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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N1931999-10-22022 October 1999 Forwards Insp Rept 50-298/99-12 on 990927-30.No Violations Noted.Insp Exam of Activities Under License as They Relate to Emergency Preparedness & to Compliance with Commission Rules & Regulations & with Conditions of License ML20217G8771999-10-14014 October 1999 Forwards Insp Rept 50-298/99-10 on 990920-24.No Violations Noted ML20217G7401999-10-14014 October 1999 Forwards MOR for Sept 1999 for Cooper Nuclear Station. Rept Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20217C2671999-10-0808 October 1999 Forwards Insp Rept 50-298/99-03 on 990823-27 & 0907-10.No Violations Noted.Purpose of Insp to Ensure That Licensee Had Effective Programs for Identifying,Evaluating & Correcting Problems Which Could Impact Safe Plant Operations ML20212K9661999-09-30030 September 1999 Forwards Safety Evaluation Accepting plant-specific Safety Evaluation Rept for USI A-46 Program Implementation at Cooper Nuclear Station ML20216J1081999-09-28028 September 1999 Ltr Contract:Task Order 048, Cooper Safety Sys Design & Performance Capability Insp, Under Contract NRC-03-98-021 ML20212J5061999-09-27027 September 1999 Forwards Insp Rept 50-298/99-07 on 990718-0828.No Violations Noted.Inspectors Focused on Implementation of Licensee Reactor Safety & Emergency Preparedness Programs ML20212F3641999-09-22022 September 1999 Forwards Insp Rept 50-298/99-09 on 990823-26.No Violations Noted ML20216J8061999-09-20020 September 1999 Forwards Rev 37 to Safeguards Plan,Iaw Provisions of 10CFR50.(p).Rev Withheld,Per 10CFR73.21 ML20212C4921999-09-15015 September 1999 Forwards Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station.Rept Includes Operating Data Rept,Unit SD Rept & Documentation of Challenges to Safety/Relief Valves ML20212A6061999-09-14014 September 1999 Forwards Insp Rept 50-298/99-08 on 9900816-20.No Violations Noted.Insp Focused on Implementation & Effective Performance of Access Authorization/Fitness-for-Duty (Behavior Observation) Program & Access Control of Personnel ML20211N5271999-09-0202 September 1999 Responds to NRC 990823 RAI Re Y2K Readiness at Cooper Nuclear Station,Per GL 98-01,Suppl 1 05000298/LER-1999-006, Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl1999-08-26026 August 1999 Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl ML20211F1311999-08-24024 August 1999 Forwards Rev 1 to Calculation Nedc 97-044, NPSH Margins for RHR & CS Pumps, in Support of 990615 Proposed Amend to DPR-46 Re Containment Overpressure Contribution to ECCS Pumps NPSH Requirements 05000298/LER-1999-003, Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel1999-08-23023 August 1999 Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel ML20211F4661999-08-23023 August 1999 Discusses GL 98-01 Issued by NRC on 980511 & NPPD Responses for Cooper Nuclear Station & 990628 & Results of Visit to Plant on 990811-12.Staff Determined That Integrated Contigency Plan Incomplete & CNS Not Y2K Ready ML20210R0301999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Cooper Nuclear Station,Iaw Guidance Provided by GL 97-02.Rept Also Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P6761999-08-10010 August 1999 Requests That Following Changes Be Made to Distribution on NRC Correspondence ML20210P6861999-08-0909 August 1999 Forwards Insp Rept 50-298/99-06 on 990530-0717.No Violations Noted.During Insp,Inspectors Identified Two Issues Categorized as Being Low Risk Significance & within Licensee Response Band ML20210N1331999-08-0606 August 1999 Forwards Notice of Withdrawal of Application for Amend to FOL DPR-46.By Ltr Licensee Withdrew Amend Request Which Would Have Revised Usfar to Reflect as-built Configuration of Reactor Bldg Isolation Dampers ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K6071999-08-0202 August 1999 Submits Withdrawal of Proposed License Amend Re Secondary Containment Isolation Description & Refueling Accident Analysis Results ML20210K3811999-08-0202 August 1999 Forwards Listed Info,Which NPPD Believes Demonstrates Ability to Obtain Funds in Amount of $10 Million for Payment of Such Premiums within Specified Three Month Period,Iaw 10CFR140.21 ML20210G5101999-07-28028 July 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 990101-0630,per Provisions of 10CFR26.71(d) ML20210D2541999-07-21021 July 1999 Forwards Insp Rept 50-298/99-02 on 990628-0702.Purpose of Insp Was Primarily to Evaluate Effectiveness of Licensed Operator Requalification Program.No Violations Were Identified ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20209H8191999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20209E6951999-07-12012 July 1999 Discusses Response to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Recommends Review of New Database Diskettes on Listed Website.Comments Due by 990901 or Data Entered Into Rvid for Plant Will Be Acceptable ML20209D8731999-07-0808 July 1999 Refers to 990707 Meeting Re Licensee Recent Maintenance Program self-assessment.Also Discussed How Licensee Incorporated Assessment Findings Into Rev of Maintenance Performance Improvement Plan.List of Attendees Encl ML20209B7851999-07-0101 July 1999 Forwards Corrected Occupational Radiation Exposure Repts, for Cys 1996 & 1997.Util Stated That Repts Did Not Properly Tabulate Number of Personnel Receiving Exposures Less than 100 Mrem by Work & Job Functions in CY96 & CY97 05000298/LER-1999-005, Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl1999-07-0101 July 1999 Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl ML20196J2471999-06-29029 June 1999 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps, 05000298/LER-1999-004, Forwards LER 99-004-01.Commitments Made by Util Are Encl1999-06-28028 June 1999 Forwards LER 99-004-01.Commitments Made by Util Are Encl ML20209B5451999-06-28028 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196H0331999-06-24024 June 1999 Informs NRC of Deletion of 1991 Commitment Contained in Ltr Re Feedwater Nozzle Bypass Leakage Monitoring at Plant ML20196F7511999-06-24024 June 1999 Discusses 990622 Meeting with Public at Arbor Manor, Alburn,Ne to Provide Overview of Pilot Insp Program ML20209A7221999-06-23023 June 1999 Submits Revised Pages to Proposed Change to Plant TS Previously Submitted in ,Per 990615 Telcon with NRC ML20196F5331999-06-22022 June 1999 Forwards Examination Summary Rept for FW Nozzle Examinations Performed During 1998 Fall Refueling Outage at Cooper Nuclear Station.Rept Covers Past Examinations Up to & Including 1998 Fall Refueling Outage ML20196B4681999-06-17017 June 1999 Forwards TS Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610.List of Effective Pages for TS Bases, Encl ML20196E1411999-06-16016 June 1999 Forwards Insp Rept 50-298/99-05 on 990502-29.Noncited Violations Identified ML20195H8891999-06-14014 June 1999 Forwards Response to NRC 990315 RAI Re GL 95-07, Pressure Locking & Thermal-Binding of SR Power-Operated Gate Valves, 180-day Response Submitted by District on 960213 ML20195F6171999-06-0909 June 1999 Informs That GE Rept, Matl Presented by GE 970709 Meeting at Cooper Nuclear Power Station Re Replacement of ECCS Pump Suction Strainers Between Nppd,Ge & NRC Staff, Will Be Withheld from Public Disclosure as Requested ML20207G3031999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Rev 24,under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195E2351999-06-0808 June 1999 Forwards Response to NRC 990517 RAI Re Util Proposed Change to TS Re Calibr Frequency of Reactor Recirculation Flow Transmitters Associated with APRM ML20207G4481999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure,Epip 5.7.1, Emergency Classification,Rev 23 C2,under Provisions of 10CFR50,App E,Section V ML20207G3001999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station Ep,Rev 33,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required Based on Determination That EP Effectiveness Not Affected by Changes ML20207G4531999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Revision 25,under Provisions of 10CFR50,App E,Section V ML20207D3811999-05-27027 May 1999 Informs That During Next 6 to 12 Months,Starting 990530,NRC Plans to Conduct Insps Shown in Attached Insp Plan.Insps Include Both Planned Baseline & Supplemental Insps (Formerly Core & Regional Initiative Insps) ML20207A5191999-05-19019 May 1999 Forwards Insp Rept 50-298/99-04 on 990321-0501.Four Violations Identified & Being Treated as non-cited Violations 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217G7401999-10-14014 October 1999 Forwards MOR for Sept 1999 for Cooper Nuclear Station. Rept Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20216J8061999-09-20020 September 1999 Forwards Rev 37 to Safeguards Plan,Iaw Provisions of 10CFR50.