Forwards Schedules & Resolutions for SEP Topics II-5.B,V-5, VIII-3.B,V-12.A,XV-16,XV-18,III-4.A,VI-7.A.3,VI-10.A, II-3.B,II-3.B.1,II-3.C,III-1,III-2,III-3.A,III-3.C, III-4.A,III-4.B,III-4.D,III-5.A,III-5.B & III-6ML20067B616 |
Person / Time |
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Site: |
Oyster Creek |
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Issue date: |
11/29/1982 |
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From: |
Phyllis Clark GENERAL PUBLIC UTILITIES CORP. |
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To: |
Crutchfield D Office of Nuclear Reactor Regulation |
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References |
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RTR-NUREG-0822, RTR-NUREG-822, TASK-***, TASK-RR NUDOCS 8212060247 |
Download: ML20067B616 (17) |
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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
,
GPU Nuclear NUh Q[ 100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
November 29, 1982 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 SEP Integrated Assessment Our recent letter dated November 16, 1982, provided our schedules for equipment modifications and additions resulting f rom SEP integrated assessment. The letter also provided GPU Nuclear Corporation (GPUNC) positions concerning resolutions of some of the SEP topics proposed by the NRC staff with which we disagreed.
Subsequently, the NRC staff requested a meeting for further discussion of the schedules and topic resolutions in order to reach agreement between GPUNC and the NRC staf f. That meeting was held on November 18, 1982 and we were able to reach ageement on all items.
ATTACHMENT I to this letter lists schedule and resolution agreed at our meeting for each of the topics.
o37 8212060247 821129 PDR ADOCK 05000219 P PDR GPU Nuclear is a part of the General Public Utihties System
Mr. D. M. Crutchfield .
Page 2 ,
November 29, 1982 We are also transmitting the revised integrate.J assessment summary table (Table 4.1 of draft NUREG 0822) as ATTACHMENT II. The revised table reflects the agreements reached during our November 18, 1982, meeting with the NRC staff. The revised portions of the table are indicated by double asterisks (**).
Very truly yours,
, ok P. R. Clark Executive Vice President bif Attachments cc: Ronald C. Haynes, Administrator Region 1 U. S. Nuclear Regulatory Comnission 631 Park Avenue King of Prussia, NJ 19406 i NRC Resident Inspector j Oyster Creek Nuclear Generating Station
! Forked River, NJ 08731 i
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ATTACHMENT I SEP TOPIC SCHEDULES AND RESOLUTIONS AGREED ON NOVEMBER 18,1982 BETWEEN GPUNC AND THE NRC STAFF TOPIC NO. III-5E Pipe Break Outside Containment 4
As stated in our November 16, 1982 letter, GPUNC will prepare and
! transmit a report to the NRC by February 28, 1983, which predicts crack growth rate in the Oyser Creek isolation condenser lines. Based on our findings GPUNC will propose .an appropriate leakage detection method with adequate sensitivity. Our preliminary evaluation indicates the extremely j slow growth rate will allow the use of a crack with suf ficiently large
- leak rate for visual and audio detection TOPIC NO. V-5 Reactor Coolant Pressure Boundary Leakage Detection CPUNC will perform a '_' leak before break" analysis for the most j limiting piping to justify the sensitivity of the current leak detection systems available in the containment sump. Results of the analysis will be transmitted .to the NRC by June 30, 1983. GPUNC will also propose Technical Specification change before Cycle 10 startup to include operability requirement of the leakage detection systems inside containment. GPUNC will prepare action statements in Technical Specifications.
TOPIC NO. VIII-3B DC Power System Bus Voltage Monitoring and Annunciation Our November 16, 1982 letter stated that the battery status alarms will be installed during Cycle 11 refueling outage due to the number of modifications already planned in the control room during the l forthcoming (Cycle 10) outage. However, the NRC ' staff requested an intermediate resolution of this issue since PRA performed by the NRC consultant rated this issue of high risk importance. GPUNC will provide an intermediate resolution which consists of periodic inspections of the i
safety related battery systems such as verification of battery breaker position, battery current, charger current, etc. Plant inspection procedure will be revised to include the periodic inspection of the battery systems before Cycle 10 starup. The intermediate resolution will be in effect until the installation of the battery status alarms during Cycle 11 outage.
