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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny ML20206S2541999-01-20020 January 1999 Confirms Resolution of Thermo-Lag Fire Barriers in Fire Zones OB-FZ-6A & OB-FZ-6B (480 Switchgear Rooms) IAW Previous Commitments Contained in Gpuns Ltrs to NRC & 971001 ML20199J2631999-01-18018 January 1999 Requests That Listed Changes Be Made to Correspondence Distribution List for Oyster Creek Generating Station ML20199D0271999-01-11011 January 1999 Requests Listed Addl Info in Order to Effectively Review TS Change Request 264 Re Ownership of Property within Exclusion Area ML20199A6521999-01-0707 January 1999 Notifies That Reactor Operators G Scienski,License SOP-11319 & D Mcmillan,License SOP-3919-4 Have Terminated Licenses at Oyster Creek Nuclear Generating Station, Effective 990101 ML20198T1061999-01-0606 January 1999 Forwards Rev 15 to Gpu Nuclear Corporate Emergency Plan for TMI & Oyster Creek Nuclear Station. with Summary of Changes Which Reflect Use of EALs Approved in NRC Ltr to Gpun on 980908 & Other Changes Not Related to Use of New EALs ML20198K0331998-12-23023 December 1998 Forwards Change Request 268 for Amend to License DPR-16. Amend Would Change TS to Specify Surveillance Frequency of Once Per Three Months ML20198H0181998-12-22022 December 1998 Forwards Attachment Addressing New Info & Modifying 980505 Submittal Re Request for Change to Licensing Bases for ECCS Overpressure,In Response to NRC Bulletin 96-03, Potential Plugging of ECCS by Debris in Bwrs ML20198H8521998-12-16016 December 1998 Dockets Completion of Physical Inventory Performed in July 1997,as Addl Info to Nuclear Matl Balance Rept Submitted on 980416 ML20196H4461998-12-0202 December 1998 Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits ML20196B4471998-11-23023 November 1998 Provides Required Response 2 to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers in Bwrs. During Recently Completed 17R Refueling Outage,New Strainers Were Installed ML20195J8451998-11-12012 November 1998 Forwards Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan, as Change Previously Made Without Appropriate Notification to NRC ML20195C7201998-11-11011 November 1998 Forwards 120-day Required Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment, ML20195E1221998-11-10010 November 1998 Notifies NRC of First Time Usage of Code Case N-504 & Inclusion Into OCNGS ISI Program,As Accepted by RG 1.147, Inservice Insp Code Case Acceptability ML20155J6851998-11-0505 November 1998 Forwards TS Change Request 266,to Modify Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & Verify Channel Operability ML20155H5641998-11-0202 November 1998 Informs That Bne Has No Comments on Proposed Change 259 to Ts,Correcting Required Water Level in Condensate Storage Tank So That Design Basis Is Correctly Implemented ML20155G3741998-10-29029 October 1998 Forwards Response to NRC 980619 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L2551990-09-14014 September 1990 Advises of Preparation for Final Refueling Outage to Complete Second 10-yr Interval for Inservice Insps ML20059F5121990-09-0505 September 1990 Requests Exemption from Filing Requirement of 10CFR55.45(b)(2)(iii) to Allow Submittal of NRC Form 474, Simulator Facility Certification, After 910326 Deadline & to Allow Administering of Simulator Portion of Test ML20059F7441990-08-31031 August 1990 Forwards Util Review of NRC Backfit Analysis for Hardened Wetwell Vent.Nrc Analysis Does Not Support Conclusion That Hardening Existing Vent Is cost-beneficial Mod for Plant ML20059E9061990-08-30030 August 1990 Forwards Response to 900808 Request for Addl Info Re NRC Bulletin 90-002, Loss of Thermal Margin Caused by Fuel Channel Box Bow ML20059G1841990-08-29029 August 1990 Ack NRC Request to Perform Type C Testing During Unscheduled Outage,As Plant Conditions Will Allow.Type