(p).Rev Withheld,Per 10CFR73.21 ML20212C4921999-09-15015 September 1999 Forwards Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station.Rept Includes Operating Data Rept,Unit SD Rept & Documentation of Challenges to Safety/Relief Valves ML20211N5271999-09-0202 September 1999 Responds to NRC 990823 RAI Re Y2K Readiness at Cooper Nuclear Station,Per GL 98-01,Suppl 1 05000298/LER-1999-006, Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl1999-08-26026 August 1999 Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl ML20211F1311999-08-24024 August 1999 Forwards Rev 1 to Calculation Nedc 97-044, NPSH Margins for RHR & CS Pumps, in Support of 990615 Proposed Amend to DPR-46 Re Containment Overpressure Contribution to ECCS Pumps NPSH Requirements 05000298/LER-1999-003, Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel1999-08-23023 August 1999 Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel ML20210R0301999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Cooper Nuclear Station,Iaw Guidance Provided by GL 97-02.Rept Also Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20210P6761999-08-10010 August 1999 Requests That Following Changes Be Made to Distribution on NRC Correspondence ML20210K6071999-08-0202 August 1999 Submits Withdrawal of Proposed License Amend Re Secondary Containment Isolation Description & Refueling Accident Analysis Results ML20210K3811999-08-0202 August 1999 Forwards Listed Info,Which NPPD Believes Demonstrates Ability to Obtain Funds in Amount of $10 Million for Payment of Such Premiums within Specified Three Month Period,Iaw 10CFR140.21 ML20210G5101999-07-28028 July 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 990101-0630,per Provisions of 10CFR26.71(d) 05000298/LER-1999-005, Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl1999-07-0101 July 1999 Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl ML20209B7851999-07-0101 July 1999 Forwards Corrected Occupational Radiation Exposure Repts, for Cys 1996 & 1997.Util Stated That Repts Did Not Properly Tabulate Number of Personnel Receiving Exposures Less than 100 Mrem by Work & Job Functions in CY96 & CY97 05000298/LER-1999-004, Forwards LER 99-004-01.Commitments Made by Util Are Encl1999-06-28028 June 1999 Forwards LER 99-004-01.Commitments Made by Util Are Encl ML20209B5451999-06-28028 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196H0331999-06-24024 June 1999 Informs NRC of Deletion of 1991 Commitment Contained in Ltr Re Feedwater Nozzle Bypass Leakage Monitoring at Plant ML20209A7221999-06-23023 June 1999 Submits Revised Pages to Proposed Change to Plant TS Previously Submitted in ,Per 990615 Telcon with NRC ML20196F5331999-06-22022 June 1999 Forwards Examination Summary Rept for FW Nozzle Examinations Performed During 1998 Fall Refueling Outage at Cooper Nuclear Station.Rept Covers Past Examinations Up to & Including 1998 Fall Refueling Outage ML20196B4681999-06-17017 June 1999 Forwards TS Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610.List of Effective Pages for TS Bases, Encl ML20195H8891999-06-14014 June 1999 Forwards Response to NRC 990315 RAI Re GL 95-07, Pressure Locking & Thermal-Binding of SR Power-Operated Gate Valves, 180-day Response Submitted by District on 960213 ML20195E2351999-06-0808 June 1999 Forwards Response to NRC 990517 RAI Re Util Proposed Change to TS Re Calibr Frequency of Reactor Recirculation Flow Transmitters Associated with APRM ML20207A0701999-05-19019 May 1999 Forwards Rev 3 to CNS Strategy for Achieving Engineering Excellence, Which Provides Effective Tool for Overall Engineering Work Mgt.Commitments Made by Util,Encl ML20206R7601999-05-17017 May 1999 Forwards Annual Radiological Environ Rept,Radiological Environ Monitoring Program,Jan-Dec 1998,per TS 5.6.2 ML20206P9681999-05-13013 May 1999 Forwards Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station.Rept Includes Documentation of Challenges to Safety/Relief Valves ML20206J0741999-05-0404 May 1999 Forwards Rev 14 to CNS QA Program for Operation, Per 10CFR50.54(p) & 10CFR50.71.None of Changes Represent Reduction of Commitments.Summary of Changes,Encl ML20206J2331999-05-0303 May 1999 Forwards CNS Annual Radioactive Effluent Release Rept for 1998 & Offsite Dose Assessment Manual ML20206F2021999-04-30030 April 1999 Informs That NPPD Now Anticipates LAR Committed in Will Be Submitted by 990615.Operability Evaluations Presently in Effect Ensure That ECCS Pumps Are Operable But Nonconforming & Are Capable of Fulfilling Safety Functions ML20206E5461999-04-29029 April 1999 Forwards Cooper Nuclear Station Occupational Radiation Exposure Rept for 1998. Numbers Reported Reflected Tabulation of All Personnel on Site by Work & Job Function. Repts Will Be Corrected & Resubmitted by 990701 ML20205K1151999-04-0101 April 1999 Submits Extension of Commitment Date for Rev to Plant Strategy for Achieving Engineering Excellence from 990331 to 990519.Licensee Requires Addl Time to Finalize & Approve Rev 3 to Plant Strategy for Achieving Engineering Excellence ML20205E4331999-03-31031 March 1999 Forwards First Biennial Rept of Financial Assurance for Decommissioning for Cns,Per 10CFR50.75(f)(1) ML20205A0561999-03-23023 March 1999 Provides Info Detailing Property Insurance Coverage Maintained by NPPD & Midamerican Energy Co for Cns,In Compliance with 10CFR50.54(w)(3) 05000298/LER-1999-001, Forwards LER 99-001-00,including List of NRC Commitments Made by Util1999-03-22022 March 1999 Forwards LER 99-001-00,including List of NRC Commitments Made by Util ML20204G8811999-03-22022 March 1999 Forwards CNS Inservice Insp Summary Rept,Fall 1998 Refueling Outage (RFO-18), IAW Provisions of 10CFR50.55a. Analytical Evaluation for RPV Shell Weld Indications & Augmented Exam Results of RPV Also Included ML20204J4841999-03-19019 March 1999 Requests NRC Review & Approval of CNS ISI Relief Request (RR) PR-04,rev 1.ISI RR PR-04,rev 0 Required CNS to Perform Visual Insp of RPV Head Flange Seal Leak Detection Line. Approval Is Required Because Test Methodology Was Changed 05000298/LER-1998-013, Forwards LER 98-013-01 Re Missed Surveillance of Secondary Containment Isolation Valve.List of NRC Commitments Encl1999-03-16016 March 1999 Forwards LER 98-013-01 Re Missed Surveillance of Secondary Containment Isolation Valve.List of NRC Commitments Encl ML20204C9641999-03-15015 March 1999 Forwards Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station.Rept Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20207J5811999-03-10010 March 1999 Forwards Rev 1 to Calculation Nedc 98-024, APRM - RBM Setpoint Calculation ML20207F9661999-03-0101 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-298/98-08.Corrective Actions:Circumstances Surrounding Four Examples Have Been Discussed with Individuals Involved & Counseled,Where Appropriate ML20203C6961999-02-0808 February 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 980701-1231,per 10CFR26.71(d) ML20202H6721999-02-0202 February 1999 Informs of Changes in Schedule Affecting Four Commitments in ,By Greater than One Month & Notifies of Plans to Issue Rev 3 to Strategy for Achieving Engineering Excellence ML20202E2231999-01-28028 January 1999 Forwards Response to NRC 980603 RAI Re NRC Ongoing Review of IPEEE for Cooper Nuclear Station,Submitted 961030 ML20199K6721999-01-19019 January 1999 Requests Extension of Present Due Date to 980202,as Addl Time Is Required to Resolve Issues Raised on Corrective Actions During Senior Mgt