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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] |
Text
e ,
GPU Nuclear Corporation
' Nuclear =f;'er388 Forked River,New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
May 14, 1984 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Crutchfield:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Fire Protection -- Exemption Request By my letter dated Septerier 16, 1983, GPU Nuclear Corporation requested a schedule exemption from 10 CFR 50.48(c) of the regulations. As a result of discussions held with Mr. James Lombardo of your staff, we are submitting a specific listing of the modifications for which a schedule exemption is requested. h is list is to be used in conjunction with Enclosure No. 2 from my September 16, 1983 letter.
Very truly yours,,
Vice President and Director Oyster Creek PBF:SD: dam Enclosure cc: Dr. R omas E. Murley, Administrator
! Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731
- I 0405180026 840514
- gl/
l PDR ADOCK 05000219 PDR 'g F
l GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation
4
> s Oyster Creek Nuclear Generating Station Appendix R Schedule Relief by Fire Area
1.0 INTRODUCTION
~ GPU Nuclear-letter dated September 16, 1983 requested a schedule exemption from having to complete Appendix R modifications in tne time frame required by 10 CFR 50.48(c). The letter provided our justification and alternative measures being taken to insure that tne granting of the exemptions will not endanger life or property or the common defense and security of the public. Tnis suomittal specifically lists those modifications being exempted and snould be used in conjunction with the GPU Nuclear submittal of September 16, 1983.
2.0 MODIFICATIONS REQUIRING A SCHEDULE EXEMPTION (BY FIRE AREA / ZONE) 2.1 Fire Zone RB-FZ-1B 95' Elevation The rerouting of the following Isolation Condenser System circuits in conduit in this zone:
63-303 (ventline valve V-14-5 control) 63-303A (ventline valve V-14-20 control)11-769 (makeup line valve V-11-36 power) 21-1901 (makeup line valve V-ll-36 control)11-770 (makeup line valve V-ll-34 power) 1906 (makeup line valve V-ll-34 control) 82-37 (letel transmitter LT/IGO6A)
The installation of a new 125V DC MCC.
The ine allation of a new power feeder circuit to provide power to the new 125V DC MCC from the "B" train battery system.
Tne rerouting in conduit of the power, control and indication circuits 62-22, 154,63-617, 618, 619, 281 and 285 to "B" train steam and condensate line valves V-14-33 and 35.
The rerouting of Main Steam Isolation drain valves V-1-110 and 111, power and control circuits 62-51, 52, 395 and 396 in conduit.
2.2 Fire Zone RB-FZ-lc 75' Elevation Isolation Condenser System "B" train valve V-14-32, to be powered from a new "B" train MCC located in RB-FZ-6B.
The rerouting of Isolation Condenser System valve V-14-32, power and indication circuits for 12-404 and 22-265, within this zone in conduit.
. s Isolation Condenser System "A" train valve V-14-31, to be powered from MCC DC-2, not DC-1.
The rerouting of Isolation Condenser System valve V-14-31, power and control circuits for 62-21,63-280 and 63-284, witnin this zone in conduit.
The rerouting of circuits 62-22,63-281, 63-285 and 63-619 in conduit within this fire zone to support to repowering of V-14-33.
Isolation Condenser System "A" train valve V-14-34, to be powered from MCC DC-2, not DC-1.
Isolation Condenser System "B" train valve V-14-35, to be powered from the new 125V DC MCC located in RB-FZ-1B, not DC-2.
Tne rerouting of power and control circuits 62-19, 154 and 63-282, 278, 617.and 618 within this zone.
Tne rerouting of the following Isolation Condenser System circuits in conduit: (.
l 63-303 (ventline valve V-14-5 control) '
l' 63-303A (ventline valve V-14-20' control)11-769 (makeup line valve V-ll-36 power) 21-1901 (makeup line valve V-11-35 control) i 11-770 (makeup line valve V-11-34 power) l 21-1906 (makeup line valve V-11-34 control)
[ 82-37 (level transmitter LT/IG06A)
The routing in conduit of the new 125V DC Power Feeder Circuit for j the new MCC located in RB-FZ-1B.