C Exemptions Should Remain in Effect Until New Outage Start Date ML20059C8231990-08-27027 August 1990 Advises That SPDS Enhancements Described in Completed,Per 900628 Request.Offline & Online Testing Completed & Enhancements Considered to Be Operational ML20059C8571990-08-24024 August 1990 Provides Results of Evaluation of Ability to Meet Acceptance Criteria for Eccs,In Response to 900804 Notice of Violation. Plant Meets Acceptance Criteria Contained in 10CFR50.46 W/ Valve Logic Design Deficiency in Containment Spray Sys ML20058N0781990-08-0909 August 1990 Submits Info Re pressure-temp Operating Limits for Facility, Per Generic Ltr 88-11.Util Recalculated Adjusted Ref Temp for Each Belt Line Matl as Result of New Displacement Per Atom Values ML20063P9521990-08-0909 August 1990 Advises That Response to NRC 900523 Request for Assessment of Hazardous Matl Shipment Will Be Sent by 910531 ML20058L9521990-08-0303 August 1990 Forwards Rev 2 to Security Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20058L9551990-08-0303 August 1990 Responds to SALP Rept 50-219/88-99.Although Minor,Several Factual Errors Noted.Dialogue Promotes & Identifies Areas Where Improvements Should Be Made ML20056A2071990-07-30030 July 1990 Forwards Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Record Review Performed & Sys Walkdowns Completed to Assemble Requisite List ML20055H7961990-07-20020 July 1990 Advises of Change to Preventive Maint Program for Electromatic Relief Valves.Rebuild Schedule Will Be Modified to Require Rebuilding Two or Three Valves During Refueling Outage & Remaining Valves During Next Refueling Outage ML20058N9911990-07-20020 July 1990 Partially Withheld Response to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Box Bow (Ref 10CFR2.790(b)(1)) ML20055J0481990-07-19019 July 1990 Requests 2-wk Extension for Submittal of Response to Re Installation of Hardened Wetwell Vent W/ Appropriate Extension Period to Be Decided Pending Outcome of 900724 Meeting Discussion W/Bwr Owners Group ML20064A1221990-07-11011 July 1990 Discusses 900710 Telcon W/Nrc Re Util Corrective Actions in Response to NRC Finding That Operator Received Passing Grade on Administered Requalification Exam in 1989 Should Have Received Failing Grade.Corrective Actions Listed ML20055F8491990-07-10010 July 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 188,reducing Low Condenser Vacuum Scram Setpoint ML20043H7471990-06-21021 June 1990 Confirms Telcon W/A Dromerick Re Util Plans to Inspect CRD Hydraulic Control Units During Plant Walkdown to Address USI A-46, Seismic Qualification of Equipment in Operating Nuclear Power Plants. Walkdown Planned in Oct 1992 ML20043H2301990-06-14014 June 1990 Documents Licensee Commitment to Improve Seismic Restraints for Diesel Generator Switchgear Encls,Per 900613 Telcon W/ Nrc.Engineering Will Be Finalized & Mods Completed Prior to 900622 ML20043F7581990-06-0707 June 1990 Responds to Request for Info Re Util Compliance W/Generic Ltr 88-01 & Insp Plans for Upcoming 13R Outage.Frequency of Insp of Welds Classified as IGSCC Categories C,D & E Will Not Be Reduced During 13R Outage ML20043C5801990-05-25025 May 1990 Provides Descriptions & Conclusions of Three Remaining Issues of SEP Topic III-7B.Issues Include,Evaluation of Drywell Concrete Subj to High Temp & Thermal Transients ML20043C2461990-05-25025 May 1990 Forwards Rev 7 to EPIP 9473-IMP-1300.06 & Rev 4 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Emergency Dose Calculation Manual. ML20043B2981990-05-21021 May 1990 Responds to NRC 900420 Ltr Re Violations Noted in Insp Rept 50-219/90-06.Corrective Actions:Incident Critique Rept Incorporated as Required Reading for Appropriate Operations Personnel & Change Made to Procedure 201.1 ML20043D0701990-05-17017 May 1990 Provides NRC W/Addl Info Re SPDS & Responds to Concerns Raised During 900117 & 18 SPDS Audit