|
|---|
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] |
Text
. .
Jersey Central Power & Ught Company Madison Avenue at Punch Bowl Road Mornstown, New Jersey 07960 (201)455-8200 December 21, 1979 Mr. Thomas V. Wambach Systematic Evaluation Program Manager Division of Operating Reactors United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20555
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Topic 111-6 Seismic Design Considerations
Dear Mr. Wambach:
The purpose of this letter is to forward additional seismic design documentation requested by the U.S. NRC's Seismic Review Team (SRT) and to advise you of the status of Jersey Central Power & Light Company's (JCP&L) actions in several areas discussed during the July 17 and 18,1979 seismic review meeting at 0yster Creek.
The status of our responses to requests for Oyster Creek seismic design information is summarized in Attachment A.
If there are any additional questions regarding the infor-mation provided, please call Jim Knubel, Supervisor-Nuclear Safety &
Licensing Section, (201) 455-8753.
Very truly yours, M/,
Ivan R. Finfr k, .
Vice President Attachments -
7
/olf Jf b/
Jersey Central Power & Ught Company is a Me 8001210 r of the General Pu0hc Utit:es System
DOCKET N0. 50-219 ATTACHMENT A OYSTER CREEK NUCLEAR GENERATING STATION SEP TOPIC III-6 SEISMIC DESIGN CONSIDERATIONS
'1 7'74 @ 8 ' December, 1979
A. Information Requested by NRC Letter dated September 4, 1979 Attachment 6 to NRC (T.V. Wambach) letter dated September 4, 1979 to JCP&L requested the following information. The status of JCP&L's response to each request is also given.
- 1. Item A-1 Information requested: " Shear areas of original reactor building and turbine building models".
Response: This information was transmitted to the NRC (T.V. Wambach) by JCP&L (Y. Nagai) letter dated November 27, 1979.
- 2. Item A-2 Information requested: " Structural drawings (including foundation details) in sufficient detail to permit verification analyses of the following buildings:
- Reactor building
- Turbine building
- Office building (portion founded on reactor building)
- Ventilation stack Response: These drawings were transmitted directly to Lawrence Livermore Laboratory at the request of the NRC by Burns and Roe in August, 1979.
Additional structural drawings were transmitted by JCP&L letter dated November 27, 1979.
- 3. Item A-3 Information requested: " Reinforcement details of block wall in contain-ment spray corner room (near stairway)".
Response: Reinforcement details for the block walls are shown in Burns and Roe drawings 4505-4 and 4514-3, attached.
- 4. Item A-4 Information requested: " Confirmation of soils design information; shear wave velocity or shear moduli, poissons ratio, bearing capacity".
Response: This information was transmitted to the NRC (T.V. Wambach) by MPR letter dated September 14, 1979.
- 5. Item B-1 Information requested: " Emergency condenser - original Forster Wheeler computations including arrangement drawings showing support and anchorage details".
Response: Available desin drawings and calculations were transmitted as Enclosure 2 to JCP&L (T. Tipton) letter dated August 24, 1979, to the NRC (T. Wambach).
4....
- 6. Item B-2 Information requested: " Reactor pressure vessel stress report - Com-bustion Engineering".
Response: The Oyster Creek reactor vessel s ess report, including drawings, were transmitted as Enclosure 5 .o JCP&L (T. Tipton) letter dated August 24, to the NRC (T.V. Wambach).
- 7. Item B-3 Information requested: " Reactor vessel supports - Burns and Roe com-putations (1965)".
Response: Enclosure 6 to JCP&L's letter of August 24, 1979 included design calculations for the vessel ring girder and horizontal stabil-izer supports. Additional vessel support drawings and calculations are forwarded herewith in Enclosure 1.
- 8. Item B-4 I n f o rma ti on requested: " Stabilizer - analytical techniques used to evaluate the stabilizer and overall RPV support system".
Response: The information requested is provided in Enclosure 1.
