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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
[Table view] |
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Writer's Direct Dial Number:
December 22, 1989 C000-89-0806 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen
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Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 Integrated Schedule Project List Semi-Annual Update I
Pursue t r.o condition'2.C(10)'of Provisional Operating License DPR-16, GPU j Nucibar has implemented the Long Range Planning Program for OCNGS. .As required. l by Section V.A of the Plan, the following attachments are submitted to provide ~j
- the semi-aratual project list updates !
- 1. Attachment A contains a new project list of Category A, B and C-projects annotated by an asterisk (*) to identify new projects.
.11. Attachment a contains a summary of Category A and B projects which
.have been completed, deleted, deferred, changed in scope, or otherwise have had schedule changes with explanations as -j appropriate. 'Also contained are Category B and C budget activity i numbering changes. One Category C project has been deleted.
One potential Category A project schedule change is discussed in Attachment A u (see Note in Category A list). Six Category B schedule changes and one ,
I. deletion are discussed in Attachment B.
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Very truly yours,
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R.Lf.Long f DL l Vice Pres gent and Director '
Corporate Services RLL/PC/cb(C320379) l cc's on next page k l.
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. DR ADOCK0500g9 GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation
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ATTACHMENT A OYSTER-CREEK NUCLEAR GENERATING STATION INTEGRATED SCHEDULE !
SEMIANNUAL UPDATE-(DECEMBER, 1989) f
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OYS.TEQ CREEK P.Q O J E C T- LISTIN8 --
N CATEGORYL*A*' PROJECTS - .
SORT BY CATEGORY / CYCLE /BA STATUS'AS OF-090EC69-OBS BA DESCRIPTION ' CYCLE / ~ CLASSIFICATION NUMBER ' YEARS _ __------------------- _ _- - - - - - - - = - - - = = - -- -- - --
- - - - - = - - - .
1 402631 ALTERNATE ROD INJECTION MOD (ATWS) 12R- (see note) . NRR +
RB23 CR ".
INSTALL ALTERNATE ROD INJECTION SYSTEM. 10CFRSO.62 RULE.-
2 402ADH STATION BLACKOUT MODIFICATIONS 14R NRR -
YARD RB CR ENGINEER AND INSTALL RECOMMENDED PLANT MODS IN ACCORDANCE WITH 10CFRSO.63 .
NOTE: The planned alternate rod' insertion system modification was completed during the 12R outage. This item remains on the Category A list as a result of the November 11, 1988 NRC letter regarding the instrument.
component diversity issue. GPUN and the BWR Owners Group assessments find no technical merit in further modification. As such, GPUN is a participant in BWR Owners Group activities regarding the diversity.
Issue. CPUN activities related to project design, procurement, etc.
are on hold pending NRC/BWROG resolution. .As a result, further modification, if required, cannot be implemented any sooner than the 14R refueling outage. Final scheduling is ultimately dependent upon the timing of the resolution.
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CATEGORY 'B' PROJECTS * .
SORT BY CATEGORY / CYCLE /BA STATUS AS OF 21DEC89 X-OBS BA DESCRIPTION -CYCLE / CLASSIFICATION.
NUMBER ' YEARS 3 315302 SEP TOPIC III-l 12 NRR EVALUATE DESIGN OF SPECIFIC COMPONENTS AND INCORPORATE RESULTS-IN AN UPDATE.
TO THE FSAR. LAI 82251.06 4 402840 N2 WATER CNEMISTRY IMPLEMENTATION 12 NRR TB RB YARD FINAL TESTING AND IMPLEMENTATION.
5 402859 ESW FLOW INDICATION ( CONTROL ROOM ) 12 NRR RS23 INSTALL FLOW TRANSMITERS. CONOUIT AND CABLE. REG. GUIDE 1.97 REQ'TS.
6 408116 ACCESS CONTROL-CARO READERS / ALARMS 12 NRR -
CR CSR PROCUREMENT S INSTALLATION OF KEY CARD READER UNITS W/ ALARM FOR CONTROL EOOM AND CABLE SPREAD ROOM
! 7 402859 ESW FLOW INDICATION ( CONTROL ROOM ) 12U MRR CR INSTALL POWER SUPPLIES, SIGNAL CONDI TIONERS, AND INDICATORS IN C. R. PANEL IF/2F. REG GUIDE 1.97 REO*TS.