Documented in 900130 Ltr ML20043B3901990-05-0909 May 1990 Responds to NRC 900408 Ltr Re Violations Noted in Insp of License DPR-16.Corrective Actions:Two Narrow Range Drywell Pressure Monitoring Instruments to Be Provided During Cycle 14R Refueling Outage,Per Reg Guide 1.97,Category 1 ML20042G7071990-05-0808 May 1990 Forwards Summary of Initiatives & Accomplishments Re SALP, Per 891031 Commitment at mid-SALP Meeting.Plant Div Responsibilities Now Include Conduct of Maint Outages & Emergency Operating Procedure Training Conducted ML20042G2291990-05-0707 May 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 180,revising Tech Specs Re Fuel cycle-specific Parameters ML20042G2601990-05-0404 May 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 187,revising Tech Specs to Accommodate Implementation of 24-month Plant Refueling Cycle ML20042E9431990-04-20020 April 1990 Forwards Revised Epips,Consisting of Rev 7 to 9473-IMP-1300.01,Rev 4 to 9473-1300.11 & Rev 2 to 9473-ADM-1319.04.Deleted EPIPs Listed,Including Rev 3 to 9473-1300.19,Rev 2 to 9473-1300.21 & Rev 5 to 9473.1300.24 ML20042E6371990-04-16016 April 1990 Informs of Plans to Install Safety Grade Check Valve in Supply Line Inside Emergency Diesel Generator Fuel Tank Room Coincident W/Replacement or Repair of Emergency Diesel Generator Fuel Oil Tank ML20042E5001990-04-13013 April 1990 Forwards Rev 1 to Topical Rept 028, Oyster Creek Response to NRC Reg Guide 1.97. ML20012E8711990-03-28028 March 1990 Lists Property Insurance Coverage,Effective 900401,per 10CFR50.54(w)(2) ML20012D4391990-03-19019 March 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 186,allowing Idle Recirculation Loop to Be Isolated During Power Operation by Closing Suction,Discharge & Bypass Valves ML20012B6781990-03-0202 March 1990 Requests Exemption of Specified Local Leak Rate Test Intervals to Include Next Plant Refueling Outage Scheduled for Jan 1991,per 10CFR50,App J ML20012A1501990-02-23023 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 184,removing 3.25 Limit on Extending Surveillance Intervals,Per Generic Ltr 89-14 ML20011F2571990-02-21021 February 1990 Advises That 891003 Request for Appropriate Tech Specs for Chlorine Detection Re Control Room Habitability,Not Warranted ML20006G0101990-02-21021 February 1990 Discusses 900110 Meeting W/Nrr Re 13R Insp Criteria for RWCU Welds Outboard of Second Containment Isolation Valve. All Welds Required 100% Radiography Based on Review of Piping Spec.Response to Generic Ltr 88-01 Will Be Revised ML20006F5931990-02-20020 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 177.Amend Changes Tech Spec 4.7.B to Include Battery Svc Test Every Refueling Outage & Mod of Frequency of Existing Battery Performance Test ML20011F6641990-02-20020 February 1990 Responds to NRC 900122 Notice of Violation & Forwards Payment of Civil Penalty in Amount of $25,000.Corrective Actions:Change Made to Sys Component Lineup Sheets in 125- Volt Dc Operating Procedure to Include Selector Switches ML20006F9181990-02-15015 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 183,permitting No Limitation on Number of Inoperable Position Indicators for 16 ASME Code Safety Valves During Power Operation ML20006D2551990-01-30030 January 1990 Forwards Response to Generic Ltr 89-13 Re Plant Svc Water Sys.Insp Program for Intake Structure at Plant Implemented During Past Two Refueling Outages & Emergency Svc Water Currently Chlorinated to Prevent Biofouling ML19354E8571990-01-24024 January 1990 Forwards Omitted Pages of 900116 Ltr Re State of Nj DEP Comments on Draft full-term OL SER & Clarification of Page 10,fourth Paragraph on New Seismic Floor Response Spectra ML20006B2171990-01-23023 January 1990 Responds to Unresolved Items & Weaknesses Identified in Insp Rept 50-219/89-80.Corrective Actions:Procedure Re Containment Spray sys-diagnostic & Restoration Actions Revised