TOPIC NO. V-12A Water Purity of BWR Primary Coolant Our November 16 1982 letter to the NRC stated that GPUNC will revise Oyster Creek Technical Specifications after examining our Cycle 10 experience. However, during our meeting on November 18, 1982, the NRC staf f requested GPUNC to revise Technical Specifications before Cycle 10 startup. GPUNC agreed to revise Technical Specifications prior to Cycle
10 startup incorporating Reg. Guide 1.56 limits for conductivity and chloride concentration. Action statements will be proposed by GPUNC.
The NRC staff concluded in the meeting that an issuance of a special report rather than an LER by GPUNC would be acceptable following a violation of the Reg. Guide limit for conductivity. The existing limit for conductivity will still remain as an upper bound for the plant operation.
TOPIC NO. XV-16, XV-18 Radiological Consequences of Failure of Small Lines Carrying Primary Coolant and Main Steam Lines Outside Containment GPUNC will revise Oyster Creek Technical Specification adopting General Electric Standard Technical Specifications for iodine limits before Cycle 10 startup. GPUNC will propose action statements.
TOPIC NO. III-4A Tornado Missiles GPUNC will provide a portable pump and hoses for shutdown heat removal during a postulated tornado missile incident. The pump and hoses will be housed in the area of Reactor Building which is protected from the tornado missiles and flooding (the pump will also be used as a redundant pump to the existing condensate transfer pump during a postulated maximum hurricane flood -See SEP Topic II-3B in ATTACHMENT II). Since placing of the pump and hoses is not outage related, GPUNC will complete the project by the end of 1984. The project also include revising the plant emergency procedure for tornado incidents.
TOPIC NO. VI-7.A.3 Emergency Core Cooling System Actuation System TOPIC NO. VI-10A Testing of Reactor Trip System and ESF, Including Response Time Testing Before Cycle 10 startup GPUNC will revise Technical l Specifications to include the emergency condenser logic testing and the i
reactor trip system testing in accordance with the instruction provided I
in our current surveillance procedures for both systems.
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ATTACilMENT II yvi lohle 4.1 Int egra ted 4>>ev.ni.-ut simni.o y n Tech. Spec.
g SEP modifications so Topic Sect,on i Comple-
- required from llat ti a t Litensee tion No. 11 o . Title SEP review requirements PRA en agree > date rating S 11-3.8, 4.1(1) Condensate Transfer P4mip 11-3.8.1, Power flo See SEP Topic No. III-4A** yes* 12/84** -
Section No. 4.6.4 I l- 3. C 4.l(2) Flooding' Level Procedures flo None - - -
4.1(3) Canal Water tevel 11 o Install antumatic water Instrumentation Ye> Cycle XI -
level instramu nt.stion in the intate canal.
4.1(4) Isolation Condenser No Demonstrate minimum quantity Flooding Yes Cycle X -
of water maintained in condensate storage t .sk
- ,s sufficient for long-term
- cooling and inclinie minimum m
inventory in plant procedures.
4.l(S) Low Water Level Shutdown No lione - - '
4.1(6) llurricane Flooding of flo Revise escrgency procedures Pumps Yes Cycle X -
to ident ily alternate water sources anel Ilow paths shoulil Icw elevation pumps be -
f luo.leil.
4.1(7) Flooding Elevation tio Evalisat.t e onseiginences of Yes 2/83** -
ofigas tenilding flooding and confirm all other entrance
. levels .ibuve 23.S IL.
<ee footnotes at end of table.
g
wvwetuunnfb
@m lable 4;l (Continued) s n _ _ -
Tech. Spec.
2 SEP modifications
- Topic Section Comple-required from Backlit No. No. Title Licensee Lion g
T SEP review require:aents agrees date PRA rating Il-3.C 4.1(8) Groundwater Elevation No See item 4.4(2). .
4.1(9) Roof Drains No Install scarppers in the Yes Cycle X -
reactor building and turbine +6 mo.
building par.spet s.
111-1 4.2 Classification of Struc- No tures, Compon1nts, and Evaluate design of specified Yes 10 CFR -
Systems compontuts on a sampling 50.71 basis, opgrade if necessary, (e)(3)(ii) and din.ument classification in FSAH update.