Additional data on the support truss between the biological shield and reactor building is contained in Reference 18 of " Summary of Seismic Design Information, Oyster Creek Nuclear Generating Station" which was forwarded to the NRC (D.L. Ziemann) by JCP&L (I.R. Finfrock) letter dated July 9, 1979.
- 9. Item B-5 Information requested: " Heat exchangers - containment spray and shut-down (arrangement drawings including support and anchorage details or qualification data)".
Response: Design calculations for the containment spray heat exchangers were transmitted as Enclosure 7 to our August 24, 1979 letter. The shutdown cooling heat exchanger is shown in Southwestern Engineering Company drawing 77367. Foundation details for the shutdown cooling heat exchanger are shown on Burns and Roe drawing 4074-4. These drawings are attached.
- 10. Item B-6 Information requested: " Pumps - emergency service water and recircula-tion (arrangement drawings including support and anchorage details and/or qualification test data)".
Response: Information on the emergency service water pumps was pro-vided as Enclosure 8 to our August 24, 1979 letter. R e~c i r c u l a t i o n pump support drawings and other information were provided ,with our August 24, 1979 letter.
.1 - .
- 11. Item B-7 Information requested: " Tanks - condensate storage and 7 day fuel oil (arrangement drawings including support and anchorage details and/or original seismic design computations)".
Response: Information on the condensate tank was provided as Enclosure 9 to our letter of August 24, 1979. Additional drawings of the con-densate storage tank were transmitted by JCP&L letter dated November 27, 1979. Design calculations for the emergency diesel fuel oil storage tank are attached as Enc losure 2.
- 12. Item B-8 Information requested: " Diesel generator support - any original com-putations that evaluate the sliding stability of the diesel generator unit and the effect of relative displacement of attached lines or information that would permit such an evaluation".
Response: Calculations on the stability of the diesel generator and switchgear are attached as Enclosure 3.
- 13. Item B-9 Information requested: " Motor. operated valves - effect of eccentric mass on 1" to 4" diameter lines".
Response: We have identified two applications of valves with operators in safety related piping systems less than 4" in size. These are the 2" motor-operated recirc bypass valves and approximately 1-1/2" air-operated valve in the CR0 hydraulic system. We are obtaining specific weight and dimensional data on the heavier of these valves and will transmit analyses of the effect of the eccentric mass on piping stresses as soon as they are available.
- 14. Item B-10 Information requested: " Control rod drive hydraulic control units -
- a. computations addressing the lateral support of tubing
- b. anchorage criteria for the CRD modules including supoorting computations and field verification that the modules are supported in accordance with the design criteria".
Response: Enclosure 4, attached, contains seismic qualification data for the CRD hydraulic control units and original seismic analyses for the attached 3/4- and 1-inch piping. Information on the anchorage (holddown) of the CRD control units is being obtained and is discussed in more detail in paragraph B.5, below.
O
- 15. Item B-ll Information requested: "M-G set in cable spreading room - arrangement drawings including support and anchorage details, weights and/or computations, qualification data".
Response: Available test data and drawings are presented in Enclosure 5.
- 16. Item B-12 Information requested: " Piping isometric drawings including support locations, support stiffnesses (or necessary drawings of supports to enable a determination of support stiffnesses), valve locations, valve masses and center of gravity and other pertinent details needed to independently verify and audit the seismic capability of the following piping systems:
- a. Isolation condenser piping - from containment penetration to the condenser
- b. 2" control rod drive return piping (50')"
Response: MPR letter dated October 2, 1979, to the NRC (T.V. Wambach) transmitted available piping layout drawings, isometrics, support design drawings and piping specifications for four systems inside the containment: main steam, feedwater, 1 solation condenser and CRD hydraulic return. Additional information on isolation condenser and 2" CRD pip-ing outside co ntainment is given in Enclosure 10.
- 17. Item B-13 Information requested: "RK01 - 5 instrument racks - Blume analysis".
Response: Seismic analyses of instrument racks RK01 and RK05 were transmitted as Enclosure 4 of our August C4, 1979 l etter. Additional information on the anchorage of these racks is being obtained and is discussed in Paragraph B.5 below.