to Stand Alone Re Installation of Jumpers ML19354E3891990-01-19019 January 1990 Responds to Violations Noted in Insp Rept 50-219/89-27. Corrective Actions:Procedure 108 Revised to Allow Temporarily Lifting of Temporary Variation ML19354E8441990-01-19019 January 1990 Forwards Revised Tech Spec Table 4.13-1, Accident Monitoring Instrumentation Surveillance Requirements, in Support of Licensee 890630 Tech Spec Change Request 179,per NRC Project Manager Request ML20006B2881990-01-18018 January 1990 Forwards Results from Feedwater Nozzle Exam,In Accordance w/NUREG-0619 Insp Format ML20005G8161990-01-16016 January 1990 Provides Assessment of State of Nj Concerns Re full-term OL Plant,Per NRC 891222 Request.Comments Did Not Raise Any Concerns That Refute Conclusions Reached by NRC That Facility Will Continue to Operate W/O Endangering Safety ML19354D8281990-01-15015 January 1990 Responds to Violation Noted in Insp Rept 50-219/89-21. Corrective Action:Procedure A000-WMS-1220.08, Mcf Job Order Revised to Provide Detailed Guidance for Performance of Immediate Maint ML20042D4891989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Fulfilling 6-month Reporting Requirement ML20005E1401989-12-22022 December 1989 Forwards Integrated Schedule Semiannual Update for Dec 1989 1990-09-05
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GPU Nuclear Corporation NU01Mr One Upper Pond Road Parsippany, New Jersey 07054 201 316-7000 TELEX 136-482 Writers Direct Dial Number January 18, 1990 U.S. Nuclear Regulatory Commission 5000-90-1857 Attentions Document Control Desk Washington, D.C. 20555 Centlemer.:
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 License No. DPR-16 Feedwater Nozzle Examination Reference GPUN Letter 11/20/85 During 12R, GPUN completed an automated ultrasonic examination of welds, inner radii and inner bores of four feedwater nozzles from externsi vessel and nozzle surfaces. For this examination, GPUN contracted for a state of the art (phased-array) UT technique with advanced tomographic data analysis. Since no indications were determined as being reportable, we did not perform dye penetrant and visual examinations of the nozzle internal diameters. The results from this inspection are presented in the Attachment in accordance with the NUREG 0619 format.
l> As part of our commitment to the NUREG 0619 inspection requirements, oyster Creek is scheduled to perform an internal dye penetrant examination of the feodwater and control rod drive return line (CRDR) nozzles. In light of our 12R experience with this UT technique, CPUN has concluded that this inspection technique is a suitable alternative to an internal dye penetrant examination to asecas nozzle integrity. By a separate submittal, GPUN will provide our basis for eliminating the 13R internal dye penetrant examinations for both the feedwater and CRDR nozzles. If you have any questions concerning the resulto from the 12R examination or the future submittal, please contact Mr. M. W.
Laggart at (201) 316-7968.
Very truly yours, A
k J. C. DeVine Vice President & Director Technical Functions DKC/DJ/cjg Attachment 9002010261 900118 O-PDR ADOCK 05000219 Q PDC ,
50-219 GPU Nuclear Corporation is a subsidiary of General Public Utdities Corporation '/
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-.' 'ces Regional Administrator Region.1 U.S. Nuclear Regulatory Commission 475 A11endale Road King of Prussia,PA 19406 Resident 2nspector t- oyster creek Nuclear Generating Station Mr. Alex Dromerick U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington, D.C. - 20555 L
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,, ATTACHMENT RESPONSES TO NUREG 0619 NUREO 0619 ITEM fa)
Number of startup/ shutdown cycles since the previous inspection, and the total number of cycles. This will include cycles accumulated.during the initial startup and testing of the plant.