, 111-2 4.3.1 Reactor Building Steel No a
Structure Above the Analyse and identify any Yes 12/82** -
0 Operating Floor needed upgrading of reactor building upper steel structure for wind loads.
4.3.2 Ventilation Stack No Analyte and identify any Yes 12/82** _
needed ig. grading of ventila-tion start for wind loads.
4.3.3 Effects of Failure of No Nonseismic Category I Analyic turbine building Yes 6/83 -
Structures capacity for wind loads, evaluate consequences of failure end idiniify any needed upgrading.
4.3.4 Components Not Enclosed No None -
in Qualified Structures - -
4.3.5 . Exterior Hasonry Walls No fione - - -
See footnotes at end of table.
a
ATTACWfENT II y lable 4.1 (Centinued) n Tech. Spec.
-s SEP modifications Comple-E Topic Section required from Backtit
- No. No. Title Licensee Lion PRA vi SEP review requirements agrees date rating 5 III-2 4.3.6 Roof Decks No Provide analysis or reactor 12/82** -
Yes buildinig roof.
- Analyze capacity of turbine Yes 6/83 -
building; s ont to withstand wind lo.nis.
4.3.7 Intake Structure, Oil N(, Analyte tapacity to with- Yes -
,, lanks, and Diesel Gener- stand winni and tornado 12/82**
ator Building loads arid upstratie, if necessary.
+ 4.3.8 toad Combinations No Submit analyses demon- yes * ,6/83** ,
strat feig; wisi(I goa,l> were 8 properly combined with other specified loads.
4.3.9 Soil and foundation No tione - - -
Capacities III-3.A 4.4(1) lifdrostatic Loads No None - - -
(Combination) 4.4(2) liydrostatic Loads No Evaltiati short ilureition Yes 4/83 -
(Short-Duration) hydrostatic loacts on and floatat ioni giotential of structures essent.ial to sale shuliluun in rauijunction with I lui..lis.;; emerijency procedin c3 (liem 4.l(6)).
4.4(3) Below-Grade Penetration No ll uic - - -
Flooding r
$, latile 4.1 (Continued) o e
@ Tech. Spec.
n SEP s Topic Section modificalions required from Dacilit Comple-
$ No. No. Title Licensee Lion PRA x SEP review iequircuents agrees d.ite rating
$o III-3.C 4.5.1 Intake and Discharge Canals No Itune - - -
4.5.2 Intake Structure Trash No Racks and Intake Screens formalize existing inspec- Yes* Cycle X** -
tion pr.n.tice as p.u t of shifL tin nuver or inservice
- inspet.t. ion (ISI) procedures nutil w. ster level moslifi- '
cdtiola ib Complete (ltene 4.1(3)).
4.5.3 Roof Drains No See item 4.l(2) - - -
4.5.4 Inspection Program No fievelop .nnt implem.:nt a Yes Cycle X -
, formal inspection program s
for water control structures.
@ III-4.A 4.6.1 Emergency Diesel No Analyze potential for and Yes 3/83 Generators and fuel co, sequence > of tornado-Oil Day Tank siissile damage of the diesel generator insilding.
4.6.2 Hechanical Equipment No Access Area Evaluate the potential for Yes I/83 -
and consequences of tornado-missile impact in the reactor fusilding access alour region and ident ily any ni<essary correct ive attinns.
4.6.3 Control Room, Reactor No None Building, and Turbine - - -
Building Heating,
.VentilatinD, and Air Conditioning (HVAC)
Systesis See footnotes at end of table. '
D
n - - _. _. ____
~ -
ATTACHME.Vr II o
m lable 4.1 (Continuseil)
W
-s n _ . . . . .
lech. Spec.
2 8*
SEP modificalions
- Topic Section Comple-required from BackIit
- No. No. Title SEP review I.icensee tion PRA rn requirements agrees d.ste rating T
III-4.A 4.6.4 Condensate Storage Tank, No Provide protection tcr Yes** .12/84** -
Torus Water Storage Tank, suffic.ient systems and and Service Water and compon. nt > to ensure a safe Emergency Service Water Pumps shutdown in the event of damaije tioin torn.iilo missiles. 6 flooding III-4.B 4. 7 Turbine Missiles No inspee.t turbine .n d propose Yes 12/84 -
inspection frequency based on results.
Justif y nionitorin!; program Yes 2/83* -
- for m.iin ste.im anit reheat e , control valves.
o III-4.D 4.8.1 Truck Explosion No tione - - -
4.8.2 Aircraf t llazards No fvaluate potenti.il for or Yes 3/83 -
consequen.es of aircraf t impat. t .