[
The rerouting of the Main Steam Isolation drain valves V-1-110 and 111, power and control circuits 62-51, 52, 395 and 396, in conduit.
2.3 Fire Zone RB-FZ-lD 51' Elevation
'1be rerouting of Isolation Condenser System "B" train steamline valve V-14-32, power, control and indication circuits12-404, 22-622 and 625, in conduit and protected with a one-nuur fire carrier.
Tne rerouting of Isolation Condeser System "B" train steamline valve V-14-33, control circuits63-281 and 617, in conduit and protected witn a one-hour fire carrier.
Tne rerouting of Isolation Condenser System "A" train ventline valves V-14-1, 5, 19 and 20, circuits63-303, 303A, 459 and 459A in conduit and protectea with a one-hour fire barrier.
The rcrouting of Isolation Conden.cer System "A" and "B" train makeup line valves V-11-36 and 34, power and control circuits11-769 and 21-1901,11-770 and 21-1906, in conduit and protected with a one-hour fire barrier.
The rerouting of Isolation Condenser System "A" train level transmitter LT/IGO6A and B, circuit 82-37 and 38, in conduit and protected with a one-hour fire barrier.
The rerouting of Isolation Condenser System condensate valve V-14-37, power, control and indication circuits12-342, 22-392 and 22-404, in conduit and protected with a one-hour fire barrier.
The rerouting of the following Isolation Condenser System circuits to outside of this fire zone:
62-21 (steamline valve V-14-31 power)63-284 (steamline valve V-14-31 control) 62-22 (steamline valve V-14-33 power)63-285 (steamline valve V-14-33 control) 62-19 (condensate valve V-14-34 power)63-282 (condensate valve V-14-34 power)
The rerouting of the following Isolation Condenser System circuits in conduit and protected with a one-hour fire barrier:
63-280 (steamline valve V-14-31 control)63-278 (condensate valve V-14-34 control)
The rerouting of ADS System relief valve control and indication circuits82-275, 276, 278, 273, 274, 277, 311, 325, 537 and 538, in conduit and protected with a one-hour fire barrier.
The rerouting of CRD pump NC08B control circuit 22-104, in conduit.
The installation of a one-hour fire barrier on "B" train Reactcr Wide Range Fuel Zone Level circuits 82-592-2, 593-2, 594, 597 and 598.
The installation of a one-hour fire barrier around Reactor Wide Range Fuel Zone Level instruments PT-56, dpt-6, 7 and TE-59.
The rerouting of Neutrcn Monitoring - IRM circuits21-921 and 910, in conduit and protected with a one-hour fire barrier.
The rerouting of Reactor Building Closed Cooling Water (RBCCW) pump 1-2, power circuit 12-60, in conduit and protected with a one-hour fire barrier.
The installation of a partial fire barrier between RBCCW pumps 1 1 and 1-2.
The routing into this zone of Drywell Cooling Units RF-1-4 and 1-5 power and control circuits 12-73, 74,22-413, 414, 415 and 416, in conduit.
i The routing into this zone of RBCCW valvrs to drywell cooling units V-5-147, 143, 166, and 167, power and control circuits12-445, 446,
-443, 646 (647),22-768, 770, 769, 771, 393, 395, 1168 and 1169, in conduit and protected witn a one-nour fire barrier.
The routing in conduit of the new 125V DC Power Feeder Circuit for the new MCC located in RB-FZ-1B.
The rerouting of Main Steam Isolation arain valves V-1-110 and 111, power and control circuits 62-51, 52, 395 and 396, in conduit.
2.4 Fire Zone RB-FZ-1E 23' Elevation
'Ihe installation of a one-nour fire barrier on Scram Discharge Volume Level Switch RDO8E and its associated circuit 71-69.