Review of Insp Rept 50-298/98-15 05000298/LER-1998-011, Forwards LER 98-011-00,per 10CFR50.73(a)(2)(v).Commitments Made by Util,Encl1999-01-19019 January 1999 Forwards LER 98-011-00,per 10CFR50.73(a)(2)(v).Commitments Made by Util,Encl ML20199E6281999-01-14014 January 1999 Forwards Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station.Rept Also Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20206P4171998-12-31031 December 1998 Informs of Extended Completion Due Date of Third Commitment Re EOP Calculations,Per Licensee 980723 Response to Violations Noted in Insp Rept 50-298/98-02.Date Has Been Extended to 990228 ML20199D2251998-12-30030 December 1998 Forwards 1998 CNS Simulator Certification Rept,As Required by 10CFR55.45.Rept Describes Performance Tests Conducted from 1995-98,discusses Performance Test Discrepancies from 1995-98 & Provides Revised Test Plan for 1999-2002 ML20198K2491998-12-23023 December 1998 Discusses RAI Re Response to NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps ML20205A4411998-12-17017 December 1998 Forwards Initial Exam Outline for RO Written Exam to Be Given Week of 990208.Preliminary Copies of License Applications for Candidates Encl ML20196C4011998-11-20020 November 1998 Forwards Rev 1 to Cooper Nuclear Station COLR Cycle 19. Licensee Discovered That COLR Submitted with Contained Incorrect Max Average Planar Linear Heat Generation Rate Curves Specified in Figures 1 to 4 1999-09-20
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A6891990-09-12012 September 1990 Forwards Evaluation of Environ Qualification of Okonite T95/35 Tape Splices in Instrumentation Applications at Facility,Per 900813 Request.Tape Splices Fully Qualified for Use in Plant Instrumentation Circuits in Harsh Environ ML20028G9041990-08-28028 August 1990 Forwards Fitness-for-Duty Program Performance Data for Jan-June 1990.Util 900705 Ltr Provided Addl Info to NRC Re Panel of Drugs Included in Testing Program.Info Re Cutoff Levels for Benzodiazepine in Ltr Incorrect NLS9000369, Forwards Endorsement 80 to Maelu Policy MF-70 & Endorsement 96 to Nelia Policy NF-200,reflecting Shutdown Credit for Most Recent Outage for Nuclear Liability Insurance for Plant1990-08-27027 August 1990 Forwards Endorsement 80 to Maelu Policy MF-70 & Endorsement 96 to Nelia Policy NF-200,reflecting Shutdown Credit for Most Recent Outage for Nuclear Liability Insurance for Plant ML20056A7801990-08-0202 August 1990 Forwards Owners Data Rept for ISI & Owners Rept for Repairs & Replacements NLS9000308, Forwards Info to Demonstrate Util Ability to Obtain Funds for Payment of Deferred Insurance Premiums.Supporting Documentation Encl1990-08-0101 August 1990 Forwards Info to Demonstrate Util Ability to Obtain Funds for Payment of Deferred Insurance Premiums.Supporting Documentation Encl NLS9000196, Responds to Violations Noted in Insp Rept 50-298/90-09. Corrective Actions:To Ensure Future Clarity,District Will Revise Procedures to Clearly Indicate Acceptability of Okonite in Instrumentation Applications1990-07-31031 July 1990 Responds to Violations Noted in Insp Rept 50-298/90-09. Corrective Actions:To Ensure Future Clarity,District Will Revise Procedures to Clearly Indicate Acceptability of Okonite in Instrumentation Applications NLS9000268, Forwards Endorsement 79 to Maelu Policy MF-70 & Endorsement 95 to Nelia Policy NF-2001990-07-10010 July 1990 Forwards Endorsement 79 to Maelu Policy MF-70 & Endorsement 95 to Nelia Policy NF-200 ML20055F3701990-07-10010 July 1990 Informs That Acceptance Criteria for Startup Physics Tests Have Been Met for Recent Cycle 14 Startup,Per NLS9000260, Requests Rev to List of Carbon Copies on NRC Correspondence to util.Marked-up Ltr Showing Revs Encl1990-07-0909 July 1990 Requests Rev to List of Carbon Copies on NRC Correspondence to util.Marked-up Ltr Showing Revs Encl ML20044A8331990-07-0606 July 1990 Informs of New Official Title for Ga Trevors,Effective 900701 NLS9000254, Notifies That Util Fitness for Duty Program Includes Drug Screening for Addl Drugs Over Min Panel of Drugs Required by 10CFR26.Drugs & Testing Cutoff Levels Listed1990-07-0505 July 1990 Notifies That Util Fitness for Duty Program Includes Drug Screening for Addl Drugs Over Min Panel of Drugs Required by 10CFR26.Drugs & Testing Cutoff Levels Listed NLS9000192, Forwards Rev 8 to Updated SAR for Cooper Nuclear Station. Rev 6 to QA Program Transmitted on 900406 Ref in App D.Next Rev to Updated SAR Will Be Submitted on or Before 9107221990-07-0202 July 1990 Forwards Rev 8 to Updated SAR for Cooper Nuclear Station. Rev 6 to QA Program Transmitted on 900406 Ref in App D.Next Rev to Updated SAR Will Be Submitted on or Before 910722 ML20043J0651990-06-22022 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Item 4.1 of Generic Safety Issues 75 Not Applicable to Plant NLS9000217, Submits Followup Response to Insp Rept 50-298/89-34 Re Physical Security Program.Util Completed Safeguards Info Audit of Each Contractor Holding Safeguards Info.Contractor Surrendered All Safeguards Info Documents on Plant to Util1990-06-19019 June 1990 Submits Followup Response to Insp Rept 50-298/89-34 Re Physical Security Program.Util Completed Safeguards Info Audit of Each Contractor Holding Safeguards Info.Contractor Surrendered All Safeguards Info Documents on Plant to Util ML20043G6381990-06-15015 June 1990 Forwards Monthly Operating Rept for May 1990 & Corrected Operating Rept for Apr 1990 for Cooper Nuclear Station ML20043G1101990-06-14014 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Rept 50-298/90-12.Corrective Actions:Individual Senior Technician Status Rescinded & Procedure Describing Qualification Requirements,Including Health Physics Experience,Written ML20043G6471990-06-13013 June 1990 Forwards Decommissioning Funding Plan,Per 10CFR50.75 & Decommissioning Trust Fund Agreement Between Util & Firstier Bank,Lincoln Dtd 900601 ML20043G4581990-06-13013 June 1990 Forwards Endorsements 72-78 to Maelu Policy MF-70 & Endorsements 88-94 to Nelia Policy NF-200 ML20043G3891990-06-13013 June 1990 Forwards Endorsements 14 & 15 to Nelia Policy N-41 & Maelu Policy M-41,respectively ML20043F4981990-06-0505 June 1990 Forwards Changes to Proposed Rev 6 of Plant QA Program for Operation Policy Document Submitted in 900406 & 19 Ltrs ML20043C4381990-05-31031 May 1990 Forwards Change to QA Program for Operation Policy Document for Review & Approval,Per 10CFR50.54(a)(3) ML20043C3091990-05-30030 May 1990 Responds to NRC 900430 Ltr Re Violations Noted in Insp Rept 50-298/90-15.Util Does Not Believe That Violation Existed & Therefore No Corrective Action Required.Inservice Testing Program Being Enhanced as Result of Insp ML20043C7081990-05-25025 May 1990 Forwards Rev 6 to Inservice Testing Program for ASME Class 1,2 & 3 Components, as Committed in Util 890926 Response to Generic Ltr 89-04.Summary Listing of Changes Also Encl NLS9000198, Forwards Public Version of Nebraska Public Power District Cooper Nuclear Station 1990 Evaluated Exercise,9007251990-05-23023 May 1990 Forwards Public Version of Nebraska Public Power District Cooper Nuclear Station 1990 Evaluated Exercise,900725 ML20043B6551990-05-18018 May 1990 Forwards Response to Insp Rept 50-298/90-05 Re Safety/Security Interface Issue.Response Withheld (Ref 10CFR73.21) ML20042F7371990-05-0303 May 1990 Forwards Tech Spec Bases Section 3.12.C, Svc Water Sys, in Response to SSFI Repts 50-298/87-10 & 50-298/89-03 & Implementation of Design Change 90-009, Automatic Isolation of SW-MOV-37MV on Low Svc Water Pressure, for Review ML20042F2821990-05-0101 May 1990 Clarifies Initiating Conditions Listed in 900316 Ltr Re Review of 890919 Rev 11 to Plant Emergency Plan.Gaseous Release Emergency Action Level Established as High Alarm on Effluent Monitor ML20042F1491990-04-30030 April 1990 Provides Response to NRC Safety Evaluation Concerns Re Util Response to Generic Ltr 88-01.Licensee Will Conform to NRC Position on Reporting Requirements ML20042F1481990-04-30030 April 1990 Provides Results of Quarterly Local Leak Rate Test on Containment Purge & Vent Valves at Plant ML20042E4601990-04-12012 April 1990 Forwards Rev IX to