Response
Between-the previous feedwater noanle inspection-(7R) and the most recent inspection (12R), there have been seventy three (73) start-up/ shutdown cycles (i.e. planned or forced outages). The total number of start-up/ shut-down cycles accumulated up to the 12R outage is one hundred and fifty seven-(157).
NUREG 0619 ITEM (b)
Summary of methods used and results of previous' inspections, including maximum crack depth and number of cracks found in previous PT-and-grinding operations, and number of startup/ shutdown cycles between such inspections.
Resnonse
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The summary of methods and the results from the 1977 inspection of feedwater nozzles A, B, C and D are delineated below. The number of cycles between inspections are in our response to item (a).
Initial Indications Inspection areas were laid out on each feedwater nozzle covering from the I.D.
of vessel shell to nozzle forging weld to a distance 7 1/8"'into the nozzle bore from the ve:sel wall (the extent of cladding into the bore)'. The inspection areas were cleaned of all oxide with flapper wheels,_ rags and acetone. The results of the internal dye penetrant examination showed 54 unacceptable indications. The 45' nozzle contained the largest number _of indications but the worst were in the 225' nozzle.
45' nozzle - 36 indications 1/2" -L4" long 135' nozzle - 3 indications 1" - 2 1/2" long 225' nozzle - 4 indications 2" - 12" long with numerous branches 315' nozzle - 11 indications 1" - 12" long Indleations Subsecuent to Clad Removal Upon completion of clad removal,_the machined surfaces were dye penetrant-inspected. The examinations revealed the following number of indications:
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45' n: :10 - 5 indicati*ns 1/2' - 1 1/2" long 135' nozzle - No indications !
225' nozzle - 4 indications 1/2" - 3" long 315' nozzle - 3 indications 1/4" - 1" long ;
All indications were removed by hand with pencil grindere using tungsten {
carbide burra. Ground out areas were blended to a 3:1 slope and polished with flapper wheels. The nozzles were etched with a 5% nitric acid / isopropyl ;
alcohol solution to determine if all the cladding had been_ removed from the ;
bore and radius. Patches of cladding remained at 12 and 6 o' clock positions on l the blend radii of most nozzles. All of the cladding was removed using pencil r grinders and tungsten carbide burra. The ground out areas were blended and l polished with flapper wheels and dye penetrant inspected. [
The final condition of the nozzles was photographed. The deepest grindout was !
7/32" in the 315' nozzle. The condition of the nozzles was as follows:
45' nozzle - 5 grindoute 1/32" - 1/8" depth 135' nozzle - no grindoute 225' nozzle - 3 grindoute 3/64" - 1/16" depth 315' nozzle - 3 grindoute 1/32" - 7/32" depth i NUREG 0619 Item tel Description of any additional system changes or changes in operating procedurec that will affect feedwater flow or temperature and that should be considered in ,
predicting future cracking tendencies based on-past history.
Reenonces ;
No changes to the system or the operating procedures are currently planned'for !
Cycle 12 which could affect normal feedwater flow or temperature. In order to .
more. effectively control reactor water level during start-ups and shutdowns, a i block valve will be' installed during 13R to stop leakage from the feedwater regulating valve which can bypass the low flow feedwater regulating valve. +
i NUREO 0619 Item (D) -!
A detailed discussion of the inspection results, including a complete l
description of cracking location, dimensions, and profile, if cracking was-found. Drawings and photographs, if available, are requested.