- Tne installation of a one-hour fire barrier on CRD Hydraulic instrumentation DPIS/RD39, PI/PT-RD18, FT/FI-RD15, dpt/RDOS, RDO8A and PS-RD24.
The rerouting of the following CRD Hydraulic System circuits, in conduit and protected with a one-hour fire barrier:
i.21-234 (RDO8A Alarm)71-382 (dPIS/RD-39 Alarm)71-383 (PS/RD24 Alarm) 82-94 (PI/PT-RD18 Instrument) 82-96 (FT/FI-RD15 Instrument) 82-98 (dPI/RD29 Instrument)82-421 (PI/PT-RD18 Instrument)82-423 (FT/FI-RD15 Instrument)82-426 (dPI/RDO5 Instrument)
The changing of ' Isolation Condenser System "B" train valve V-14-37 power source from MCC 1AB2 to a new NCC located in FA-68.
The rerouting of Isolation Condenser System valve V-14-37, power and control circuits12-342 and 22-392, in conduit and protected with a one-hour fire barrier.
Tne installation of a one-nour fire barrier to penetration No. 18.
The rerouting of Isolation Condenser System valve V-14-37, control circuit 22-404, to outside this zone.
Tne rerouting of the following Isolation Condenser System circuits in conduit:
'11-769 (Makeup Line Valve V-11-36 power) 21-1901 (Makeup Line Valve V-11-36, control)63-280 (Steamline Valve V-14-31 control)63-278 (Condensate Line Valve V-14-34 control)63-303 (Ventline Valve V-14-5 control) 63-303A (Ventline Valve V-14-20 control)
. 82-37 (Level Transmitter LT/IGO6A) 3 t
- , _ _ _ _ .m_ , -, , , , , -
The rerouting of the following Isolation Condenser System circuits out of this fire zone:
12-404 (Steamline Valve V-14-32 power)22-622 (Steamline Valve V-14-32 control)22-625 (Steamline Valve V-14-32 indication) 62-19 (condensate-Valve V-14-34 power) 62-21 (Steamline Valve V-14-31 power) 62-22 (Steamline Valve V-14-33 power)63-281 (Steamline Valve V-14-33 indication)63-284 (Steamline Valve V-14-31 control)63-285 (Steamline Valve V-14-33 control)63-617 (Condensate Valve V-14-35 control)
The rerouting of ADS System relief valve power and control circuits63-537, 538, 539, 540, 595,82-275, 277, 311 and 537, in conduit and protected with a one-hour fire barrier.
The installation of a one-hour fire barrier for penetration Nos. 8, 10, 13, 18, 19 and 44.
We installation of a one-hour fire barrier for Reactor Wide Range Fuel Zone Level indication circuit 82-596 and associated penetration No. 57.
1 The installation of a one-hour fire barrier for the following Neutron Monitoring System - IRM circuits: l 84-127 (RH02G Detector Circuit)84-135 (RH03G Pre-Amp Circuit)84-280 (RHO 3G Pre-Amp Circuit)84-288 (RHO 3G Pre-Amp Circuit)
The installation of a one-hour fire barrier for penetration no. 22 and IRM detectors RHO 2G and RH03G.
The rerouting of IRM motor drive No. 7 power and control circuit 11-303 and 21-76, in conduit and protected with a one-hour barrier.
The installation of a one-hour fire barrier for penetration no. 54.
The rerouting out of this zone of IRM motor drive circuit 21-921.
The changing of the pvwer source for RBCCW to DW Cooling Isolation Valves V-5-147, 148, 166 and 167, from MCC 1821A and B to the new MCC in FA-6B.
We rerouting RBCCW to DW Cooling Isolation Valves V-5-147,148,166, and 167, power and control circuits, in conduit and protected with a one-hour fire barrier.
The installation of a one-hour fire barrier for penetration nos. 11 and 19.