Reg Guide 1.97 Instrumentation List to Correct Errors Identified During NRC Insp (Insp Rept 50-298/90-01) ML20042E2031990-04-0606 April 1990 Suppls 900122 Response to Insp Rept 50-298/89-34.Completion Date for External Audits Extended to 900531 ML20042E0791990-03-27027 March 1990 Forwards Annual Radiological Environ Operating Rept 1989. ML20012D9571990-03-23023 March 1990 Submits Supplemental Response to Util 890417 & 0803 Responses to Station Blackout rule,10CFR50.63.Util Reserves Right to Review Final Issue of NUMARC 87-00,App D Prior to Implementation ML20012D9671990-03-20020 March 1990 Lists Present Levels of Property Insurance Coverage,Per 10CFR50.54(w)(1).Policy Expiration Date for Coverage Is 900501.Util Presently Involved in Insurance Renewal Process ML20012C6951990-03-15015 March 1990 Notifies NRC of Intent to Defer Response to Generic Ltr 89-19,per 900306 Approved Scheduler Extension.Response Will Be Submitted on or Before 900504 ML20012C6931990-03-15015 March 1990 Submits Final Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Final Item,Verification That Mfg Air Quality Requirements for Essential Components,Completed ML20011F5631990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-298/89-31.Corrective Actions:Numbered Lead Seal Installed & Logged When Found Missing on 891113 & Procedure 0.9 Reviewed W/Personnel ML20011F8111990-03-0202 March 1990 Forwards Corrections to Rev 24 to Plant Safeguards Plan.Rev Withheld (Ref 10CFR73.21) ML20012A5061990-02-26026 February 1990 Forwards Proprietary GE11 LTA Fuel Bundle Description for Cooper Nuclear Station Reload 13,Cycle 14. Util Plans to Load Four Fuel Assembly Lead Test Assemblies as Part of Plant Reload 13.Encl Withheld (Ref 10CFR2.790) ML20012C7801990-02-23023 February 1990 Forwards Comments on Questions & Answers Associated w/900221 Exam.Recommends That Comments Be Considered in Written Exam & Serve as Basis for Refining Exam Answers ML20011F6531990-02-21021 February 1990 Lists Property Insurance Coverage Carried by Util W/Nelia & Maelu W/Expiration Dates of 900501 ML20011F1131990-02-15015 February 1990 Requests Relief from Commitment to Continue motor-operated Valve Testing Under Program Established in Response to NRC Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transient Due to Improper Switch Settings. ML20011F0321990-02-14014 February 1990 Responds to NRC 900118 Ltr Re Violations Noted in Insp Rept 50-298/89-37.Corrective Actions:Plant Svcs Procedure 1.6, Warehouse Marking & Tagging Will Be Revised to Delete Requirement of Placing Hold Tag W/Work Item File ML20006C5391990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Applicable HX Performance Evaluation Procedures Will Be Revised by 901231 & Ultrasonic Testing Will Be Performed ML20006A5031990-01-22022 January 1990 Forwards Response to Insp Rept 50-298/89-34.Response Withheld (Ref 10CFR73.21) ML20006A8191990-01-16016 January 1990 Forwards Endorsement 71 to Maelu Policy MF-70 & Endorsement 87 to Nelia Policy NF-200 ML20006A9641990-01-16016 January 1990 Forwards Endorsement 5 to Nelia Certificate NW-107 & Maelu Certificate MW-43 ML20006A5091990-01-16016 January 1990 Forwards Endorsement 13 to Nelia Certificate N-41 & Endorsement 13 to Maelu Certificate M-41 ML20005G5621990-01-0808 January 1990 Forwards Monthly Operating Status Rept for Dec 1989 & Revised Operating Status & Unit Shutdown Data Repts for Nov 1989 for Cooper Nuclear Station ML20005E8661990-01-0404 January 1990 Forwards Rev 25 to Safeguards Plan.Changes Reflect Improvements to Main Vehicle Gate,Restrictions on Warehouse Searches & Distribution Changes for Annual Security Audits. Rev Withheld (Ref 10CFR73.21) 1990-09-12
[Table view] |
Text
-
- .
- o , - .
e GENERAL OFFICE
- g. Nebraska Public Power District " " " W Nn*J %"^Mt""' "
NLS9000177' April 30, 1990 U.S. Nuclear Regulatory Commission-Attention: Document Control Desk Washington, DC 20555 *
Subject:
Supplemental Response to Generic Letter-88-01 Cooper Nuclear Station NRC Docket No. 50-298,-DPR-46
Reference:
- 1) Letter from P. W. O'Connor (NRC) to G. A. Trevors (NPPD). dated-February 14, 1990, Review of NPPD's Response to Generic Letter-88-01 (TAC No. 69131)-
- 2) Letter from G. A. 'Trevors - (NPPD) to U.S.. Nuclear Regulatory . !
Commission dated ' July 24, 1989, " Request for Additional Information - Generic Letter 88-01" (TAC No. 69131)
.3) Letter - from L. G. Kuncl ( NPPD ) ' to - U .'S . Nuclear Regulatory Commission dated ' August _ 3, 1988, "IGSCC in ' BWR Austenitic Stainless Steel Piping, Generic' Letter 88-01"
- 4) Letter from D. B. Vassallo-(NRC) to L. G. Kuncl (NPPD) dated ;
September 1, 1983 issuing Confirmatory Order 1
- 5) Letter from W. O. Long (NRC) to G. A. Trevors- (NPPD) dated-July 20, 1987 " Clarification of Effective Page -
Technical Specifications for' Cooper Nuclear Station" 1
Gentlert an:
Reference 1 found the District's previous responses to Generic Letter 88-01 3 acceptable with the exception of four areas as documented in the Staff's H Safety Evaluation Report (SER) and contractor Technical Evaluation Report ,
p (TER). This letter provides the District's response to the four areas of
. :) concern. -
)-
ko 1. your responses concerning intergranular stress corrosion cracking (IGSCC) !
@$@ classifications and accessibility contain conflicting. and inconsistent g information. The staff will find these responses acceptable, provided otn that the recommendations described in Section 2.3'5 of the enclosed-
[OML Technical Evaluation Report (TER) are implemented.
b
.OQ NPPD Response:
8(
0 b.c L O The recommendations described in Section 2.3.5 of the subject TER were )}
$o: implemented. The listing of welds provided in Reference 2 has been
- @@g updated and is attached for information. The new listing accounts for K.._ _
= __ _
v _ _ _ _ _
Powerius prise in nesraska
U.S. Nucl:^r Regulstory Commicsion
. P;gn'2 L
portions of the Reactor Water Cleanup (RWCU) System that were replaced with IGSCC resistant material during the 1990 refueling outage . . . The l resulting new .w elds are identified in the comments column of the new L listing and the - welds removed by the RWCU . pipe replacement have _ been t
L deleted. All inaccessible welds have been classiffwd as IGSCC Category G
- l. and Weld RCA-BF-1 has. been reclassified as IGSCC Category D. All welds l reported to have cracks . in Reference 2 have been either replaced or I
repaired, or were. misidentified as having cracks and have been corrected accordingly in the attachment. No welds described 'in the attachment have
. flaw indications, consequently there are no.IGSCC Category F welds.
- 2. Your responses declined ;to propose a Technical Specification. change' that -
includes a statement on- inservice inspection (ISI) as required by this 1 generic letter. This position 1s .not acceptable. NPPD:should propose.an C
, amendment to the Cooper Technical Specifications as required by Generic Letter 88-01. The model specification for boiling water reactors that was >
. provided in Attachment B to the generic letter should be . utilized unless I changes are necessary to accommodate plant specific differences at Cooper Nuclear Station.
NPPD Response:
l The District committed, in Reference 3, to be in conformance with .the l' stated staff positions . contained in Generic Letter 88 in regards to
, schedule, methods and personnel, and sample expansion. . This commitment is-l identical in content to the model Technical ~ Specification contained in the-Generic Letter. The District ' is adhering to ' this commitment and 'will continue to do so. The District does not believe . amending the Cooper Nuclear Station Facility Operating License to incorporate this. commitment into the Technical Specifications is necessary .and requests that the NRC reconsider its position on this item.
- 3. NPPD has also declined to propose an amendmeht to 'the Technical "
Specifications that limits the increase in unidentified leakage to 2 gpm over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, as required by Generic Letter 88-01.- -
Your position is unacceptable. NPPD should propose the required Technical Specification.