8 402872 TORUS O2 SAMPLE LINE ISOLATION 12U NRR CR RB23 l REWIRE FROM RELAYS IN TORUS O2 ANALYZER PANEL RUN CABLE FROM CONT.PART. MON. PANEL 1
TO TORUS O2 PANEL. MODIFY CONTROL SWITCN.
i 9 402879 RPS/ESG INSTRUMENT UPGRADE 12U NRR RBS! RB23 TB REPLACE APPROX 4 PRESS. SWITCNES.
OPERATIONAL / MAINTENANCE CONCERNS.
t 10 402927 UPGRADE P.S. TO ISO COND. VLVS, APP.-R 12U ' NRR RB51 RB75 CR INSTALL CONOUITS S CABLE. FIRE WRAP AS REQ'D. WIRING CHANGES-TO CR.10CFR50.48 APP. R REQ'TS. ( ISO CONDENSER).
- NRR 11 323613 CONT ISO VLV INST AIR SYSTEM INSP 13R RB CONTINUATION OF 12R WORK.. STROKE TEST ,
OF 40 AIR OPERATED VALVES S ACCUMULATORS NRC G.L. 88-14 , GPU LETTER 2-21-89.
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SORT BY CATEGORY / CYCLE /BA STATUS AS OF'21DEC99 M--
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OBS BA DESCRIPTION '
CYCLE /. : CLASSIFICATION ~
NUMBER YEARS
_-=_- - --
--_ - - =
12 328030 CNTRL RM NUMAN FACTORS DESGN REVIEW ISR .NRR CR REPAINT, REFURBISH E RELABEL CR PANELC 1R THRU 11R INCLUDING IXR S 9XR.
NUREG 0737 SUP 1.
13 328100 FWSCRD HOZZLE EXTERNAL UT INSP. 13R NRR DW UT INSPECTION OF THE CRD RETURN NOZZLE POSTPONED FROM 12R OUTAGE.NUREG 0619.
REMOVE INSULATION PREP SURFACES.
14 328204 RCS AUG - IGSCC INSPECTION 13R. NRR DW RB75 RB95 INSPECT PIPING WELDS.
1 15 328280 RCS STRESS IMPROVEMENT 13R NRR DW RB23 PERFORM STRESS IMPROVEMENT ON SELECTED STAIHLESS STEEL PIPING WELDS IN RCS SYS.
16 328284 CLOSURE HEAD WELDS REPAIR / REPLACEMENT 13R MRR RB 119 119 APPLY CRC TO 3 NOZZLE TO FLANGE WELDS ON RX VESSEL HEAD. REPAIR / REPLACE CLOSURE HEAD VENT / COOLING PIPE WELDS. G.L. 88-01 17 40281S CONTAINMENT PARTICULATE MONITOR -PNASE 2 13R NRR RB23 INSTALL A NEW CPM UNIT AND HAVE IT OPERATIONAL DURING CYCLE 13R.
SEP TOPIC V-5.
18 402879 RPS/ESG INSTRUMENT UPGRADE. 13R NRR RB51 RB23 TB REPLACE APPROX 25 PRESS. SWITCHES.
OPERATIONAL / MAINTENANCE CONCERNS.
19 402888 RPV CAPSULE 82 13R- NRR' 119' INSTALL CAPSULE s2 IN *R* VESSEL. -
HUREG 0822.
20 402900 ISO CONDENSER PIPING MOOS 13R ISM -
DW RB75 RB95 REPLACE ALL ISO'COND PIPING OUTSIDE THE DRYWELL MODIFY / REROUTE VENT PIPING AND REPLACE 6 10" CONT. ISOLATION. VALVES
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_ - .mO4 SORT BY CATEGORY / CYCLE /BA STATUS AS OF 21DEC891..