III-5.A 4.9(1) Cascading Pipe Breaks No , See llein 4.16. - - -
4.9(2) Jet Impingement Effects No tivne - - -
4.9(3) Drywell Penetration No flune - - -
See footnotes at end of table.
- - .H
ATTACHMENT II o
5<
un I 8181c 4.1 (l'.,nt inn. .I) et m
1 .
n lesh. Spec.
2 SEP Topic modifications Section requireil trom II.n l i i t Comple-No. No. Title Str revieu Licensee Lion PRA m requ i r. i ..ni , agrees date rating 111-5.B 4.10(1) LOCA Dutside Containment No Evalu.ite and iilentify any Yes 3/83 -
sieeded upgrading of the main steam and reactor water cleanup (RWCU) piping outside containment to precluile an unisolatable break out s i<te cont ainment.
4.10(2) Emergency Condenser No
! Isolation , t. valuate and itlent ity modi- Ye:. Cycle X -
. ic.ition to provide leakage dele.:liuss in enstere flaws
' woulillie detected before
.n. .
pipe fireak occurs.
s m 111-6 4.11(1) Piping Systems H No Analyze on a sampling Yes Cycle X -
l> asis and verity ailequacy ut support desiipis for the
- ,eismic resist.ince of speciIled pipinig systems.
4.11(2) Mechanical Equipment No llem..n,trate th.it the control Ye. 12/82* -
rod ih ive sysicm .nni vesse 1 >
intern ils h.sve :,ull icient - ,
c.ip.u i t y t o re . is t a sa fe
~
.,butlown earthquate or take c.orr..Isve attinn. ~
4.11(3) Electrical Equipment No
- Reevalu.ite 4160-V switch- Yes Cycle X -
gear p.ini!! .eli hdreig ? and sI dl*l ilesnon.Ir.ite, on a sampling 83 an).
b.isi . .nlequ.ny of electri-e . I p.o e i .ppori3. .
See footnotes at end of table.
ATTACFBIENT II y Table 4.1 (Contimacil) m n fech. Spec.
s SEP n.oilii icai ions
[$ Topic Section reiguireil f rom u.n l i t Ces.ep t e-
- Ii.ensee Linn No. No. Title SCP eview re.peir er.. n ts PRA m .
a!pye , elo t e rating
$ III-6 4.11(4) Ability of Safety- No (ti n i.-
Related Electrical -
Equipment to Function 4.11(5) Qualification of Cable No Provide plan to implement Yes 1
Trays Cycle X -
results of $LP Owners
(;roup Program on a t-lant-
- , pes. i t ic bas is.
111-7.8 4.12 Design Codes, Design tio Criteria, Load I v.sluate arte.pucy of Ye:, 6/83 -
original design criteria Combinations and Reactor un 4 :,aniplinig basis for Cavity Design Criteria T.
un
- .I.e. e l ic.I st rot.tural ele ent,.
- 9 III-8.A 4.13 Loose-Parts Honitoring No
> !!.ine - -
i and Core Barrel Low Vibration Monitoring Ill-10.A 4.14(1) Thermal Overload Bypass No tvaluate theraul overload Ye> Mediumi leyp.e.scs for engineered 12/82**
astty scatures (tSt) valves.
4.14(2) Magnetic Trip Breakers No flun.- - - -
IV-2 . 4.15 Reactivity Control Systems, No it..ne Including Functional Low Design and Protection -
A0 ainst Single Falinres ,
J .
See footnotes at end of table.
O
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Tecli. Spec.
Q SEP modi fications Cumple-
$ Topic Section required from liai.t ! i t -
F No. . No. Title Licensee Lion .PRA vi SEP review rerin i n en.en ts a jrees date rat.ing
$ V-5 4.16.1 Airborne Particulate and No Make these monitors yes*
Cycle X** tow Gaseous Radioactivity operational Honitoring
. topic lil-5.A analysis.
4.16.2 Operability Requirements Yes include lealage iletection Yes** 12/82 -
- .ytt.:m IimiLing t.ondif.lons N for operation in lechnical
( N.. Intersystem Leakage No None - - -
t 4.16.4 Reactor, Coolant N.o Non.-
- .- y Inventory Balances .