Tne installation of a one-hour fire barrier for Main Steam Outocard Isolation Valve circuit 63-245 and associated penetration no. 12.
Tne rerouting out of this zone of Main Steam Drain Line outboard valves V-1-110 and 111, power and control circuits 62-51, 52,63-395 and 396.
Tne rerouting of Drywell Cooling Units RF-1-4 and 1-5, power and control circuits 12-73, 74,22-415 and 416, in conduit and protected with a one-hour fire barrier.
The rerouting of RBOCW valves V-S-147, 148', 166 and 167 power and control circuits12-443, 445, 446, 646 (647),22-395, 770, 771 and 1168, in condait and protected with a one-hour fire barrier.
The rerouting out of this zone of RBCCW valves V-5-147, 148, 166 and 167, control circuits22-393, 768 and 769 conduit.
The rerouting out of this zone of RBCCW pump 1-2 power circuit 12-60.
2.5 Fire Zone RB-FZ-1F -19' Elevation The rerouting of CRD Feed Pump NCO8A and B, power circuits 12-13 and 12-17, in conduit.
2.6 Fire Area TB-FA-3A 4160V Emergency Switchgear - 1C Tne rerouting out of this fire area of Drywell Cooling Units RF-1-4 and 1-5 interlock circuits22-839 and 1025.
2.7 Fire Zone TB-FZ-llB Turoine LuDe Oil Storage, Pumping and Purification Area The rerouting of Drywell Cooling Units RF-1-4 and 1-5 interlock circuits22-839 and 1025, in conduit and protected with a three-hour fire barrier.
The installation of a three-hour fire barrier for Service Water Pump 1-2, control circuit 22-87.
2.8 Fire Zone TB-FZ-llc Switchgear Room, West End of Turbine Building on Mezzanine Level Tne rerouting of Drywell Cooling Units RF-1-4 and 1-5 interlock circuits22-839 and 1025, in conduit and protected with a tnree-hour fire barrier.
The installation of a three-hour fire barrier for Service Water Pump 1-2, control circuit 22-87.
E 2.9 Fire Zona TB-FZ-llD ' Basement Floor, South End Ine rerouting of "B" train 4160V Emergency Switchgear ID, EDG2 and DG 2 Switengear operation, control and indication, and breaker control circuits 24-28, 32, 86-55, 56, 57, 58, 60, 61, 62, 63 and 65, in
' conduit and provided with a one-hour fire carrier.
Tne installation of a one-nour fire barrier for 4160V ES Switchgear 1D, USS 1B2 and 1B3, power feeder circuits 86-71, 14-25 and 28.
The rerouting of Drywell Cooling Units RF-1-4 and 1-5 interlock circuits22-839 and 1025, in conduit and protected with a one-hour fire barrier.
Tne rerouting of Service Water Pump 1-2 control circuit 22-87, in conduit and protected with a one-hour fire barrier.
2.10 Fire Zone TB-FZ-llE ~ Condenser BaJ
'Ine rerouting or Drywell Cooling Units RF-1-4 and 1-5 interlock circuits22-839 and 1025, in conduit and protected witn a one-hour fire barrier.
The rerouting of Service Water Pump 1-2 control circuit 22-87, in conduit and protected with a one-hour fire Darrier.
2.11 Fire Area OB-FA-6 480V Switcngear Room Tne modification to civide OB-FA-6 into two fire areas designated as OB-FA-6A and 6B.
l Tne installation of a.new MCC for 480V and 120VAC service, a new relay panel for EMRV operation, and a new 125VDC power panel, in
-OB-FA-6B.
The rerouting in conduit of tne following electrical system circuits out of OB-FA-6A to De totally within OS-FA-6B.