COS BA DESCRIPTION CYCLE / CLASSIFICATION ~
NUMBER YEARS-21 402938 RWCd PENETRATION PIPING REPLACEMENT ISR 'MRR DW RB REPLACE THE PIPING IN THE RWCU SYSTEM PENETRATIONS WITH SEAMLESS IGSCC ~
RESISTANT NG-316 S.S.-(G. L. 88-01) 22 408XX1 SECURITY VITAL AREA UPGRADE 14 NRR RB LOCK AND ALARM PERSONNEL DOOR ACCESS POINTS, ROOF HATCH S RR AIRLOCK 10CFR73.55 (C) (1) 23 328ABJ RCS AUG - IGSCC INSPECTION 14R NRR DW RB75 RB95 INSPECT PIPING WELDS PER HUREG 0313 REV 2.
24 328ABL RCS STRESS IMPROVEMENT 14R NRR DW RB23 PERFORM STRESS IMPROVEMENT ON SELECTED STAINLESS STEEL PIPING WELOS IN RCS SYSTEM.
25 402808 CONVERT COMPUTER RM TO GSSI/EMER DIR OFF 14R NRR CPR CONVERT COMPUTER ROOM INTO GSS OFFICE.
REQUIRES SECURITY PROOFING 26 402910 C R RECORDERS 14R NRR CR REMOVE E REPLACE APPROX. 15 DEFICIENT /
OBSOLETE RECORDERS - REDUCE OPERATOR ERROR. NUREG 0737 SUPP 1.
27 402936 CPM /DW ISO VALVE MOD TO PRECLUDE AUTO RE 14R NRR CR .
~
INSTALLATION OF POSITION SWITCHES ANO WIRING CHANGES FOR VALVES V-38-9,10.16 S
- 17. NUREG-0737 ITEM II.E.4.2 28 328ADA FW/CRD NOZZLE INSPECTION - 15R ISR NRR DW ,
NDE 4 FW & CRD RETURN NOZZLES.tEXTERNAL UT INSPECTION). NUREG 0619 REQ'TS.
29 328146 0.C. PROBABILISTIC RISK ASSESSMENT-IPE 87-92 NRR UPDATE EXISTING OC PRA. PERFORM AN INDIVIDUAL PLANT' EVALUATION. NRC G. L.
88-20. COMPLETE BY 9-1-92.
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OYS.TER CREEB PROJECT LICTINQ-CATEGORY 'S' PROJECTS STATUS AS OF 210EC89 SORT SY CATEGORY / CYCLE /BA - - . . _ . . . _ _ . . _ _ . . - - - -
_____________-----------..___________.-. CYCLE / ' CLASSIFICATION-OSS SA DESCRIPTION YEARS ' '
NUMSER ---- - - - - - - - - - = = . - _ - - - . . ~ . . . _ _ _ - - - - . . . - - - - - - - - - - - - - - . . . . . . _ _ _ . _ _ _
_...__ _. _ - ...== _____..__ .._. .------
87-93 MRR 33 328205 SOUG SUPPORT S PARTICIPATION - BWROG PARTICIPATION IN SEISWIC WALIFICATICW UTILITY GROUP FOR ECJIP SEISWIC 00A.
LIFICATION. UNRESOLVEE "4AFETY ISSUE.
87 93 MRR 31 328226 SOUG PROGRAM IeIPLEMENTATION ESTABLISH SEISMIC OUALIFICATION FOR OYSTER CREEK. SCOPE INCLUOES WALKDOWNS AND EVALUATIONS.
87/89- NOR 32 328092 WENOOR OOCuaIENT CONTROL PROGRAM REVW OF VENDOE MANUALS FOR EXISTNG EQUIP VERIFY APPLICABILITY TO SUPPORT MAINTMC ACTIVITIES LAI-83139.60
- -- ~. -- ..
.OYSTEQ' CDEEK P 0 0'J E C T- LISTINO
......-..--..- .......-- . - - - _ . ==
CATEGORY 'C' PROJECTS * .
SORT BY CATEGORY / CYCLE /BA STATUS AS OF 230EC99
--...----------...-------------------------..--- -- ....----- --.. . = - _ = - - - - - - - - - - - - . - - . . . . - - . . . - - - - - - - . - - - . . . - . . . . . . .
