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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 IR 05000219/19993011999-10-0606 October 1999 Forwards Senior Reactor Operator Initial Exam Rept 50-219/99-301 on 990830-0902 at Oyster Creek Nuclear Generating Station.Informs That Based on Results of Exams, All Six SRO Candidates Passed All Portions of Exams 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 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 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 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 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 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 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 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 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 ML20206U3551999-02-0505 February 1999 Refers to Concerns Recipient Expressed to V Dricks on 990126 Related to Oyster Creek About Event Which Occurred on 970801 & About Administrative Control of EDG Vendor Manuals 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 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 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) 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 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 ML20198H3331998-12-22022 December 1998 Forwards Responses to 970909 & 980302 RAIs Re Review of Summary Rept Documenting Results of Seismic walk-down Evaluation Addressing GL 87-02.With Five Oversize Drawings ML20198J4991998-12-22022 December 1998 Forwards Response to RAI Re GL 96-06 Issues at Plant.With Three Oversize Drawings 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 ML20028G8241990-08-23023 August 1990 Forwards fitness-for-duty Semiannual Rept of Performance Data for Jan-June 1990.Each Rept Provides Listed Info,Per 10CFR26.71(d) 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 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)) 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 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 ML20043H4221990-06-15015 June 1990 Informs That Programmatic Issue & Corrective Actions Re fitness-for-duty Program Implementation Will Be Completed by 900801 & Verified by QA for Closure No Later than 900831 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 ML20034C9491990-05-29029 May 1990 Forwards Summary of Results of Statistical Analysis of Plant Tech Spec Setpoints,Per 881017-21 & 31-1104 Safety Sys Outage Mod Insp & 890130 Meeting ML20034C9871990-05-29029 May 1990 Forwards Rev 28 to Security Plan.Rev Withheld (Ref 10CFR73.21) 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 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 ML20043B3901990-05-0909 May 1990 Responds to NRC 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 ML20042G1411990-05-0101 May 1990 Requests That NRC Provide Formal Guidance or Revised Regulations for 10CFR26, Fitness for Duty. Exemption Request for Persons Unable to Provide Urine Specimen Due to Medical Reasons Inappropriate at Present Time ML20034C4721990-04-30030 April 1990 Forwards Eight Plots to Support NRC Review of Tech Spec Change Request 181 Re Reduction in Number of Main Steam Safety Valves,Per ML20034C0371990-04-26026 April 1990 Requests 60-day Extension to Complete Evaluation of Thyroid Dose Determination,Following Design Basis LOCA ML20034C0381990-04-25025 April 1990 Responds to Bulletin 89-002 Re Anchor/Darling Model S350W Swing Check Valves W/Type 410SS Bolts.Bulletin Does Not Applied to Facility Since No Anchor/Darling Model S350W Valves Used in safety-related Applications ML20034C0001990-04-25025 April 1990 Forwards Errata to 900410 Rev 3 to Corporate Emergency Plan, Consisting of Revised Page E10A-9 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 ML20034A4411990-04-11011 April 1990 Provides Info on Recent Findings Re Plant Drywell Wall Thickness & Plans to Assess & Maintain Structural Integrity. Safety Evaluation 000243-002 Rev 4 Confirmed Safe Operation of Plant Through 13R Outage Until Aug 1991 ML20034A0691990-04-0505 April 1990 Responds to Re post-accident Neutron Flux Monitoring (Reg Guide 1.97).Final Decision & Schedule for Implementation Will Follow Review of Safety Evaluation on GE Licensing Topical Rept ML20033G7281990-03-30030 March 1990 Provides Supplemental Response to Station Blackout Rule & Requests Clarification on Containment Isolation Valves, Reactor Coolant Inventory Loss & Loss of Ventilation.Util Analysis Meets Intent of NUMARC 87-00 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 ML20033E9991990-03-0606 March 1990 Forwards Completed NRC Regulatory Impact Survey,Per Generic Ltr 90-01.Form Modified to Incorporate Inpo/Numarc Guidance & Separate Category of Staff Hours Added ML20033E7501990-03-0202 March 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 185 to Accommodate Implementation of 21-month Operating Cycle w/3-month Outage, or 24-month Plant Refueling Cycle 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 ML20033E3201990-03-0101 March 1990 Submits 10CFR26 Fitness-for-Duty Program Implementation Status Rept,Per & Informs That as Result of self- Assessment QA Audit & Requisite Corrective Actions to Resolve Audit Findings,Util Will Have Improved Program 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 1990-09-05
[Table view] |
LER-1982-016, Responds to NRC Re Violations Noted in IE Insp Rept 50-219/82-17.Corrective Actions:Utilization of Drain Path for Release of Radioactive Water Discontinued.Forwards Re Future Corrective Actions & LER 82-016/03L-0 |
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l GPU Nuclear o ked ive, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:
August 20, 1982 f
i Mr. Richard W. Starostecki, Director Division of Project and Resident Programs U.S. Nuclear Regulatory Commission Region I l
631 Park Avenue l
King of Prussia, PA 19406 l
Dear Mr. Starostecki:
Subj ect: Oyster Creek Nuclear Generating Station Docket No. 50-219 Inspection Report No. 82-17 This letter is submitted in response to your letter of July 22, 1982, regarding the findings of the June 2 - July 5,1982, routine inspection by Mr. J. Thomas of your staff.