- V-6 4.17 Reactor Vessel Integrity No Submit a plan for the Yes 12/82**
material surveillance Caphilles. -
V-10.8 4.18 Residual lleat Removal x No
% +
Review and upgraile, if Yes Before* Low System Reliability nete:.sary, shutdown Cycle 10 proi c lures to specify - Startup _
" alternate sources of '
'. f-C =
a water for primary and -
~ secon.l.ory mateop, with -
partioilar at tention to ', r.
cxternal event:.. '
- a V-II: A 4.19 Requirements 'foir Isolation No
- Demonstr.ile selief capacity Ye:,- 1/83 ' '
, of Hign- and Low-Pr' essure and arr. i.t.il.le i unsequences , '
. tcf Systems l or filent s i.. . orrec t ive action 4
to p ru t . . i R.! il ,y , t em.
> ~
See f ootnotes at end of tafale.
L g,, -%- y
',[" \
s g M s-' a &w
,s '
.s _ , ~ &
_ -- ;- g-gggg y y -
y~ "
.7 lable 4.1 (Cont iemeil) f' '
us -
e et
- 4
- y. _ . . . .. . . .-
lech. Spec.
9 SEP modifications Comple-
@ lopic Section required from Backlit l icensee tion PRA x No. No. Title SEP review m
renguirements aurec> i.a t e rating E V-12.A 4.20 Water Purity of BWR Yes implement propused procedure Yes* Cycle X** -
l Primary Coolant unit mi,ility lecluiical Specifi-I cdliutts to be consistent.
VI-1 4.21.1 Organic Materials No In31 ert and repair, if Yes Cycle X -
nec essar y, drywell coatings '6 me.
and secoat the torus.
l ,,
4.21.2 Postaccident Chemistry No None - - -
VI-4 4.22.1 Locked-Closed Valves No Provide ><.hedule to implement Yi: . 11/82 Low physical lockinig devices to ca,ure valves are not y in.sdvertent ly opened. .
4.22.2 Remote Manual Valves No Yes. Cycle X**
Provide leakaue ifetection ,
dild, il nece: sary, relocate the operating station for i>olat ion valves in the coniainment spray and core spr.sy systems.
4.22.3 Valve Location No lione - - -
4.22.4 Instrument Lines No Non.- - - -
4.22.5 Valve Location and Type No None - - -
4.22.6 Remote Manual Valves No None - - -
VI-7.A.3 4.23 Emergency Core Cooling Yes includ. em.:ry.ncy condenser Yes** Gycle X** -
System Actuation System logic ..iis,9 in t rie lechoi. ..I Lpei i t i4.itions.
See footnotes at end of tahle.
ATTACllMENT II 5< lable 4.1 (Corit inie.il) sn
. . . . . . - ~ - - - - ~ ~ - -
s tech. Spec.
n SEP -
nindifications Topic Section Comple-2 required froni llack t i t Licen,ce Lion PRA
- D No. No. Title SEP review 7e requirem..nt, ' agree:. state rating T
VI-7.A.4 4.24 Core Spray Nozzle No None - - -
Effectiveness VI-7.C.1 4.25(1) AC Automatic Bus Transfers No tvalu.ite the exi, ting Yes* 12/u2 Hediuin dtituinJt ir. httb I I*ettid fers ant! islent ify currecLive action:, to ensnre f aulted loads would sent lie t ran>l en reil.
4.25(2) DC Automatic Bus Transfers No flune - - -
VI-10.A 4.26.1 Response-Time Testing No lione - -
tow -
i 4.26.2 Instrumentation for Reactor No
- $ Verity .sti salety logic Yes 12/02 -
Trip System (RTS) lesting channels tied to the reactor ainde switch are tested by proceifure. .
Yes - luclule logic channel Yes** Cycle X** -
Lestinel in Icchnical Specilications.
4.26.3 Dual-Channel Testing No tione - - -
Vil-1.A 4.27(1) flux Monitoring Isolation No Perten m solinre m.. le and Yes 12/u2 tow
, cfici.I .indlysi:, t o <!etermine whether i:.olation elevices dt'e t's sjtlires! .48141 iali fility any vecih a! ul.sgr.nlinti.