OBS BA DESCRIPTION CYCLE / CLASSIFICATION NUMBER YEARS
. . . . . - - - - - - . . . - . . - - - - - - - - - - - - - - - - . . . . . _ _ = - - - _ . = - -
. ------ =..-_-. __=___- =_= _...... .....----...............
- 12 33 323457 CNECK VALVE MONITOR /~MSPECT PROGRAM ORR TB DW RB IMPLEMENT ACCOUSTIC AND VIBRATION MONITORING OF 6 CHECK VALVES. IMPO-SOER 86-03.
34 328290 DILUTION PLANT AREA REPAIRS 12 MRC DIL 2 INSPECT S REPAIR OF CONCRETE.
REPLACE CORROOED CONDUITS.
35 402763 WATER CHEMISTRY MONITORING SYSTEM 12 MRC RBSI TBB INSTALL PIPING FOR ON-LINE MOP'ITOR OF DISSOLVED 02 5 CONDUCTIVITY FOR rw OISCHARGE.SUST OF RW SAGPPLNG STA 33 402823 GROUNDING & LIGHTNING PROTECTION 12 ISM YARD MB INSTALL GROUNDING PROTECTION FOR MAIN AND NORTH GUARD HOUSES,MAINT.
BLDGe, MATL WAREHOUSE.
37 408783 0.C. SPENT FUEL POOL WASTE DISPOSAL 12 IDE 119 REMOVE & DISPOSE OF IRRATIATED HARD-WARE IN THE SPENT FUEL POOL.
38 408788
- RX REFUELING PLATFORM REPLACEMENT 12 IOE 119 RB23 REMOVE EXISTING PLATFORM AND INSTALL AN UPGRADED BWR-6 PLATFORM 39 408799
- PLANT PAINTING PROGRAM 12 GWC ALL PREPARE SURFACES AND PAINT IDENTIFIED EQUIPMENT, PIPING. MALLS. FLOORS AND CEILINGS.
40 323594 LIFE OF SYSTEM MAINT PLAN 12-14 MRC ALL PEPFORM REVIEWS OF O.C. PLANT SYSTEMS.
IMPLEMENT MOOS / REPAIRS RESULTING FROM SYSTEM REVIEWS.
41 323457
-- - 4 OY STEO PQOJECT C Cf E E K L-I C T I N Q CATEGORY *C* PROJECTS - -
SORT BY CATEGORY / CYCLE /BA STATUS AS OF 210EC89 OSS BA DESCRIPTION CYCLE / CLASSIFICATION NUMBER YEARS
______..______...._ ....._--_..._____.__= _ - . - - ----- ------ ---
42 402823 GROUNDING S LIGHTNING PROTECTION 13 ISM ORW ADG TB RB INSTALL LIGHTNG PROT FOR OLD RW,AOG, TB,RB, MAINT. BLDG., NATL WAREHOUSE.
1 43 402898 REPL UPPER 78 8 OLD MACHINE SMOP ROOF 13 MRC YARD REPLACE THE UPPER TURBINE BUILDING ROOF, AND THE OLD MACHINE SHOP ROOF.
44 322x22
- CORRECTIVE MAINT .13R 13R REL R8 TB DW PRO *lTDE CONTRACTOR SUPPORT TO FUNCTIONAL MAINTENANCE EFFORT 45 322024 ORYWELL SCAFFOLDING $ INSULATION 13R GWC DW INSTALL SCAFFOLD IN DW TO SUPPORT ALL ACTIVITIES. RCMV E REINSTALL OW INSULA-TION. RENV SCAFFOLD.
46 323457 CHECK VALVE MONITOR /INSP. PROGRAN 13R OGR T8 DW R8 INSPECT 35 CHECK VALVES PER INPO-SOER 86-03.
ANOTHER 35. IMPO-SOER 86-03 47 323580 LP TUR8INE INSPECTION (~A- 5 ~8") 13R MRC T8 COMPLETE INTERNAL INSPECTION OF THE "A" E ~ B" LP TURBINES. REMOVE ROTORS, SANOBLAST,UT INSP $ REINSTALL ROTORS.
