm '
f/Dw SCA LE I:2 limitation removalrequirements:
None.
Page 7 of 20
NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 2
[@ MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION Limitation Data Sheet Initial Exam Report No: 99-0234 Procedure No. ISI-UT 16 (Rev.12)
I 0235 (60deg Supl) Temp Procedure: 99-UT16-1 ISO No. ISI-47 Item No. W-2 1
Description of Limitation:
~-
No examination from nozzle due to nozzle configuration.1 1/2 Vee Cal and 60deg supi. exam used to maximize coverage.
Sketch of Limitation:
Sud 2.
45, ,50 6ds450 ;
,, \ NOZZ.
4 CAP
--- fIDW
,. . . 7 . . .
., t Scale 1:1 Limitation removalrequirements:
None.
Page 8 of 20 i
NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 3
~
QHP MATERIALS & SPECIAL PROCESSES .
INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION Limitation Data Sheet initial Exam Report No: 99-0152 Procedure No, ISI-UT-11 A (Rev. 3)
ISO No. ISI-12A (Rev.2) Item No. W-5 Description of Limitation:
No scan 2 and limited scans 3 & 4 due to nozzle configuration. Limited scan 1 due to OD counterbore.
Sketch of Umitation:
EL6cv N' t
( ,
' (,uE,n z.
j
\
RE DocGD \ l SCA LE \ I s
I
Urnitation removal requirements: 1 None.
Page 9 of 20
' NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 4 GEiP MATERIALS & SPECIAL PROCESSES ,
INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION 1999 PRAIRIE ISLAND UNIT 1 OUTAGE Limitation Data Sheet
\
\
Initial Exam Report No: 99-0041 Procedure No. ISI-UT-11A (Rev. 3) i ISO No. 1S1-13B ltem No. W-1 j l
Description of Limitation:
No scan 1 due to nozzle configuration.
Sketch of Limitation:
StML
~
/ s
, I
\ #
\ '
\ /
\
sl v
Limitation removalrequirements:
None.
Page 10 of 20
. l
, NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN
)
Figure 5 bEP MATERIALS & SPECIAL PROCESSES INSERVlCE INSPECTION - NONDESTRUCTIVE EXAMIN/. TION j
. 1999 PRAIRIE ISLAND UNIT 10UTAGE Limitation Data Sheet initial Exam Report No: 99-0146 Procedure No. ISI-UT 16 (Rev.12) l J
ISO No. ISI 9 Item No. W 10
)
Deccription of Limitation: l No scan 2 and limited scans 3 & 4 due to nozzle configuration.
Sketch of Limitation:
,2 l
y/-lo I / OZZ.
flow 1-.L '
ELB. , \'t y I Limitation removal requirements:
None.
Page 11 of 20 l
~
NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 6 UEP MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION '
1999 PRAIRIEISLAND UNIT 1 OUTAGE Limitation Data Sheet initial Exam Report No: 99-0145 Procedure No. ISI-UT-16 (Rev.12)
ISO No. ISI 9 Item No. W 11 Description of Limitation:
No scan 2 and limited scans 3 & 4 due to joint configuration.
Sketch of Limitation:
SCAD I , ,
, W-Il ,
l n /
\ ',
4
, i 1 i
, . . a., .. -_ _ _ ,
8*
nozz ', l_ _ _ a ._
scale I:2 Limitation removalrequirements:
3 None.
Page 12 of 20 j
' NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN 4
Figure 7 l
69P MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION-1999 PRAIRIEISLAND UNIT 1 OUTAGE Limitation Data Sheet Initial Exam Report No: 99-0343 Procedure No. ISI-MT 1 (Rev. 9)
ISO No. ISI-51A Item No. H-7 Description of Limitation:
Limitation #1) No access to 8 sq. inch of exam area (6 places) due to cover plate.
Limitation #2) No exam on 16 sq. inch of exam area due to configuration of cover plate (6 places).
Sketch of Limitation:
1
. fit ou W "~ % sr#
l 1 Leof V covta d A
\,
i W ,
i l Limitation removalrequirements:
No removal is possible. Cover plate is welded to component.
Page 13 of 20
- NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 8 EP MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION . NONDESTRUCTIVE EXAMINATION-1999 PRAIRIE ISLAND UNIT 1 OUTAGE Limitation Data Sheet Initial Exam Report No: 99-0340 Procedure No. ISl-MT-1 (Rev. 9) 1'D No. ISI-68A Item No. H-2 Description of Limitation.-
Exam limited to 364 sq.in. of 516 sq.in. of total weld area.