4 Broponeet For the purposes of the UT inspection, the Nozzle interior was segmented intoi three zones. These zones were defined as follows: Zone 1 - the nozzle inner radius; Zone 2A - the nozzle inner bore region from Zone 1 to the OD blend f region; and Zone 2B the nozzle inner bore region in the range of the nozzle {
boss (see attached sketch).
Ne indications were interpreted to be cracks in feedwater nozzles A, B, C, and D. A' summary of the inspection results for each nozzle is provided below: j i
NOZZLE: FEEDWATER NOZZLE "A" '
INSPECTED AREA: NOZZLE TO SHELL WELD-4-566-A (scanning-limited-from 210' to, .{
305' due to adjacent nozzles on vessel OD-surface), ZONE'1, 4 ZONE 2A AND ZONE 2B-(full coverage); ;
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' EXAMINATION RESULTS: j t
- The required sensitivity (signal to noise ratio) was achieved in all areas.
- The calibration rechecks confirmed the system sensitivity,to be within the required tolerances.
- The UT signals were ovaluated utilizing the appropriate display methods:
-C-scan
-Tomography
-Time Displacement
-A-Scan
-Soundpath Trajectory Reconstruction
- Based upon these criteria indications observed were determined.to be caused by geometry.
- Multiple indications, out of the vessel mid-wall, reaching or exceeding recording threshold, were observed during scanning for lamination type indications in the vessel wall throughout the entire circumference. The amplitude of the backwall reflection did not diminish significantly;.
indications observed were acceptable and did not interfere.with.the angle I
beam inspection as noted by the ability to' maintain angle beam signal to noise ratio.
i NOZZLE: Feedwater Nozzle "B" l
INSPECTION AREA: Nozzle to shell weld 4-566 B, Zone 1, Zone 2A and Zone 2B; NOZZLE: Feedwater Nozzle "C" INSPECTED AREA: Nozzle to Shell Weld 4-566c (scanning limited from 210' to.
300* due to adjacent nozzles on vessel OD-surface),JZone 1, Zone +2A and Zone 2B~
(full coverage);
NOZZLE: Feedwater Nozzle "D" INSPECTED AREA: Nozzle to Shell Weld 4-566 D,-Zone 1, Zone 2A-and Zone 2B;.
l EXAMIllhTION RESULTS . NOZZLES B, C, AND D The required sensitivity (signal to noise ratio) was achieved.in all areas.
The calibration rechecks confirmed the system sensitivity to be within the required tolerance.
The UT signals were evaluated utilizing the appropriate display methods:
-C-Scan
-Tomography
-Time Displacement
-A-Scan
-Southpath Trajectory Reconstruction 50-219
- Based upon.these. criteria indications observed were determined to be caused by geometry.
- Therefore, no reportable indications were detseted.
NUREG 0619 ITEM fe)
Information regarding the results of leakage monitoring. However, the staff.
must be informed immediately if on-line leakage monitoring during operation discloses any leakage on welded spargers or lea'< age on the order of 0.3 gpm through single-eleeve/ single-piston-ring spargers or triple-sleeve spargers.
Response
Up to the~12R refueling outage, Oyster Creek had no on-line. leakage monitoring system. During 12R, Oyster Creek installed a Thermal Transient Monitoring System (TTMS), a modified version of EPRI "Fatique-Pro", which has the capability for leakage monitoring.
The TTMS not only provides a record of the actual traabients encountered in service, but also gives a real time update of the remaining fatigue resistance of the nozzles. In addition, the minimum flaw detection performance of the regulatory required UT inspection is also shown to be satisfactory by the-l TTMS. Actual transients are translated into pressure and thermal stresses-which are interacted, by means of linear elastic fracture mechanics, with l
established minimum detectable crack size, in order to show that such a hypothetical flaw will'not propagate, by the next scheduled inspection, to,a l depth requiring repair, using ASME Section XI criteria.
l Five RTD's were placed on the FW nozzle and pipe. Four_RTD's were located downstream of the piston ring seal at one axial position and one upstream.