- 12--16 (Power feeder to MCC 1B21).12-417 (Power feeder to Battery Chargers MG Set B)12-447 (Power feeder to Battery Cnargers MG Set A)12-449 (Power to Auto Transfer Switen PS-1)12-452 (Power to MG Set 1-2 Control Cab) 62-94 (125V DC to USS 1B2)
-The installation of a one-hour fire barrier on the "A" train power feeder circuit from the 125V DC DCC whicn is routing through OB-FA-68.
Tne installation of the following new circuits in OB-FA-6B:
12-XXX _ (480V AC Power Feeder Circuit from USS 182 to a new MCC) 62-XXX (125V DC Power Feeder to a new relay panel) 62-XXX (125V DC Power Feeder to a new power panel)
The installation of a one-hour fire carrict on the following "A" train electrical power circuits:
12-600 (Vital MCC 1A2 to Battery Charger Cl)12-601 (Vital MCC 1A2 to Battery Charger C2)62-153 (125V DC Dist CTR C to MCC-DC-2)62-158 (125V DC Dist CTR C to USS 1A2)62-161 (125V DC Dist CTR C to Panel DC-F)62-172 (This conduit contains the "A" train Isolation Condenser circuit 62-169)62-173 (This conduit contains the "A" train Isolation -
Condenser circuit 62-169)
The rerouting of "A" train CRD pump NCO8A, power circuit 12-13, in conduit in OB-FA-6A.
The rerouting of "B" train CRD pump MCO88, power and control circuits 12-17 and 22-104, in conduit in OB-FA-6B.
The rerouting of "B" train Isolation Condenser steamline valve V-14-32, power and control circuits12-404, 22-622 and 625, in conduit for the new MCC contained in OB-FA-6B. 4 The rerouting to outside this fire area of "B" train Isolation Condenser valve V-14-35, control and indication circuit 63-617.
The rerouting of "B" train Isolation Condenser valve V-14-37 power indication and control circuits12-342, 22-392 and 404, from the new MCC located in OB-FA-6B in conduit.
The rerouting in conduit of Isolation Condenser valve V-11-34, power feeder circuit 11-770, from the new 120 V AC Instrument Panel located in the new OB-FA-6B.
The rerouting of Isolation Condenser valve V-ll-36, power feeder circuit 11-769, from existing instrument panel 4A in OB-FA-6A.
The rerouting of Isolation Condenser valve V-11-36, control circuit 21-1901, in conduit in OB-FA-6A.
Tne rerouting of Isolation Condenser valves V-14-5 and 20, control circuits63-303 and 303A, into OB-FA-6A.
The routing of Isolation Condenser steamline valve V-14-31, control circuit 63-280 into OB-FA-6A.
The routing of Level Transmitter circuit 82-37, into OB-FA-6A.
The rerouting in conduit of Drywell Cooling Units RF-1-4 and 1-5 power, control, and interlock circuits 12-73, 74,22-413, 414, 415, i 416, 839 and 1025, in fire area OB-FA-6B.
Tna rarouting'in conduit of 'ii' train RBCCW pump 1-2, power and control circuits 12-60 and 22-99, in fire area OB-FA-68.
The rerouting in conduit of RBCCW valves V-5-147, 148, 166 and 167, !
power and control circuits12-445, 446, 443, 646 (647),22-768, 770, 769, 771, 393, 395, 1168 and 1169, to the new MCC located in OB-FA-6B i and protected with a one-hour fire barrier. !
The rerouting of Neutron Monitoring circuits11-303, 21-76 and 921, ;
in conduit within OB-FA-68.
2.12 Fire Zone OB-FZ-8A MG Set Room
'Ihe installation for a one-hour fire barrier for the SDV level switch RDO8E, circuit 71-69. i The rerouting in conduit and protecting with a one-hour fire barrier ;
the following CRD Hydtaulic Instrument circuits:
71-382 (dPIS/RD39 Alarm)71-383 (PS/RD24 Alarm) t 82-94 (PI/PT-RD18 Instrument) 82-96 (FT/FI-RD15 Instrument) .