NPPD Response:
As described below, the District ' believes the existing leakage- detection Technical Specifications are adequate.
a) There are no IGSCC Category D, E, F, or G welds inside the CNS containment with the exception of weld RCA-BF-1. This particular weld i is on the capped CRD return line- to the pressure vessel and has an inner diameter less than four inches. This weld was inspected during the 1990 refueling outage with no crack indications detected. While-the TER notes : that the scope of the subject generic letter is not limited to the welds inside the containment, the leakage detection systems in question are confined to the primary containment.
U.S. Nucir:r RegulItory Comminion 1 April.30, 1990-pig 3' 3 I
b) As a result of . finding IGSCC cracking in 1983, the NRC issued ' a Confirmatory Order to the District, Reference 4,=on September 1, 1983.
The order directed enhanced leakage monitoring due to uncertainties in
. crack sizing and growth.- .The District believes this Confirmatory Order was ' issued solely' on the basis of identified cracks . in large'.
bore IGSCC susceptible piping-inside Cooper's-containment'.
L c) A July 20, .1987- letter, Reference 5, removed the enhanced leakage -
detection requirements -because. the NRC had determined that the.
circumstance (IGSCC cracking) that had led to- the Confirmatory ' Order (enhanced leakage requirements) was no longer applicable, d) The District's basis regarding unidentified leakage' rateL is described in. Cooper's : Updated Safety Analysis Report, Section IV-10. The 5.gpm rate in Section 3.6.C - of the. Technical Specifications is . extremely .
conservative relative to ' 150 ppm determined necessary to1. indicate i rapid crack propagation.
L I
e) The District . replaced IGSCC susceptible piping in '1985 to. ensure tho' continued safe operation of Cooper and ensure Cooper :would meet General-Design Criteria 4',L14, and 31. ?
In summary, the District , believes ' any :- submission regarding ' enhanced I leakage technical specifications: 10 unwarranted- andf is voluntary in nature. Just six monthc1before.the lasuance of Generic Letter 88-01, the >
NRC Staff agreed with the District' regarding enhanced leakage - detection- .]
requirements at ' Cooper. Since the ' existing . leakage specification adequately provides for - the ; public health and safety, the District' believes the previous . staff position (Reference 5) regarding leakage '
detection is adequate and does not-. plan to submit a Technical
- L Specification change in this regard.
l
- 4. NPPD's position on reporting. of flaws and' flaw evaluation -is: not.in conformance 'with the NRC staff position stated in Generic- Letter 68-01. NPPD- should modify its position on reporting requirements and repair criteria to conform to the NRC staff position 'as required in Generic Letter 88-01.
5 NPPD Response:
The District will conform to the NRC Staff . position on reporting.
requirements as' stated in Generic Letter 88-01. Th'e District will notify -
the NRC of any flaws identified that do not meet IWB-3500. criteria of Section XI of the Code for Continued Operation without evaluation, or a change found in condition of welds previously known to be cracked. The' -
District will also notify the NRC of flaw evaluation required for continued operation and/or flaw repair plans.
U.S. Nucl;;r Regulttory Comm12:1:n
- April.30, 1990
. P:ga'4 i i
l Should you have any further questions regarding this issue, please contact my office.
Sincerely,
. . Trevors Division Manager Nuclear Support
- /jW Attachment cc: U.S. Nuclear Regulatory. Commission Region,IV-Arlington, TX I 4
NRC Resident Inspector Office l Cooper Nuclear Station !
}
'l 1
l l
i i
l 1-t t
NLS9000177 Peca 1 .
11E.7 2. INERVICE !*SPECTION PROGRAl EXISTING
. WELD NO. SYSTEM ISO CFIG SIZE MAT (1) SHT SI (2)' IGSCC CRC PAST FLAW FUTURE COMMENTS CWA-CF-45 RWCU 2605-4 V-P 6" F20/P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage. -
CWA CF-46 RWCU 2605-4 P-T '6" P21 Yes No R.O. 13 A No No Per G.L. 88-01 Replaced 1990 Outage. .
CWA-CF-47 RWCU 2605-4 T-P 6" P21 Yes No A No R.O. 13 No Per G.L. 88 01 Replaced 1990 Outage.
CWA-CF-48 RWCU 2605-4 P-E 6" P21 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
CWA-CF-50 RWCU 2605-4 E-P 6" P21 Yes No A No R.O. 13 No Per G.L. 88 01 Replaced 1990 Outage.
CWA-CF-51 RWCU 2605-4 P-E 6" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
CWA-CF-52 RWCU 2605-4 E-P 6" P21 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
CWA-CF-54 RWCU 2605-4 PE 6" P21 No No A No R.O. 13 No - Per G.L. 88-01 Replaced 1990 Outage.
CWA-CF-56 RWCU 2605-4 E-T 6" F-26 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
CWA CF 57 RWCU 2605-4 T-R 6" F-26 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
CWA-CF-58 RWCU 2605-4 T-R 6" F-26 Yes No A No R.O. 13 - No Pe- G.L. 88-01 Replaced 1990 Outage.
RWCU-10 RUCU 2605-3 N-P 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-11 RWCU 2605-3 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-12 RWCU 2605-3 E-P 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-13 RWCU 2605-3 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-14 RWCU 2605-3 E-P 4" P12 No No 0 No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-15 RWCU 2605-3 P-P 4" P12 No No G No N/A No Per G.L. 88-01 Inaccessible, pipe wilt be rerouted in 1991.
RWCU-16 RWCU 2605-3 P-E 4" P12 No No G No N/A No Per G.L. 88-01 Inaccessible, pipe wilt be rerouted in 1991.
RWCU-17 RWCU 2605-3 E-P 4" P12 No No G No N/A No Per G.L. 88-01 Inaccessible, pipe vitt be rerouted in 1991.
RWCU-18 RWCU 2605-3 P-E 4" P12 No No G No M/A No Per G.L. 88-01 Inaccessible, pipe witt 4
be rerouted in 1991.
RUCU 19 RWCU 2605-3 E-P 4" P12 No No G No N/A No Per G.L. 88-01 Inaccessible, pipe will be rerected in 1991.
3
$ttac h t t9 --
NLS9000177 Pega 2 -
ITEM 2. 1" SERVICE lSPECT10N PROGRAM '
WEtD NO. SYSTEM 150 EXISTING CFIC SIZE MAT (1) SHT SI (2) IGSCC CRC PAST FL AW - FUTURE COMMENTS -
RUCU-20 RWCU 2605-3 P-E 4" P12 No No G fio N/A No Per G.L. 88-01 Inaccessible, pipe vitt' be rerouted in 1991. .
RWCu-21 RWCU 2605-3 E-P 4" P12 No No G No N/A No Per G.L. 88-01 Inaccessible, pipe will be rerouted in 1991.
RWCU-22 RWCU 2605-3 PE 4" P12 No No G No N/A No Per G.L. C8-01 Inaccessible, pipe will be rerouted in 1991.
RWCU-23 RWCU 2605-3 E-P 4" P12 fio No G No N/A No Per G.L. 88-01 Inaccessible, pipe will be rerouted in 1991.
RWCU-24 RWCU 2605-3 P-P 4" P12 No No G No N/A No Per G.L. 88-01 ~ Inaccessible, pipe will be rerouted in 1991.
RWCU-25 RWCU 2605-3 PP 4" P12 No No 0 No R.O. 12 No Per G.L. 88-01 Will be replaced or deleted 1991 Outage.
RWCU-26 RWCU 2605-3 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-27 RWCU 2605-1 E-P 4" P12 No No 'D No R.O. 12 No Per G.L. 88 01 Will be replaced or deleted 1991 Outage.
RWCU-28 RWCU 2605-1 P-E 4" P12 No No 'D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU 29 RWCU 2605-1 E-T 4" P12 No No D No R .O. '12 No Per G.L. 88-01 Witt be replaced or deteted 1991 outage.
RUCU-29A RWCU 2605-1 P-T 4" P12 No No D No R.O. 12 Per G.L. 88-01 No Witt be replaced or deleted 1991 Outage.
RWCU-30 EWCU 2605-1 T-P 4" P12 Na No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RWCU-31 RUCU 2605-1 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RWCU-32 RWCU 2605-1' E-P 4" P12 No 'No D. No R.O. 12 No ~ Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RWCU-33 RWCU 2605-1 P-E 4" P12 No No D. No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
.3 RWCU 34 RWCU 2605-1 E-P 4" P12 No No .D No' R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
-i .