Leak detection sensitivity is enhanced by the placement of the RTD's which are located more toward the bottom of the annulus than the top. Cooler, more dense leakage past the seal tends to fall and collect at the bottom of the annulus where the instruments are located.
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A calibration option allows comparison of measured with calculated outer surface temperatures. The calculated value has the built-in assumption that there-is very low leakage. A trend of-increasing departure over~a long period!
nf time of predicted surface temperature from measured values is evidence of increasing leakage. A leakage increase. detection threshold equal'to 2.0 gpm is the theoretical sensitivity of the leak detection capability.=
NUREG 0619 ITEM ff)
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Information regarding all UT crack-like indications and any subsequent PT indications. Information regarding UT techniques should be as precise and as.
extensive as possible in order that it may be of benefit in future inspections.
Response
Information regarding all UT indications is described in response to. Item D.
Since no indications were considered reportable, no PT examinations were performed.
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e CPUN C0ttblich;d twl obj:ctiv03 to be fulfillcd by- th] 12R ultrOO:nio examinations (UT). The first objective was to complete the ASME Section XI examinations required for the present 10 Year Interval. The second objective r was to complete a UT examination of the four feedwater nozzles which would.
comply with the requirements of NUREG-0619, BWR Feedwater Nozzle and Control ;
Rod Drive Return Line Nozzle Cracking. GPUN chose to add a condition onto the second objective which required the examination technique to be capable of r reliably detecting a 1/8" deep by 1/4" long axial crack on the nozzle interior ;
yet be capable of distinguishing a flaw of this size from non-flaw' conditions [
such as nozzle repair grindouts. }
Access to the nozzles was limited to the CD surface because feedwater sparger' i disassembly would be necessary for ID access. The flaws of interest are predominantly axially oriented originating on the nozzle interior in the presently unciad portion of the nozzle. ,
The geometry of the vessel nozzle involves a cylinder being interrected by a second cylinder. This geometry requires an approach involving three ;
dimensional logic rather than the normal two dimensional logic required for examining most welds such as vessel longitudinal or circumferential welds. The geometry required that the nozzle interior be segmented into three distinct zones in order to track all parameters from the examination development stage ,
through the final field examination evaluation stage. These zones are i delineated on the attached sketch.
GPUN evaluated potential contractors based on the results of a " blind run" on a full scale oyster Creek feedwater nozzle mock-up.' The simulated flaws were axially oriented end mill notches located in all three zones both in simulated grindouts and outside simulated grindouts. Grindouts were those local areas of grinding that occurred after cladding removal to' facilitate flaw removal. Zone 1 contained thirteen total flaws ranging in depth from 0.030" to 0.468" and +
lengths of 0.250" to 1.570" with two located'in grindouts. Zone 2A contained _
nine total flaws ranging in depth from 0.070" to 0.365" and lengths of 0.250" -
to 2.0" with two located in grindouts. Zone 2B contained eleven-total flaws ranging in depth from .091" to 0.435" and lengths of 0.250" to 1.010". The vendor was allowed access to four flaws in Zone 1, three flaws in Zone 2A, and ;
three flaws in Zone 2B for use as calibration reflectors. l The contractor chose Zone 1 and 2A examination incidence and lateral skew angles based on 3-D finite modeling and experimentation; Zone 2B is basically a ,
hollow cylinder and the examination approach is the same as'for a piece of pipe. Skew angle is extremely important for examination of Zones 1 and 2A because the corner trap for sound reflection is-formed 3 dimencionally as a ;
result of skew and incidence angle rather than incidence angle alone. The skew >
angle necessary is dependent on incidence angle,-distance from the nozzle centerline, and circumferential location around the nozzle.