49 323592
- CONTAINMENT ISO VLV MAINT 13R NRR INSPECT E REPAIR AS NECESSARY CONTAINMT ISOLATION VALVES IDENTIFIED BY LLRT*S.
(APPROX. 14 VALVES) 49 323612 -
ASSESTOS ABATEMENT PROGRAM 13R 13R ORR C8 R8 REMOVAL / REPLACEMENT OF ASSESTOS LAGGING MATERIAL IN THE CONDENSER BAY,RWCU VALVE NEST SD 326201 OUTAGE ISI-13R I3R HRR OW R8 TB INSPECT HANGERS. PIPING WELOS &
COMPONENTS TO SATISFY SECTION XI REQUIREMENTS. 10 YR SYSTEM HYDRO.
N t
OYSTEQ CDEEK PQOJECT LICTINO CATEGORY
- SORT SY CATEGORY / CYCLE /8A STATUS AS OF 21DEC89
____. _____________ _________ ._________..______ .._______.._..__ .___..-- ______.. ____.- == .... ______......________...... .___
i' OSS BA DESCRIPTION CYCLE / -CLASSIFICATION NUMBER YEARS
... ___..____.. ...... ...._____________ ..=== .--.___-..___-........ _ ...___--- _ _ - - - - - - - . -
51 328203 RX INTERNAL INSPECTION 13R NOR 119'
, GPUN COMMITMENT. VISUAL INSPECT _
CLADDING, SUPPORT STRUCTURES, DRYER, SEPARATOR. UPPER GRID & BLADE HANDLES.
52 328230 RCS PIPING REPAIR CONTINGENCY 13R MRC DM RS CONTINGENCY FOR IGSCC FINDINGS.
53 328265 CNEM CLEAN FLUID SYSTEM 13R RAO RS23 DM RB51 PERFORM CNEMICAL DECON OF THE RECIRC AND CLEANUP SYSTEMS TO REDUCE RAD.
IATION LEVELS.
54 402888 OTHER OUTAGE RELATED ACTIVITIES 13R ALL ALL OUTAGE RELATED ACTIVITIES SUCN AS INSPECTION % REPAIRS, SURVEILLANCES, MINOR MODIFICATIONS, MOD SUPPORT, ETC.
53 402821 RX RECIRC PUMP S MOTOR VISRATION MONITRS 13R MRC DM R8 CR INSTALL VIBRATION MONITORING TRANSDUCERS AND SUPPORT EQUIP. FOR 3 RECIRC PUMPS 5 TRANS./ PUMP.
SS 402860 LP TURBINE BLADE REPLACEMENT 13R ISM TB REPLACEMENT OF LP ISTN STAGE BLADES ON A AND B LOM PRESSURE TURSINES.
57 402869 CABLE /CONOUIT REPAIR-CIRC MATER PUMP PIT ISR REL INT REPLACE ELECTRICAL CONDUITS, CABLE AND CONDUIT SUPPORTS AT THE INTAKE STRUCTURE 58 402901 FEEDMATER SYSTEM IMPROVEMENTS 13R REL TB RS INSTALL (2) MAIN BLOCK VALVES AND REPLACE PNEUMATIC LOCK.UP RELAYS.
PRE- OUTAGE MORK: INSTALL CONDUITS.
59 402915 REDUCE NUMBER MS SAFETY VALVES 13R RAD 4 DM i
PERMANENT REMOVAL OF (8) MSSV*S BASED ON 1 STUDY PERFORNMED. INSTALL BLIND FLANGES.
_ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ - - - _ _ _ - _ _ - - _ - . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . -. .. ~ . - . ...
-a
4 0YSTEO CDEEK PQOJECT LICTINC
- - - - - - - - - - - . . - - - - - - - . - - - - - - - . . . - - - - - - - .===---__
CATEGORY *C' PROJECTS '. .