In accordance with 10 CFR 2.201, enclosed is our response to the Notice of Violation. If there are any questions regarding the supplied information, please contact me or Mr. Michael Laggart of my staff at (609) 971-4643 Very truly yours, Peter B. Fiedler Vice President and Director Oyster Creek PBF:MWL:lse Enclosure cc:
Mr. Ronald C. Haynes, 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 8209200256 820910 PDR ADOCK 05000219 O
PDR GPU Nuclear is a part of the General Pubhc Utilities System
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VIOLATION:
Technical Specification 3 6.B.(2), requires that radioactive liquid effluents, being released to the discharge canal be continuously monitored.
Contrary to the above, from June 12, 1982 to June 14,1982', about 300 gallons of water with a total activity of 70 5 millicuries was released to the discharge canal via the storm sewer system and was not continuously monitored.
RESPONSE
The violation is correct as stated above. As identified in the inspection report, the drain path utilized on June 12,13, and 14,1992, was thought to lead to a radwaste collection sump. Upon discovery by an employee that the drain path actually led to the environment via storn catch basins,. the utilization of the drain path was discontinued. Full compliance was achieved at this time.
a With regard to future corrective actions, two previcus submittals have been made to the NRC regarding the subject violation. On July 14, 1982, Reportablo Occurrence No. 50-219/82-16/03L was submitted; and on July 20, 1982, a letter was submitted detailing future corrective actions. Both submittals are being included as attachments to this response. The corrective. actions detailed, adequately address the concerns of the violation.
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CPU fluclear a '. a Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number.
July 20, 1982 Mr. Ronald-C. Haynes, Administ rator Region I U.S. Nuclear Regulatory Conmission 631 Park Avenue King of Pressia, PA 19406
Dear Sir:
Subj ec t: Oyster Creek Nuclear Generating Station Docket No. 50-219 Contamination Control On June 11, 1982, the New Radwaste service air system at Oyster Creek was contaminated with radioactive water from a resin transfer tank. The contamination resulted from a failure of a check valve to isolate at a cross-connection of the two systems.
While d raining the contaminated water from the service air system, an inadvertant release to the environment occurred.
The drain path utilized was thought to Icad to a radwaste collection sump; however, it was discovered that it actually led to the environment via storm catch basins.
Ai tsched to this letter is a copy of Reportable Occurrence No. 82-16, submitted on July 14, 1982.
The LER describes the above events in more detail; however, we feel the format of the report does not convey how serious GPU Wuclear regards this matter.
This letter is being submitted to inform the NRC as to how management intends to allocate its resources in matters of this nature.
Although the radioactivity released during this event did not endanger the public health and safety, we realize that a potential for future releases may exist due to intersystem cross-connects. In addition to the corrective actions listed in the attached Reportable Occurrence, we plan to undertake the following in order to prevent recurrence:
1.
Perform a documented review of all plant floor and roof drain systems including, where feasible, a field verification of drawings to identify the discharge points. Conspicuously mark all such drains to clearly differentiate those that discharge to nomally contaminated systems from those that discharEe to the environment or cican collection systems.
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GPU Nuclear is a port of the General Pubhc Utilities System
Mr. Bons 1d C. Haynes Page 2 July 20, 1982 2.
For floor drains or hub drains inside the radiation controlled area or other potentially contaminated areas that are found,to discharge to the enviromsent or clean collection systems, provide suitable plugs or shutoff devices, where feasible, that will be procedurally controlled to preclude inadvertant discharge of contaminated caterial.
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3 Identify all cross-connect psths to clean systems that may result from nor. mal opera tion, valving errors, valve 1cakage, or check valve Icakage.