The contractor chose to control the automated examination system search unit skew angle electronically by steering the sound rather than mechanically by ,
physically rotating the search unit. This required use of a " Phased Array" technique. The phased array system utilizes a transducer which is' segmented to -
allow for individual excitation of each segment. Each segment is sequentially !
excited to produce a steering effect (skewed angle beam), yet the timing allows t
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. tha tren:due:r to cet c3 o cing10 at nd2rd s Orch unit of cimi10r ciz3 cnd frequency. Conversely, when the search unit is in the receive mode, each segment is individually listened to and electronically delayed to produce results similar to a standard search unit. This description is applicable to search units designed for skewing; however, the same principal may be applied to search units segmented in the opposite direction (lateral) for controlling incidence angle.
The Oyster Creek nozzle mock-up was shipped to the contractor to allow for improvement of exam techniques in mutually agreed areas. A reproduceability qualification was performed following system improvements. This qualification required locating and sizing of three flaws each in Zones 1, iA, and 2B with three separate mountings of the examination manipulator. -The final examination technique for Zone 1 required the use of 57' and 65' shear wave phased array search units from the vessel shell skewed 114*-to 130'. The zone 2A technique-utilized 72* shear wave and creeping wave phased array search units from the vessel shell skewed 112' to 125'.- The :one 2B technique utilized 21* and 33' phased array incidence angles with no search unit skew angles from the nozzle -
boss.
The examination manipulator consisted of a circular split mounting ring mounted on the nozzle safe-end with separate control arms for the nozzle bons and vessel shell exams. Scanning motion was circumferential around the nozzle (Zones 1 and 2A) or nozzle boss (Zone 2B) indexed in distance from the nozzle center 13ne (zones 1 and 2A) or vessel wall (Zone 2B). Domineralized water couplant was supplied to the search unit which was designed to form a water.
film containment thus eliminating coupling pressure au an essential variable.
All digitized A-scan responses from specifically gated regions were recorded during the examination. This method of recording allowed for reconstruction of numerous display presentations which could be used during data evaluation performed off-line.
Seven different data displays were utilized for data evaluation. -The displays and descriptions are as follows:
Presentation Descrintion ,
A-scan Displays the digitized A-scan information within a gated sound path region along with probe position, skew angle, and screen pixel size.
TD-Time Displacement Displays each single A-scan over the scan line in a horizontal line with an amplitude related grey scale.
The display is available for each activated-angle and' probe.
Echo-Dynamic Displays the maximum signal in a specifically_ gated region over the full scan line (example O' to 360').
Echotomographic "A" Displays the complete UT-Data along one scan.line through a summation process.- For each probe location along the scan line the A-scan information is assigned to pixelp along with the sound path and compensation for examination skew angle. The presentation undergoes a 50-219
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+ cummati n pr: cess which. switch:s through thh diff:r:nt-skew angles and probe positions by summarizing the signal -
amplitudes'at each pixel location. The resultant ;
amplitudes are displayed in a grey scale mode.
This process of spatial summation produces a high potential for signa 1>to noise ratio eahancement.
Cchotomographic "B" This display uses the same process as the Echotomatraphic "A" display but accounts for search unit effective beam spread.
3D-Echotomographic Displays the echotomagraphic inforn.ation described above in a 3-dimensional model with amp; le representative'of vertical extent.
c-scan Displays data from a selected soundpath range assuming a constant skew angle.
Data evaluation was performed by personnel responsible for the examination system design and personnel who evaluated data from the examination technique qualifications. All personnel responsible for UT data acquisition and evaluation were also qualified and certified in accordance with the requirements of ASME Section XI.
Full examination coverage (no limitation) was achieved to examine'the interior surface of Zones 1, 2A, and 2B. Adjacent nozzles prevented scanning from 210' to 305' on nozzle A and 210' to 300* on nozzle C for the nozzle to shell weld.
Section XI examinations.
Laminar indications were detected in the vessel shell midwall region which exceeded recording criteria for angle beam scan interference but did.not exhibit a complete loss of back reflection, and therefore were acceptable per section XI. These small indications were not considered to have interfered with the angle beam examinations because there were no obvious changes in the interior surface noise pattern as displayed during data evaluation. No indications interpreted to be cracks were detected in Zones 1, 2A, or 28.
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