82-98 (dPI/RD29 Instru:aent) >
The rerouting out of this fire zone of the following Isolation Condenser valve circuits:
63-280 (Steamline Valve V-14-31 Control)63-281 (Steamline Valve V-14-33 Indication) !63-278 (Condensate Valve V-14-34 control) !
The rerouting of ADS relief valve indication circuits63-537, 538, t 539, 540 and 595, in conduit and protected with a one-hour fire barrier.
The installation of a one-hour fire barrier on Neutron Monitoring IRM instrument RHO 3G, pre-amp circuits84-135, 280 and 288.
2.13 Fire Zone OB-FZ-8C Batt.ery Room Tunnel and Electrical Tray Room -
35' Elevation The installation of a one-hour fire barrier on Scram Discharge Volume !
level switcn RDO8E, circuit 71-69. ;
Tne rerouting in conduit and protecting with a one-hour fire barrier the following CRD Hydraulic System instrument and alarm circuits:
71-382 (dPIS/RD39 Alarm)71-383 (PS/RD24 Alarm) 82-94 (PI/PT-RDl8 Instrument) 82-96 (FT/FI-RD15 Instrument) 82-98 (dPI/RD29 Instrument)
The rerouting out of this zone of CRD Pump "B" control circuit 22-104.
t
The rcrouting out of thic firo zon) of the following Isolation Condenser System valve circuits:
11-769 (Makeup Line Valve V-11-36 Power) I 11-770 (Makeup Line Valve V-ll-34 Power) "22-404 (Condensate Valve V-14-37 Control)22-622 (Steamline Valve V-14-32 Control)63-281 (Steamline Valve V-14-33 Indication)63-278 (Condensate Valve V-14-34 Indication)
The rerouting into this fire zone of the following Isolation t Condenser System valve circuits:
21-1901 (Makeup Line Valve V-11-36 Control)63-303 (Ventline Valve V-14-5 Control) 63-303A (Ventline Valve V-14-20 Control)63-280 (Steamline Valve V-14-31 Indication) 82-37 (Isolation Condenser "A" Level Transmitter Indication)
The rerouting of ADS System relief valve indication circuits63-537, 538, 539, 595 and 540, in conduit and protected with a one-hour fire i barrier.
The installation of a one-hour fire barrier on Neutron Monitoring IRM instrument RHO 3G, pre-amp circuits84-135, 280 and 288.
The rerouting in conduit of the following power circuits:
12-417 (Power Feeder to Battery Charger MG Set B) 62-XXX (Power Feeder to new 125V DC MCC in RB-FZ-1B) 6?-XXX (Power Feeder to new 125V DC Relay Panel in '
OB-FA-6B) 62-XXX (Power Feeder to new 125V DC Power Panel in OB-FA-6B) 62-94 (125V DC Dist. Ctr. B to USS 1B2)
The rerouting out of this zone of the following power circuits:
12-447 (Power Feeder to Battery Charger MG Set B) 449 (Power Feeder to Auto Transfer Switch, PS-1)12-452 (Power Feeder to MG Set 1-2 Control Cabinet)
The installation of a one-hour fire barrier on MSIV valves NSO3A and B control circuits 21-1533, 1534,63-242 and 246.
The routing in conduit of the following Main Steam Line circuits:
62-51 (MS Drain Line Valve V-1-110 Power) 62-52 (MS Drain Line Valve V-1-lll Power)62-395 (MS Drain Line Valve V-1-110 Coritrol)62-396 (MS Drain Line Valve V-1-lll Control)
L
The rcrouting out of this fire zone of RBCCW valves V-5-147, 148, 166
- and 167 control circuits 768, 769, 393 and 1169.
The rerouting out of this fire zone of RBCCW pump 1-2, control circuit 22-99.
The rerouting out of this fire zone of Drywell Cooling Units RF-1-4 and RF-1-5 fan control and interlock circuits22-413, 414,22-839 and 1025.