SORT BY CATEGORY / CYCLE /BA STATUS AS OF 210EC99
...........---------...-....------------...- - _ _ _ - - - - - - - . . . . . . - - - - - - - - - - - - - - . - - - - - - = - . - - _ _ = ....--.-----............--
OSS BA DESCRIPTION CYCLE / CLASSIFICATION NUMBER YEARS
- - . . . . . . . - - - . - - - - - - - - - - - - - . . . . . . . . . . . . . . . . . . . - - - - . . - - - - - - - - = - - - - - . --
_==-- -- ....----_ ----- _ _ - - - - . . . . . . . . . . - - - - . . . . .
C@ 322X23 CORRECTIVE WAINT -14R 14R REL RB TB DW PROVIDE CONTRACTOR SUPPORT OF FUNCTIONAL MAINTENANCE EFFORT G1 322024 DRYWELL SCAFFOLDING S INSULATION 14R GWC DW INSTALL SCAFFOLD IN DW TO SUPPORT ALL ACTIVITIES. REMV E REINSTALL DW INSULA.
TION. RENV SCAFFOLD.
62 323F33 HP TURBINE INSPECTION 14R MRC TB COMPLETE INTERNAL INSPECT OF THE HP TURSINE. RENV ROTOR FROM CASING, SANDSLAST UT INSP S REINSTALL ROTOR.
43 326F01 OUTAGE ISI-14R 14R NRG DW RB TB INSPECT HANGERS, PIPING WELDS S COMPONENTS TO SATISFY SECTION XI REOUIREMENTS.
G4 328ASK RCS PIPING REPAIR CONTINGENCY 14R MRC DW CONTINGENCY FOR IGSCC FINDINGS.
REPAIR / REPLACE OF RECIRC S OTHER S.S. D/W PIFING SYSTEMS.
GS 328ABP RX INTERNAL INSPECTION 14R NRR 119' DW GPUN COMMITMENT. VISUAL INSP-CLAD, SUPP STRUCT. DRY SEP. UPPER GRIO eLADE HNDLS.VT CSS. ANNULUS PIPE ONLY.
GG 402AOI RECIRC PUMP SPEED CONTROL 14R MRC MGSR REPLACE EXISTING MG SETS WITH STATIC VARIABLE FREOUENCY DRIVES (SCRS)
G7 402AEH OC IA83 ANALOC CONVERSION 14R REL RB CR REPLACE S IA83 PRESS SWITCHES WITH ANALOG SYSTEM.
63 402AEP LP TURBINE (C) LAST STAGE BLADE INSTALL 14R REL.
TB REPLACE LAST STAGE BLADES IN LP TURBINE *C". BLADE FAILURE CONCERNS.
Ji
'OYSTCD CDEEK POOJECT L'ISTINO CATEGORY 'C' PROJECTS - .
SORT BY CATEGORY /CYCt.E/BA STATUS AS OF 21DEC89
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - - - - - - - - - - - = - ________.._____.__....________ .________________________._________....,___...
OSS BA DESCRIPTION CYCLE / CLASSIFICATION NUMBER YEARS 69 402CCC OTHER OUTAGE RELATED ACTIVITIES 14R ALL ALL OUTAGE RELATED ACTIVITIES SUCH AS INSPECTIONS. REPAIRS. SURVEILLANCES.
MINOR MODIFICATIONS, MOD SUPPORT. ETC.
70 402636 WIDE RANGE NEUTRON MONITORING 14R NRR DW13 INSTALL AN 8 CNANNEL WRNM SYSTEM TO REPLACE EXISTING SRM'S/IRM*S.
71 402736 DUAL VALVE INDICATION REMOVAL. PH I 14R ISM '
CR R8 REPLACE DOUBLE VALVE INDICATION LIGHTS IN C.R. PNLS 1F/2F. IIF. INSTAL NEW CABLING FROM R.B. TO C.R. .
72 402848 HP TURSINE DIAPHRAM MOD 14R REL TB REPL 12 DIAPHRAMS .REPL 5. MACHINE ROTOR SEALS TO REDUCE STEAM LEAKAGE. ANALYZE AND CHANGE NAMEPLATE.