. , , , , , .%w +. ..e---
Attechmert to- -
NLS9000177 Paga 3 ITEM 2. INSERVICE I?SPECTION PJ.OGRAN EXISTING WELD NO. SYSTEN -ISO CFIG SIZE MAT (1) SHT SI (2) IGSCC CRC PAST FLAW FUTURE COMMENTS -
RWCU-35 RWCU 2605-1 P-E 4" P12 No No D No R.O. 12 No Per G.L. 38-01 Witt be replaced or
~
deleted during the .
1991 Outage.
RWCU-36 RWCU 2605-1 E-P 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RUCU-37 RWCU 2605-1 PE 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RWCU-38 RUCU 2605-1 E-P 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RUCU-39 RWCU 2605-1 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or.
deleted during the 1991 Outage.
KUCU-40 RWCU 2605-1 E-P 4" P12 ~ No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or l deleted during the 1991 Outage.
RWCU-41 RWCU 2605-1 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted W ring the 1991 Outage.
RWCU-42 RWCU 2605-1 E-P 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RUCU-43 RUCU 2605-1 P-P 4" P12 No No D Wo R.O. 12 No Per G.L. 88-01 Will be replaced or deleted during the 1991 Outage.
RWCU-44 RWCU 2605-1 P-E 4" P12 No No D- No R.O. 12 No Per G.L. 88-01 Will be replaced or deleted during the 1991 Outage.
RWCU-45 RWCU 2605-1 E-P 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted during the 1991 Outage.
RWCU-46 RWCU 2605-1 P-E 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or deleted 1991 Outage.
RWCU-47 RWCU 2605-1 E-VA 4" P12 No No D No R.O. 12 Per G.L. 88-01 Witt be replaced or No.
deleted 1991 Outase.
! RWCU-48 RWCU 2513-1 V-P 4" P12 No No D No , R .O. ' 12 No Per C.L. 88-01 Witt be replaced or
' deleted 1991 Outage.
3 m . . ~ - - ~ - -
y ~ - -- - y w. v ____________g______
" Attactusent to -
ELS9000177 Paga 4 ITEM 2. 1" SERVICE ITSPECTION PROGRAN EXISTING wet 0 NO. SYSTEN ISO CFIG SIZE NAT (1) SHT SI (2) IGSCC CRC PAST FLAW FUTURE COMMENTS -
RUCU-49 RWCU 2513-1 PP 4" P12 No No D No R.O. 12 No Per G.L. 88-01 Witt be replaced or ~
deleted 1991 Outage. .
RWCU-63 RWCU 2605-2 T-R 4" F26 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RMCU-64 RWCU 2605-2 TR 4" F26 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU-65 RWCU 2605-2 TP 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.-
RWCU 66 RWCU 2605-2 P-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Reptaced 1990 Outage.
RWCU-67 RWCU 2605-2 P-P 4" P21 No No A No R.O. 13 No Per G.L. 88 01 Replaced 1990 Outage.
RWCU-68 RWCU 2605-2 P-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU-69 RWCU 2605-2 P-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU-70 RWCU 2605-2 P-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RutU-71 RWCU 2605-2 PP 4" P21 No No- A No R.O. 13 No Per G.L. 88-01 Reptoced 1990 Outage.
RuCU-72 RWCU 2605-2 E-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWIU-73 RWCU 2605-2 P-E 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU-74 RWCU 2605-2 T-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU-75 RWCU 2605-2 P-T 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RuCU-76 RWCU 2605-2 N-P 4" P12/P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU-77 RWCU 2605-2 T-P 4" P21 No No A No R.O. 13 ' No Per G.L. 88-01 Replaced 1990 Outage.
RW 9-78 RWCU 2605-2 P-E 4" P21 Yes No A No R.O. 13 No Per G.L. 88 01 Replaced 1990 Outage.
RWCU-79 RWCU 2605 2 E-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RWCU 80 RWCU 2605-2 PE 4" P21 Yes No A No R.O. 13 No Per C.L. 88-01 Replaced 1990 Outage.
RUCU-81 RWCU 2605-2 E-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RMCU-82 RWCU 2605-2 PV 4" F21/P21 No No A- No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RuCU 83 RWCU 2605-2 V-T 4" F20/F26 No No A No R.O. 13 ' No Per G.L. 88-01 Replaced 1990 Outage.
RWCU 84 RWCU 2605-3 P-T 4" P12 Yes No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
i RWCU-85 RUCU 2605-3 E-P 4" P12 Yes No A ho R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
'I RWCU-86 RWCU 2605-3 P-E 4" P12 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
RUCU-87 RWCU 2605-3 P-N 4" P12/P21 No No A No R.O. 13 No Per G.L. 88-01 Replaced 1990 Outage.
-ma,-- #
y r w s- ,.w- y-( . -, - -
Attachseent: t"# -
' ~
l NLS9000177c lPrga 5- ,
ITEM 2. INSERVICE f f'SPECTION P"OGRAM EXISTING W ELD NO.
_ SYSTEM 150 CFIG SIZE MAT (1) SHT SI (2) IGSCC CRC PAST FLAW FUTURE ~ COMMENTS' .
RWCU-88 RWCU 2605-3 T-V 4" F21/F26 No No A No ' R.O. 13 No Per G.L. 88-01 - Reptoced 1990 Outage.~
RUCU 89 RUCU 2605-3 V-P
~
4" F21/F21 No No A No - R.O. 13 No Per G.L.'88-01 Reptoced 1990 Outoge..
RWCU-90 RWCU 2605-3 P-E 4" P21 Yes No . A No R.O. 13 No Per G.L. 88-01 Reptoced 1990 Outege.
RWCU-91 RWCU 2605-3 E-P 4" P21 No No A No R.O. 13 N'o Per s'.L. 88-01 "Reptoced 1990 Outage.
RWCU-92 RUCU 2605-3 P-E 4" P21 Yes No A No R.O. 13 No Per G.L. 88-01 Reptoced 1990 Outage..
RUCU-93 RWCU 2605-3 E-N 4" P12/F26 No No A No R.O. 13 No Per G.L. 88-01 Reptoced 1990 Outage.
RWCU-94 RWCU 2605-4 T-P 4" P21 No No A No R.O. 13 No Per G.L. 88-01 Neptoced 1990 Outoge.
l RWCU-95 RWCU 2605-4 PC 4" P21 No No A No R.O. 13 No Per G.L.'88-01 Reptoced 1990 Outage.-
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Attachment t5 NLS9000177 Prgn 6 ITE1 2. 1"SE'VICE I"SPECTION PROGRAM EXISTING HELD NO. CAT 150 SYSTEM CFIG SIZE MAT (1) (3) SHT SI (2) IGSCC CRC PAST FLAW FUTURE C0sNEENTS CSA-BF-1 B-F CNS-CS-4 Core Spray SE-N 13.44 P20/RPV-1 No Yes A Yes .R.O. 9, 10,- - No Per -
12 G.L. 88-01 ,
CSA-BF-4A B-F CNS-CS-4 Core Spray P-E 10 P20/P2 No Yes A No R.O. 9 No Per G.L. 88-01 r
CSA-BJ-2 B-J CNS CS-4 Core Spray P-SE 10 P20 No Yes A No R .O. 9 . No Per G.L. 88-01 CSA-BJ-3 B-J CNS CS-4 Core Spray P-P 10 P20 No- Yes A No- R.O. 9 No Per G.L. 88-01 CSA-BJ-4 B-J CNS-CS-4 Core Spray E-P 10 P20 No Yes A No R.O. 9 No Per G.L. 88 01 CSB-BF-1 B-F CNS-CS-3 Core Spray SE-N 13.44 P20/RPV-1 No Yes 'A Yes R.O. 9, 10 No Per G.L. 88-01 CSB-GF-4A B-F CNS-CS-3 Core Spray P-E- 10 P20/P2 No Yes A ho R.O. 9, 10 No Per G.L. 88-01 CSB BJ-2 B-J CNS-CS-3 Core Spray P-SE 10 P20 No Yes A No
- R.O. 9, 10 No Per G.L. 88-01 CSB-BJ-3 B-J CNS-CS-3 Core Spray P-P 10 P20 No Yes A No ~R.O. 9, 10 No Per G.L. 88-01 CSB-BJ-4 B-J CNS-CS-3 Core Spray E-P 10 P20 No Yes A No' R.O. 9, 10 No Per G.L. 88-01 CWA-BJ-1 B-J CNS-RWCU-3 RWCU P-P 6 P20 to- Yes .A No R.O. 9 No Per G.L. 88-01' CWA-BJ-2 B-J CNS-RWCU-3 RWCU. P-P. 6 P20 No Yes A No- R.O. 9, 10 No Per G.L. 88 CUA-BJ-3 B-J CNS-RWCU-3 RUCU 1 P-P 6 P20 Yes No; A No R.O. 9 No Per .-,
G.L. 88-01 CWA-BJ 4 B-J CNS-RWCU-3 RWCU P VA 6 P20 No Yes A - No R.O. 9 No Per G.L. 88-01 CWA-BJ-5 B-J CNS-RWCU-3 RWCU VA-P 6 P20 No Yes A No R.O. 9 No Per G.L. 88-01 CUA-BJ-6 B-J CNS-RUCU-3 RUCU P-P 6 P20 No Yes A ho R.O. 9 No Per 'l G.L. 88-01 l CWA-BJ-7 B-J CNS-RWCU-3 RWCU P-VA 6 P20 No Yes A No R.O. 9, 11 No Per ;j i
G.L. 88-01 I
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NLS9000177 l Peg 2 7 ITEM 2. !" SERVICE INSPECTION PROGRAM t
EXISTING '
I WELD N0. CAT ISO SYSTEN CFIG SIZE MAT (1) (3) SNT SI (2) IGSCC CRC PAST FLAW FUTURE ' COMMENTS CWA-BJ-8 B-J CNS-RWCU-3 RWCU VA-P 6 P20 No Yes A. No R.O. 9 No Per .