2.14 Fire Area OB-FA-9 Office Building The rerouting of ADS System relief valves NR108A and C control circuits82-274 and 84-278, in conduit, protected with a one-hour fire barrier and automatic fire detection.
The rerouting of the following power circuits:
12-417 (Power Feeder to Battery Charger MG Set B) 62-XXX (Power Feeder to new 125V DC MCC in RB-FZ-1B) 62-XXX (Power Feeder to new 125V DC Relay Panel in OB-FA-6B) 62-XXX (Power Feeder to new 125V DC Power Panel in OB-FA-68) 62-94 (125V DC Dist Ctr B to USS IB2)
The routing of the following Main Steam Drain Line Isolation Valves:
62-51 (MS Drain Line Valve V-1-110 Power) 62-52 (MS Drain Line Valve V-1-lll Power)62-395 (MS Drain Line Valve V-1-110 Control)62-396 (MS Drain Line Valve V-1-lll Control) i k
2.15 Fire Zone OB-FZ-10A Monitoring and Cnange Room l Tne rerouting of CRD pump NC08A, control circuit 22-104.
t The rerouting out of this fire zone of Isolation Condenser "A" train :
ventline valves V-14-5 and 20 control circuits63-303 and 303A.
The rerouting of Isolation Condenser "B" train makeup line valve V-11-34, power and control circuits11-770, in conduit.
The rerouting out of this fire zone of Isolation Condenser "A" train f makeup line valve V-11-36, power and control circuits11-769 and 21-1901.
The rerouting to out of this fire zone of Isolation Condenser "A" train level transmitter LT/IG06A circuit 82-37.
-Th2 rarouting in conduit of the following Isolation Condenser System circuits: _
12-342 (Condensate Valve V-14-37 Power)12-404 . (Steamline Valve V-14-32 Power)22-392 (Condensate Valve V-14-37 Indication)
'22-404- (Condensate Valve V-14-37 Control)22-622 (Steamline Valve V-14-32 Control)22-625. (Steamline Valve V-14-32 Indication) i Tne' rerouting of ADS System relief valves NR108A, C, D, and E, I control circuits82-276,_278, 325 and 274, in conduit and protected with a one-hour fire barrier. l The installation of a one-hour fire barrier on ADS System relief l valve NRlOBE control circuit 82-538.
The installation of a one-hour fire barrier on RX Wide Range Fuel Zone Invel' circuits 82-592-2, 593-2, 594, 597 and 598. ,
~
The rerouting of.a' Neutron Monitoring - IRM circuits21-921 and 910 in conduit and protected with a one-hour fire barrier. -
The routing in this fire zone of the following electrical system and containment system circuits:
12 (RBCCW Pump 1-2 power) _
12-73= (DW Cooling Unit RF-1-4 Power)
12-74 (DW Cooling Unit RF-1-5 Power)-
12-417- (Power to Battery Charger MG Set B)
- 12-443 (RBCCW Valve V-5-166 Power)_
- 12-445 (RBCCW Valve V-5-147 Power)
- 12-446 ,(RBCCW Valve V-5-148 Power) 12-447- (Power to Battery Charger MG Set B).12-449 (Power to Auto Transfer Switch PS-1)12-452 (Power to MG Set 1-2 Control Cabinet)
-*12-646(647) (RBCCW Valve V-5-167 Power) 99 (RBC W Pump 1-2 Control).