73 402883 CONTAINMENT REVIEW $ UPGRADE 14R ISM R8 DW EVALUATE THE OC CONTAINMENT IN RELATION TO PROPOSED NRC SEVERE ACCIDENT CONT.
POLICY (CHERNOBYL). SCOPE TO BE DEFINED.
74 4014"1 FEEDWATER SYSTEM IMPROVEMENTS 14R REL CR NCSR REPLACE ANALOG CONTROL SYSTEM WITH OIGITAL.
75 402929 DIGITAL RECIRC FLOW CONTROL I4R 14R REL CR REPLACE GEMAC HARDWARE WITH DIGITAL SYSTEM.
76 402 ABO SOUG MOOS ISR NRR IMPLEMENT MOOS RESULTING FROM SOUG WALKDOWN IN 14R. SCOPE NOT YET DEFINED.
77 328182 AS-BUILT DRAWING PROGRAM 87 89 MRR DRAWING REVISIONS TO REFLECT AS SUILT/
AS FOUND CONDITIONS RESULTING FROM FCN'S.
OYSTED CDEEK PQ0 JECT LI@TINO -
CATEWORY 'C' PROJECTS " -'
SORT SY CATEGORY / CYCLE /BA STATUS AS OF 210EC89 -
OSS BA DESCRIPTION CYCLE / CLASSIFICATION NUMBER YEARS -
t 78 328259 CONFIGURATION MNGT - DRMG PROGRAM 87 90 ISM PHASE 1 OF 2 - COMPUTERIZED UPGRD OF OC DMNGS. CREATE STMDRS.PROCDRS, SAMPL DIGRMS 8 IDNFY END. USERS.
79 409057 SIMULATOR FACILITY 87-90 NRR CONSTRUCT A TMI-TYPE SIMULATOR BLDG AT O.C. FOR SIMULATOR AND SPT.
l 89 402011 OC REPLICA SIMULATOR 87-91 NRR l YARD 1 DESIGN, FABRICATE, INSTALL A SIMULATOR l DUPLICATING THE OC CONTROL RM FUNCTIONS l
FOR TRAINING PURPOSES.
81 328148 0.C. PLANT LIFE EXTENSION 87 93 REL DEVELOP 3-PNASE PLEX PLAN. PNASE 1 i
TO DETERMINE FEASIBILITY AND COST /
ANALYSIS OF # LEX.
82 402880 0.C. FUEL POOL CORE OFF LOAD (STUOY) 87-93 ORR RB ESTABLISH ADOITIONAL SPENT FUEL STORAGE CAPACITY FOR FULL CORE OFF LOAD BEYOND 1993 AT O.C.
83 328274 CONFIGURATION MGM*T -DESIGN BASES-1989 89 ISM DEVELOP O.C. SYSTEM DESIGN BASES. PERFORM SSFI*S AND IMPROVE DRAMING LEGIBILITY.
C4 328278 CONFIGURATION MGM'T-SSFI, 1990 90 ISM CONTINUATION OF DEVELOPING O.C. SYS1EM DESIGN BASES. PERFORM SAFETY SYSTEMS FUNCTIONAL INSPECTIONS, (SSFI).
85 402934
- CONF. MGu*T- DESIGN BASES - POST 89 90-92 ISM DEVELOPMENT OF OC SYSTEM DESIGN BASES.
PERFORM SSF*S AND IIOPROVE DRAMING LEGIBILITY.
t s 06 323508 INSERVICE TEST 10 YEAR UPDATE 90/91 NRR REVIEW AND UPDATE IST PROGRAM TO j MEET SECT XI AND IOCFR50.55.
_ _ - . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - - _ . . . . . . .- . _ -- -, x
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OYCTEQ CDEEK PQOJECT- L I S.T I N th
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- . = . - . -- -----------_ - . - -
CATEGORY
- SORT BY CATEGORY / CYCLE /BA STATUS'AS OF 210EC89 i
.--..------------- == -...- ----...........-.... ==---..... ..--...=_-__ -- -- ...- .... -...--............------....-..........
OSS BA DESCRIPTION CYCLE / CLASSIFICATION NUMBER YEARS 87 40991X REPLICA SIMULATOR UPGRADES 92-93 NOR UPGRADE THE SIMULATOR TO MATCH PLANT MOOS AS APPLICABLE.