- 18. Item B-14 Information requested: "4160-480 transformer - arrangement drawings including weights, center of gravity and tie down details or qualifica-tion test data".
Response: Anchorage data for this and other electrical equipment is discussed in paragraph B.5, below.
- 19. Item B-15 Information requested: " Ins trumen tation test reports - GE".
Response: General Electric NID Standards and Qualification Engineering Qualification Report Memoranda No. 1, Rev. 1, dated January 26, 1971; Memorandum No. 2, dated September 1970 and Supplement to Memorandum No. 2 dated Marcy 1971 are presented in Enclosure 6. These qualifica-tion reports were prepared for the Dresden 2 nuclear. station but are applicable in part to the equipment installed at 0yster Creek.
- 19. (continued)
An engineering evaluation of the applicability of these reports to the specific equipment installed at 0yster Creek is being made by General Electric and Jersey Central. The results of this evaluation will be transmitted to the NRC as soon as they are available.
- 20. Item B-16 Information requested: " Battery racks - computations supporting evalua-tion of new racks and qualification testing data for jars when avail-able".
Response: Information on the battery racks was provided as Enclosure 3 to our August 24, 1979 letter.
- 21. Item B-17 I nf orma ti on requested: " Cable trays including lateral supports -
original supporting criteria and/or later qualification testing data".
Response: As discussed during the July 17 and 18, 1979 meeting at Oyster Creek, tests on cable trays and supports were conducted by several utilities and an architect engineering firm. We expect these data to have applicability to Oyster Creek. We have recently obtained the data and will transmit them to you following our review.
- 22. Item B-18 Information requested: " Crane over service water pumps - provisions for assuring that crane will not overturn and damage the emergency service water pumps and/or supporting evaluations".
Response: An evaluation has been made of the stability of the bridge crane over the intake structure and emergency service water pumps.
This evaluation is attached as Enclosure 7 and shows that the crane will not fall on the emergency service water pumps during an earth-quake.
- 23. Item B-19 Information requested: " Emergency Service Water - Any additional existing information that can be provided to address the state of stress at entry points into the buildings or other discontinuity points".
Response: The piping referred to above is the buried portion of the emergency service water piping between the intake structure and the turbine building. Because of the various changes in analytical methods for buried piping since this piping was analyzed, we are in the process of re-analyzing the buried emergency service water piping.
This analysis is being performed by URS/J.A. Blume and Associates and is expected to be complete within the next month. A copy will be forwarded for your information at that time.
- 117('133
B. Information Discussed During July 17 & 18, 1979 Meeting at Oyster Creek During the July 17 and 18, 1979 seismic review meeting at Oyster Creek, a number of items not covered in your letter of Sep-tember 4, B79 were discussed, The status of these action items are as follows:
- 1. Intake structure analysis - Additional seismic analyses of the intake structure were submitted in Enclosure 1 to our August 24, 1978 letter to the NRC (T.V. Wambach).
- 2. Office building evaluation - An evaluation of the portion of the office building which contains the Station A and B batteries and cable tunnel is attached as Enclosure 8.
- 3. Drywell supports - The SRT requested information on the design of the lateral supports for the drywell. Chicago Bridge and Iron Company drawings 9-0971-36 and -37 are attached and show the drywell stabilizer assembly details.
- 4. Supports for isolated phase bus ducts - An analysis has been performed to determine whether the isolated phase bus duct supports are adequate to prevent the ducts from falling on or near the 4160 Volt switchgear during the design earthquake. This analysis is attached as Enclosure 9 and indicates that some additional bracing of these Class II duct supports is needed to upgrade them to Class I seismic requirements. We plan to add this bracing during the next refueling outage.
- 5. Equipment holddown and support - During the July 17 and 18, 1979 meeting at Oyster Creek, JCP&L representatives advised the NRC of actions completed or underway to evaluate and improve, where needed, the anchorage and support of selected equipment. This effort is still in progress. We will advise you of the results of our evaluations as soon as they are complete.
~
hI77tII4'