- 22-393 (RBCCW Valve V-5-166 Control)
'*22-395 (RBCCW Valve V-5-166 Control)22-413 .(DW Cooling Unit RF-1-4 Control)22-414 (DW Cooling Unit RF-1-5 Control)22-415 (DW Cooling Unit RF-1-4 Control)22-416 "(DW Cooling Unit RF-1-5 Control)
~*22-768 (RBCCW Valve V-5-147 Control)
,*22-769 (RBCCW Valve V-5-148 Control)
- 22-770 (RBCCW Valve V-5-147 Control)
- 22-771- (RBCCW Valve V-5-148 Control)
- 22-1168. (RBCCW Valve V-5-167 Control)
- 22-1169 (RBCW Valve-V-5-167 Control) 62-94 (Power Feeder 125VDC Dist. Ctr. B to USS 1B2)
62-XXX -(125V DC Power Feed to new relay panel) 62-XXX -(125V DC Power Feed to new power panel)
- These circuits will be protected with a one-hour fire narrier.
2.16 Fire Zone OB-FZ-10B Chemical Laboratory, Laundry and Instrument Shop The rerouting of RBCCW valves V-5-147, 148, 166 and 167, power and control circuits12-443, 445, 446, 646 (647),22-393, 395, 768, 769, 770, 771, 1168 and 1169, in conduit and protected with a one-hour
' fire barrier.
'Ibe rerouting in conduit of the following electrical system and containment system circuits:
60 (RBCCW Pump 1-2 Power) 12-73 (DW Cooling Unit RF-1-4 Power) 12-74 (DW Cooling Unit RF-1-5 Power) 417 (Power to Battery Charger MG Set B)12-449 (Power to Auto Transfer Switch PS-1) 12-452- (Power to MG Set 1-2 Control Cabinet) 22-99 (RBCCW Pump 1-2 Control)22-413 (DW Cooling Unit RF-1-4 Control)22-414 (DW Cooling Unit RF-1-5 Control)22-415 (DW Cooling Unit RF-1-4 Control)22-416 (DW Cooling Unit RF-1-5 Control) 62-94 (Power Feeder 125V DC Dist. Ctr. B to MSS 1B2)11-770 (Makeup Line Valve V-ll-34 Power)12-342 (Condensate Valve V-14-37 Power)12-404 (Steamline Valve V-14-32 Power)22-104 (CRD Pump NG088 Control)22-392 (condensate Valve V-14-37 Indication)22-404 (condensate Valve V-14-37 Control)22-622 (Steamline Valve V-14-32 Control)22-625 (Steamline Valve V-14-32 Indication) 62-XXX (125V DC Power Fced to new relay panel) 62-XXX- (125V DC Power Feed to new power panel)12-447 (Power to Battery Charger MG Set A)'21-921 (Neutron Monitoring Channel 17) 2.17 Fire Area OB-FA-22 Upper Cable Spreading and Mechanical Room The installation of'an automatic suppression and detection system.
The rerouting of RBCCW valves V-5-147,148,166 and 167 control circuits22-393, 768,'679 and 1169, in conduit and protected with a one-hour fire barrier.
The rerouting of the following "B" train circuits:
21-1906 (Makeup Line Valve V-11-34 control) 22-99 (RBCCW Pump 1-2 Control) u 22-104 (CRD Pump NC08B Control)22-404 (Condensate Valva V-14-37 Control) ,22-413 (DW Cooling Unit RF-1-4 Control) ,22-414 (DW Cooling Unit RF-1-5 Control)22-622 (Steamline Valve V-14-32 Control)63-281 (Steamline Valve V-11-33 Indication)63-617 (Condensate Valve V-14-35 Control)21-921 (Neutron Monitoring Channel 17)
- 2.18 Fire Area CW-FA-14 Circulating Water-Intake The installation of a one-hour fire barrier on AC and DC power circuits 14-28 and 62-93, from the underground cable ducts to the unit substation 1B3.
.The installation of a partial barrier between the USS 1A3 and 183 to create a dike for each individual substation to prevent a transformer i oil fire from spreading from one unit substation to another.
The installation of a one-hour fire barrier on Service Water pump #
.1-2, power and control circuits 12-78 and 22-87.
2.19 Fire Area DG-FA-15 No. 1 Emergency Diesel Generator Room ,
The installation of an external oil supply to each diesel generator day tank. L I
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