G.L. 88-C1 CWA BJ 9 B-J CNS-RWCU-3 SWCU P-f 6 P20 No Yes A No 2.0. 9 - No Per G.L. 88-01 CWA-BJ-10 B-J CNS-RWCU-3 RWCU E-P 6 P20 No Yes A No R.O. 9, 10 No Per .'
G.L. 86-G1 .
CWA BJ-11 B-J CNS-RWCU-3 RWCU P-P 6 P20 Yes No -A No See Comment No Per.
- G.L. 88-01 CWA-BJ-12 B-J CNS-RUCU-3 RWCU P-VA 6 P20 No Yes A No R.O. 9, 10 No Per G.L. 88-01 CWA-BJ-14 B-J CNS-RWCU-3 RWCU PP 6 P20 No Yes A No R.O. 9, 10 No Per G.L. 88-01 CWB-BF-8 B-F 2509-1 RWCU P-VA 4 P2/P12 No No D No R.O. 12 No Per .
G.L. 88-01 JPA-BF-1 B-F CE232-241-5 NB SE-N 6 P20/RPV-1 No No A No R.O. 9, 13 No Per G.L. 88-01
- JPB-BF-1 B-F CE232-241-5 NB SE-N 6 P20/RPV-1 No No A No R.O. 9 No Per G.L. 88-01 RAD-BF-7 B-F CNS-RR-37 Recirc. P-P 24 P20/P3 No Yes A No R.O. 9 No- Per G.L. 88 01 RAD-BJ-1 B-J CNS-RR-37 Recire. PU-P 28 P20 No Yes A No R.O. 9, 10 No Per G.L. 88-01 RAD-BJ-2 B-J CNS-RR-37 Recirc. P-VA 28 P20 No Yes .A No R.O. 9, 10 No- Per G.L. 88-01 RAD-BJ-3 B-J CNS RR-37 Recire. VA-P 28 P20 No ' Yes A No ' R.O. 9, 10 No Per G.L.~88 01
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i RAD-BJ-4 B-J CNS-RR-37 recirc. P-T 28 P20 ' No Yes A No R.O. 9, 10 No Per G.L. 88-01 RAD-BJ-5 B-J CNS-RR 37 Recire. T-4W 30 P20 No Yes A No R.O. 9 No - Per.
G.L. 88-01 RAD-BJ 6 8-J CNS-RR-37 Recire. P-T 24 P20 No Yes A No R.O. 9 No Per I G.L. 88-91 RAH-BJ-1 B-J CNS RR-37 Recire. 4W-P 22 P20 No Yes A No R.O. 9 No Per G.L. 88-01
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ITEM 2. INSERVICE trSPECTION PROGRAM EXISTING WELO NO. CAT ISO SYSTEM CFIG SIZE MAT (1) (3) SHT SI (2)~ IGSCC CRC' PAST FLAW FUTURE COINEENTS RAH-BJ-2 B-J CNS-RR-37 Recire. 4W P 22 P20 No Yes A No R.O. 9 - No Per -
G.L. 88-01 ,
RAS-BF-1 B-F CNS-RR-37 Recirc. SE-N 29 P20/RPV-1 No Yes A. Yes R.O. 9, 10 No - Per-G.L. 88-01 RAS BF-12 B-F CNS-RR-37 Recirc. P-P 20 P20/P3 No Yes A No R.O. 9, 10 No Per G.L. 88-01 RAS-BJ-2 B-J CNS-RR-37 Recirc. SE-P 28 P20 No Yes A No R.O. 9, 10 No Per G.L. 88-01 p.
RAS-BJ-3 BJ CNS-RR-37 Recirc. P-T 28 P20 No Yes A No - R.O. 9 No Per G.L. 88-01 RAS-BJ-4 B-J CNS-RR-37 Recirc. T-P 28 P20 No Yes .A No R.O. 9 No Per G.L. 88-01 RAS-BJ-5 B-J CNS RR-37 Recirc. P-VA 28 P20 No Yes A No R.O. 9 No Per G.t. 88-01 RAS-BJ 6 B-J CNS-RR-37 Recirc. VA-P 28 P20- No Yes A No R.O. 9 No Per G.L. 88-01' RAS BJ-6A 8J CNS-RR-37 Recirc. P-WE 28 P20 Yes No A No R.O. 9 No Per
.G.L. 88-01
- RAS-BJ-6B' B-J CNS RR-37 Recirc. WE-F '4 P20 No No A No R.O. 9 - No Per e-'
G.L. 88-01 RAS-BJ-7 B-J CNS-RR-37 Recire. .P-E 28 P20 Yes No A No R.O. 9 No Per G.L. 88-01 RAS-BJ 8 B-J CNS-RR-37 2ecirc. E-PU 28 P20 No Yes' A No R.O. 9 No Per G.L. 88-01 RAS-BJ-9 B-J CNS-RR-37 Recire. T-E 20 P20 No Yes A NoL R.O.- 9 Mo .Per G.L. 88-01 RAS-BJ-10 B-J CNS-RR-37 Recire. W-E 9 P20 Yes No A No R.O. 9 - No Per G.L. 88 01 RAS-BJ-11 B-J CNS-RR-37 Recire. E-E 20 P20 No Yes A No R.O. 9, 10 No Per G.L. 88-01 RBD-BF-7 B-F CNS-RR-38 Recirc. P-P 24 P20/P3 No . Yes A No R.O. 9,'13. No Per G.L. 88-01 RBD-BJ-1 B-J CNS-RR-38 Recirc. PU-P 28 P20 No Yes A No ' R.O. 9 ' No Per G.L. 88-01
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WELD NO. CAT ISO SYSTEM CFIG SIZE MAT (1) (3) SHT SI (2) ICSCC CRC PAST FLAW FUTURE CunnaNTS RBD-8J-2 B-J CNS-RR-38 Recirc. P-VA 28 P20 No Yes 'A No R.O. 9 No Per -
G.L. 88-01 .