4.27(2) Reactor Protection system flo ~ 1...,i .. l l r i c. il (RPS) Protective Trip 1.. ..tec t i on Yes rycle XI -
,, i t i.. I:.
i.ou.r upply
.o..! 1;l", a ,1 cr t .u e See f ootnotes at end of table.
ATTACHEVT II y ui lable 4.1 (Continued)
C+
q _ _ . _ . . _ . _ _ . _ _ . . . . . _ - -
n Tech. Spec.
s SEP
@ moditicaLions lopic Section requirect trom Backiit I:omisle-
- No. No. licen,ee tion PRA litle un SEP review requi reroent s agrees date rating
$ Vll-1.8 4.28 Trip Uncertainty and Setpoint Analysis Review No Install analog trip system. . Ye:, Cycle XI Low of Operating Data Dase
. Vil-2 4.29 Engineered Safety features -
System Control Logic and See Item 4.14(1). - -
Low Design Vll-3 4.30 Systems Required for Safe No Shutdown Provide minimum inventory - -
Low f or condensate storage tank
. as a water source for flood-ing event s (lien: 4.l(4))
i asid ident iry non-I SF equip-g ment in couldown procedures (Item 4. It!).
Vill-2 4.31 Onsite Emergency Power No Hodify annunciator > to Yes Cycle XI Low Systems (Diesel Generator) conform to IEt t Std.
279-19/l and hypass two trips (voltage-ampere reactive and reverse power) durinig accident conditions.
Vill-3.B 4.32- DC Power System Bus No Voltage Monitoring and Scheduh in>tallation of Yet, 12/82** liigh Anaunciation specified hattery status alarm,.
Vill-4 4.33 Electrical Penetrations of No
.None - - -
Reactor Containment See footnotes at enr1 of table.
=
ATTACHMENT II o-
- < Iafile 4.1 (Cor.: isumil) us
' --- - ~ ~ - -
Tech. Spec.
Q SEP modificaLions
% Topic Section Comple-7t- reignired irom IM:t it L icen:.ce t it,n tio. No. Title SEP review PRA v> i ci:n ii .-n..-n t > aurces state rating Q IX-5 4.34(1) Restoration of Ventilation tio tvain.it e .niit i ev ine, i f . Ye:, 3/83 -
nece.s..ry, the lo w-o f-ofisite poveer pnn:edures to en:, ore that restoration of ventilJtion sy*,tems Will not overload the aliesels.
4.34(2) Reactor Building No None Ventilation - - -
4.34(3) Core Spray and Containment No Spray Pump Ventilation llemonstrate subject pumps Yes 3/83 -
can operate with a loss
? of vent ilation, or identify y corrn Live act iosi, as nece n.iry.
4.34(4) Battery, Motor-Genarator, No and Switchgear Ventilation Ivalo.ite eltect > of loss of Yes 12/83 -
ventilation to the subject room , anil islent ify any needed upgrading. .
XV-1 4.35 Decrease in feedwater Ho Itone Temperature, Incrsase in - - -
Feedwater Flow, and In- .
crease in Steam Flow and Inadvertent Opening of a Steam Generator Relief or Safety Valve .
XV-15 4.36 Radiological Conseituences Yes in.plement BWR Standard Yes** Cycle X**
of failure of Small Lines lechnii:al Specif ication Carrying Primary Coolant Outside Containment limit 1.n prim.iry toolant
.ir i i v i t f.
o 5<
un I.d,le 4.1 (G.nt inue.Il d
m a fec.h. Spec.
Q SEP modificotions Topic Section Cinnple-
$ 11 o . No. Title required from Udt.k r i t Licen.cc Iinn PRA
-. SEP review requireu.ents aurces date rating g XV-18 4.37 Radiological Consequences -
of a Main Steam Line see llem 4.36. .
Failure Outside Containment XV-19 4.38 Loss-of-Coolant Accidents tio Develop and implement a Resulting from Spectrum Yes Cycle XI -
of Postulated Pipe Breaks preventive maintenance program for the main steam
': Within the Reactor Cnolant Pressnre Boundary isolation valves or justify existing maintenance based on operating experience.
~
Sibmit results of evalua- Before* Cycle X -
' i Lion int luding testing Cycle 10 g experieni:e. Startup
- lligh for other reasons as explained in the referenced section. _ _ . _ _ - . .
NOTES:
Later - the licensee has not yet responded.
Cycle refers to the end of a vecific refueling outage by core cycle.
e e