88 328ADT POST 92 ACTIVITIES C-M DESIGN BASIS RECO 93-94 ISM O C SYSTEM DESIGN BASEC. PERFORM SSFI*S AND IMPROVE DRAWING LEGIBILITY.
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i ATTACEMENT B i
OYSTER CREEK NUCLEAR GENERATING STATION INTEGRATED 8CHEDULE SEMIANNUAL UPDATE-(DECEMBER, 1989)
CATEGORY "A" PROJECTS ADDITIONS: NONE DELETIONS: NONE SCHEDULE CHANGES: NONE OTHER CHANGES NONE l
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W CATEGORY 'B' PROJECTS 1
1
" Additions: As denoted by
- next to the project title.
Completions: None L Deletions: 3/h 40EYYY - Remove Density Compensation from Reactor P Water Level Recorder This project was identified as Item No. 1-1 in the l attachment to GPUN letter dated september 19, 1986 concerning the Detailed Control Room Design Review required by NUREG 0737, supplement 1. A recent l evaluation concluded that the removal of density l compensation from reactor water level control -)
instrumentation (GENAC) is unnecessary. This is due to i the fact that reactor protection water level instruments (Yarway) are density compensated for normal operating conditions and there is good agreement between the water level indicated by these instruments and the water level control instrumentation. In ;
addition, oyster Creek has not experienced unnecessary alarms or trips during startups or shutdowns due to the difference in density compensation between Yarway and GENAC instrumentation. l Schedule Changes: B/A-402815 - containment Particulate Monitor Phase 2 The installation of the CPM now requires a modification to the power supply circuitry. The installation of the new circuitry cannot be done while the plant is operating. Therefore, completion of the CPM project has been changed from cycle 12 to 13R.
c B/A-328030 - Control Room Human Factors Desian Review
! Cycle changed from 12U to 13R.
B/A-402910 - Control Room Recorders cycle change from 13R to 14R based on priority and available GPUN resources. This is the last phase of l the control room recorder replacement program which we have been implementing over the past several refueling outages.
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QATEGORY 'B' PROJECTS (continued)
.. B/A-328 ADA - FW/CRD Nossle Inspection cycle changed from 14R to 15R. As a result of previous inspection findings and fatigue stress analysis, GPUN believes that it is possible to_ extend the inspection intervals and utilise external UT as the primary-
, inspection method. Further details regarding inspection ;
intervals and scope will be provided in separate l
correspondence. j B/A 402808 - Sicma computer Room conversion to GSS Office i
The control Room Design Review identified certain design deficiencies which were to be resolved by this +
modification during refueling outage 13R. Subsequent to release of preliminary engineering, it was recently decided to increase staffing (additional on-shift SRos) in this facility. As a result of this scope change, available time and resources are insufficient to j implement this modification during the 13R refueling i outage. GPUN intends to complete the modification during refueling outage 14R.
B/A-328205 - SOUG Succort and Particination ongoing project, extended to 1993.
Other Changest Budaet Activity (B/A) Number Chances OBS.# NEW B/A NUMBER PREVIOUS B/A NUMBER 16 328284 328 ABO l B/A-328284 - RWCU PeAq_ Ration & CH Weld ReDairs The work scope under this activity has been divided into l
two activities. B/A 328284 covers closure head weld repairs, B/A 402938 covers RWCU penetration piping replacement. ;
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CATEGORY "C" PROJECTS I l
I Additions: As denoted by
- next to the project-title ;
I I
completions: None l J
Deletions: B/A-402845 - Under Vessel Cablinc Other Changes Budcat Activity (B/A) Number Chang.g.3 i OBS. # NEW B/A NUMBER PREVIOUS B/A NUMBER 34 328290 328ADM l 61 322024 322X21 B/A 328146 - Probabilistic Risk Analysis Update This activity has been moved from Category "C" to I Category "B".
i References GPUN Letter to NRC dated 10/31/89 addressing ;
IPE Generic Letter 88-20.
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