Sketch of Limitation:
a n, IZZ, 3 3.. .. ~ _ 2 3 D \D I
k L__. j L.A i t
~
Limitation removalrequirements:
None.
1 Page 14 of 20 l I
l
1
. NORTHERN STATES POWER INSERVICE INSPECTION j PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 9
[ nip MATERIALS & SPECIAL PROCESSES <
INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION-1999 PRAIRIE ISLAND UNIT 1 OUTAGE ,
I Limitation Data Sheet '
initial Exam Report No: 99-0339 Procedure No. ISI-MT 1 (Rev. 9)
ISO No. ISI-68A Item No. H 1 Description of Limitation:
Exam limited to 183 sq.in. of 215 sq.in. of total weld area.
Sketch of Limitation:
Hl _
! 1 f 27,2,l J
%)
?\ \
\
J . \
Limhation removal requirements:
None. 1 Page 15 of 20
, NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN l
Figure 10 62ip MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION-1999 PRAIRIEISLAND UNIT 1 OUTAGE Limitation Data Sheet Initial Exam Report No: 99-0338 Procedure No. ISI-MT 1 (Rev. 9)
ISO No. ISI-68A Item No. H 3 Description of Limitation:
Exam limited to 183 sq.in. of 215 sq.in. of total weld area.
Sketch of Limitation:
a3
.f !
J;m
\b i i
[,
I Limitation removal requirements:
None.
Page 16 of 20
, NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 11 4
USiP MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION-1999 PRAIRIEISLAND UNIT 1 OUTAGE Limitation Data Sheet .
InitialExam Report No: 99-0366 Procedure No. ISI-MT-1 (Rev.9)
ISO No. ISI 83D ltem No. H 1
~
Description of Limitation:
Configuration prohibits examining weld at base of support.
Sketch of Limitation:
Y; -
7B '
t 1 ;
O ri t ; ?
jT. e fuMP U k Nl- 1 W i L
.y 6L t ,,
i rn i
( s sno .-
l wAGESj/Bl4 lW
Limitation removal requirements: ,
None.
Page 17 of 20
, NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 12
[iSiP MATERIALS & SPECIAL PROCESSES INSERVICE INSPECTION - NONDESTRUCTlVE EXAMINATION" 1999 PRAIRIEISLAND UNIT 1 OUTAGE Limitation Data Sheet .
InitialExam Report No: 99-0367 Procedure No. ISI-MT-1 (Rev. 9)
ISO No. ISI-83D ltem No. H-2 Description of Limitation:
Configuration prohibits examining weld at base of support.
Sketch of Limitation:
YC
? -
O ri t ! !!
.@:. . PUMP U I M iI ;I-- M b i
t il e 1 4----....- i
/ s-suo .-
. lw4aES$U)l4 lW AREA n r 10 sc4 %
Limitation removal requiremenfs:
None.
Page 18 of 20
a
=
p .
, NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 13 SEP MATERIALS & SPECIAL PROCESSES INSERVICEINSPECTION NONDESTRUCTIVE EXAMINAT10N' 1999 PRAIRIE ISLAND UNIT 1 OUTAGE Limitation Data Sheet Initial Exam Report No: 99 0368 Procedure No. ISI-MT-1 (Rev. 9)
ISO No. ISI-83D ltem No. H-3 Description of Limitation:
Configuration prohibits examining weld at base of support.
Sketch of Limitation:
v .
iB
> a O n ? : t j
.LT. .> Pump E L L:!= L-l. W: ;
A (I F t
\
tc-......: :: ...---.;
SRD VIEJ wauls)IBl4 YW #
MfA
/Joi 1*0_ SCAD i
Limitation removalrequiremenfs:
)
None.
Page 19 of 20
I 4
' NORTHERN STATES POWER INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1,3RD INTERVAL EXAMINATION PLAN Figure 14 SEP MATERIALS & SPECIAL PROCESSES INSERVICEINSPECTION NONDESTRUCTIVE EXAMINATION-1999 PRAIRIE ISLAND UNIT 1 OUTAGE i
Limitation Data Sheet initial Exam Report No: 99-0369 Procedure No. ISl-MT 1 (Rev.9)
ISO No. ISI-83D ltem No. H-4 Description of Limitation:
Configuration prohibits examining weld at base of support.
Sketch of Limitation:
?
@i .
o , s .
O n ? : ? :
!T.1. Pump E L Mi- l- W ;
B II & k is....... i gap f ,
V/Ed
. IDAulS$lBig fW l gr to scMt Limitation removalrequirements:
None.
Page 20 of 20