RBD-BJ 3' B-J CNS-RR-38 Recire. VA-P 28 P20 No Yes A- No R.O. 9 No- Per
- G.L. 88-01 RBD-BJ-4 B-J CNS RR-38 Recire. P-T 28 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RBD-BJ-5 B-J CNS-RR-38 Recirc. T-4W 30 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RBD-BJ-6 B-J CNS-RR-38 Recirc. P-T 24 P20 Yes No A No R.O. 9 No Per G.L. 88-01 RBH BJ-1 B-J CNS-RR-38 Recirc. 4W P 22 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RBH-BJ-2 B-J CNS-RR-38 Recirc. 4W-P- 22 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RBS-BF-1 B-F CNS-RR-38 Recirc. SE-N 29 P20/RPV-1 No .Yes A Yes R.O. 9, 13 No Per G.L. 88-01 RSS BJ-2 B-J CNS-RR-38 Recire. SE-P 28 P20 No Yes A No R.O. 9 No Per G.L. 88 01 RBS-BJ-3 B-J CNS RR-38 Recirc. P-P 28 P20 No Yes A No R.O. 9 No Per
-G.L. 88-01 RBS BJ-4 B-J CNS-RR-38 Recirc. P-P 28 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RBS BJ-5 B-J CNS-RR-38 Recirc. P VA 28 P20 No- Yes A No R .O.' 9 - No- Per G.L. 88-01 RBS-BJ-6 B-J CNS-RR-38 Recire. VA-P 28 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RBS-BJ-6A B-J CNS-RR 38 Recirc. P-VE 28 P20 Yes No A No R.O. 9 No Per G.L. 88-01
. RBS-BJ-6B B-J CNS-RR-38 Recirc. WE-F 4 P20 No No- A No R.O. 9 No Per G.L. 88-01 RBS-BJ-7 B-J CNS-RR-38 Recire. P-E 28 P20 Yes No A No - R.O. 9 iNo Per G.L.'88-01 RBS-BJ-8 B-J CNS-RR-38 Rectrc. E-PU 28 P20 No Yes A No R.O. 9 No Per G.L. 88-01
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ITE3 2. I" SERVICE trSPECTION PROGRAM EXISTING' WELD NO. CAT ISO SYSTEM CFIG SIZE MAT (1)'(3) SHT SI (2) IGSCC CRC PAST FLAW FUTURE COMMENTS RCA-BF-1 B-F N/A NB N-SE 5 P18/RPV-1 No. No D No R.O. 11, 13 .No Per G.L. 88-01 .
RRA-BF-1 BF CNS-RR-38 Recire. SE-N 14 P20/RPV-1 No Yes A Yes' R.O. 9 No Per G.L. 88-01 RRA-BJ-2 B-J CNS-RR-38 Recire. P-SE -12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRA-BJ-3 8-J CNS-RR-38 Recirc. P-P 12 P20 No Yes A No R.O. 9 No Per G.L. 88 01 RRA-BJ-4 B-J CNS-RR-38 Recirc. P-E 12 P20 Yes No A No R.O. 9 No Per G.L. 88-01 RRA-BJ-5 B-J CNS-RR-38 Recirc. R-E 12 P2O No Yes A No R.O. 9 ~ No Per G.L. 88-01 RRB BF-1 B-F CNS-RR-38 Recirc. SE-N 14 P20/RPV-1 No Yes A Yes R.O. 9 No Per G.L. 88-01 RRB-BJ-2 B-J CNS-RR-38 Recirc. P-SE 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRB-BJ-3 B-J CNS-RR-38 Recirc. T-P 12 P20 No. Yes A No R.O. 9 No Per G.L2 88-01 RRC-8F-1 B-F CNS-RR-38 Recirc. SE-N 14 P20/RPV-1 No Yes A ' Yes R.O. 9, 10 .No Per G.L. 88-01 RRC-BJ-2 B-J CNS-Rk-3o Reclec. P-SE .12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRC-BJ-3 B-J CNS-RR-38 Recirc. R-P 12 P20 No Yes A No R.O. 9 No. Per G.L. 88-01 RRD OF-1 BF CNS-RR-38 Recirc. SE-N 14 P20/RPV-1 No Yes A Yes R.O. 9 No Per G.L. 88-01 RRD-BJ-2 BJ CNS-RR-38 Recire. P-SE 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRD-BJ-3 B-J CNS-RR-38 Recirc. T-P. 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRE-BF-1 B-F CNS-di-39 Recirc. SE-N 14 P20/RPV-1 No Yes
-A Yes 'R.O. 9, 10 No Per G.L. 88-01 RRE-BJ-2 ' B-J CNS-RR-38 Recirc. P-Sr 12 P20 No Yes A No R.O. 9, 10 No - Per G.L. 88-01
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NLS9000177 Prga 11 ITEM 2. INSERVICE INSPECTION PROGRAM EXISTING WELD NO. CAT ISO SYSTEM CFIG SIZE MAT (1) (3) SHT SI (2) IGSCC CRC PAST' FLAW FUTURE COMMENTS RRE-BJ-3 B-J CNS-RR-38 Recirc. P-P 12 P20 No Yes A No R.O. 9, 10 ' No Per G.L. 88-01 RRE-BJ-4 B-J CNS-RR-38 Recirc. P-E 12 P20 Yes No A No R.O. 9, 10 No Per G.L. 88-01 RRE-BJ 5 B-J CNS RR-38 Recirc. R-P 12 P20 No Yes A No R.O. 9, 10 No -Per G.L. 88-01 RRF BF-1 BF CNS-RR-37 Recirc. SE-N 14 P20/RPV-1 No' Yes A Yes R.O. 9 No Per G.L. 88-01 RRF-BJ-2 BJ CNS RR-37 Recirc. P-E 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRF-BJ 3 B-J CNS-RR-37 Recirc. P-P 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRF-BJ-4 B-J CNS-RR-37 Recirc. P-P 12 P20 Yes Yes A Eo R.C'. 9 No Per G.L. 88-01 RRF-BJ 5 B-J CNS RR 37 Recire. R-P 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRG-BF-1 B-F CNS-RR-37 Recirc. SE-N 14 P20/RPV-1 No Yes A. Yes R.O. 9 No Per G.L. 88-01 RRG-BJ-2 B-J CNS-RR-37 Recirc. P-SE 12 P20 No Yes A No R.O. 9 No Per G.L. 88-01 RRG-BJ-3 B-J CNS-RR-37 Recirc. T-P 12 P20 No Yes A No R.O. 9 No Per G.L. 88 01 RRH-BF-1 B-F CN. RR-37 Recirc. SE-N '14 P20/RPV-1 No Yes A Yes R.O. 9, 10 No Per G.L. 88-01 RRH-BJ-2 B-J CNS-RR-37. Recire. P-SE 12 P20 No Yes. A No R.O. 9, 10 No Per G.L. 88-01 RRH BJ-3 B-J CNS-RR-37 Recire. R-P 12 P20 No Yes A No R.O.' 9, 10 No Per G.L. 88-01 RRJ-BF-1 B-F CNS-RR-37 Recire. SE N P20/RPV-1 No Yes. A Yes R.0, 9i 12 No Per G.L. 88-01 RRJ-BJ-2 B-J CNS-RR-37 Recire. P-SE 12 P20 No Yes A No- R.O. 9 No Per G.L. 88-01 i RRJ BJ-3 B-J CNS-RR-37: Recirc. T-P 12 P20 ' no Yes A No R.O. 9 No Per G.L. 88 01 9
9
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NLS9000177.. - E Pcg2 12- '.
liEM 2. INSERVICE I"SPECTION PROGRAM ..
EXISTING UELD NO. CAT ISO SYSTEM' CFIG SIZE MAT (1) (3) SHT SI (2) IGSCC CRC PAST FLAW FL'TukE COM ENTS RRK-BF-1 8-F CNS-RR-37 Recirc. SE-N 14 P20/RPV-1 No. Yes A- Yes " R.O. 9, 12 No Per ,s G.L. 88-01 -
RRK-BJ-2 e-J .CNS-RR-37 Recire. P-SE 12 P20 No Yes A No R.O. 9 . No' ~ Per'-
G.L. 88-01 RRK-BJ-3 8-J CNS-RR-37 Recire. P-P 12 P20 No Yes -A No R.O. 9 . No- L+r G.L. 88-01 RRK-8J-4 B-J CNS-RR-37 Recire. P-P 12 P20 Yes No A No R.O. 9 No Per G.L. 88-01 RRK-8J-5 B-J CNS-RR-37 Recire. P-P 12 P20 No Yes A No R.O. 9 ' No- Per G.L. 88-01 :
w
- Weld located inside penetration and is considered inaccessible.
- Witt be replaced or deleted in 1991.
(1) Nonconforming Material' - P12, ASTM-A-312 TYPE 304 F19, ASTM-A-403 GRADE WP-304 Conforming Material - P20, 316 NG P21,.SA/A-312 iP316t~
F20, A-403 GR WP-316 F21, A-182 GR F-316 F26,.SA/A-403 WP-316L F27, SA/A-182 GR F-316L Other Materlat -
P18, SB-166 Inconet -
4 (2) The Stress Improved SI, method utilized by NPPD'was Induction Heating Stress improvement. Pre and post' treatment in pections were performed .,
within two years of the service date using methods and personnel approved by the NRC.
(3) xxx/xxx indicates a staintess steet to carbon steel weld.
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