Encure that appropriate procedural controls exist on the intentional use of these croc -connects to n.Ssare that cross contamination does not occur.
4.
For all system or component draining evolutions using temporary pipe or hose connections, establish procedural controls to verify the discharGo point of the drain path before commencing the evolution.
5 For systems or component drain paths determined to discharge to the environment or cican systems, evaluate, on an individual basis, the feasibility and desirability of redirecting the drain Isth to a contaminated collection system.
The above actions are scheduled for cocpletion prior to 2/1/83 If there are any questions, please feel free to call me or Mr. Michael Laggart of my staff at (609) 971-4643 Very truly yours,
//
Peter'B. Fiedler Vice President and Director Oyster Creek PEF:MWL:Ise cc: KRC Recident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731
GPU Nuclear r,
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Forked River New Jersey 08731 609 693-6000 Writer's Direct Dia! Number:
July 14, 1982 Mr. Ronal'd C. Haynes, Administrator Ragion 1 U.S. !;uclear Eeculatory Ccrcicsion 631 Psrk Avenue King of Prussia, PA 19406
Dear Mr. Haynes:
Subject:
Oyster Creek ?:uclear Generating Station Docke t !io. 50-219 Licensee Event Report Reportable Occurrence io. 50-219/82-16/03L This letter forwards three copies of a Licensee Event Esport to report Reportable Occurrence No. 50-219/82-16/03L.in ccapliance ith paragraph 6 9 2.b.4 of the Technical Specifications.
Very truly yours, I'
We Peter S. Fiedler Vice President and Pirector Oyster Creek PBF:1se Enclosures cc: Director (40 copies)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Director (3)
Office of Manage::,ent Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC Resident Inspector Oyster Creek Nuclear Cenerating Station Forked River, NJ 08731 lK2 m--
OnvDH30T"J GPU Nuc! ear es a part of :ne Gene al Puche Utm: es S*s:em
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OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/82-16/03L Report Date-July 14, 1982 Decur rence Dat e_
June 11, 1982 Identification of Occurrence An unconitored release of radioactive water occurred due to contamination of service air piping in the New Radwaste Building. In one instance the leakage was to the discharge canal via the drainage system, and in two other instances, the leakage was to the soil.
This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.4.
J Conditions Prior to Occurrence 4
The plant was at steady state operation.
l Power Levels:
Reactor 1621 MWt Generator 540 MWe i
Mode Switch R,u n Description of Occurrence
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On Friday, June 11, 1982 at approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, New Radwaste Operations j
personnel were preparing to transfer spent resins from the storage tank into a shipping cask.
Prior to the actual. resin transfer operation, the tank was filled with condensate water to create a slurry and was then mixed using air at approximately 30 psig. With the air still mixing t,e tank contents, condensate h
water was used to backflush the resin transfer line into the tank.
It was during this backflush that the vent line became plugged, (attributed to a blinded resin screen on the vent) which resulted in pressurizing the tank from i
l the condensate transfer system. Water was forced back into the air line, through the pressure regulator and the in-line check valve (condensate water pressure at the tank is greater than air system pressure).
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Licensee Event Report Page 2 Report able Occurrence No. 50-219/82-16/03L The first evidence of a problem was when the backflush line pressure did not decrease as expected.
Further indications received later were an area high radiation ala rm near the air receiver tank, and the discovery of radioactive fluid leaking f rom a moisture trap in the air line.
The resin tank was isolated and all necessary safety and radiological concerns were promptly a leaking addressed. During the investigation into the extent of the problem, hose connection in an air line outside of the ::ew Radwaste Soilding was discovered. Total leakage to the soil was estimated at appr. imately 10 m1, with a gross radioactivity of 0.62 microcuries.
The air system geometry is such that most of the contaminated water remained in the bottom of the air receiver tank (thus preventing the accumulation in the a ir compre s sor a nd a f ter c ooler f rom becoming cont amina ted). The air receiver is automatically blown down through a drain line which has a filter and a trap in the line. The available data suggests this feature was inoperabic at the time of this event.
During the pri=ary decontamination of the air receiver, it was flushed with water several times via an alternate route utilizing a bypass around the filter / trap assembly.
It was realized on June 21, 1982, that the drain line from the air receiver leads to the storm drain which discharges directly to the discharge canal.
It total of approximately 300 gallons was discharged, with was estimated that a gross radioactivity o f 6.21 E-2 microcurie s/ml. This correlates to a total of 0.0705 curies.
Upon discovery of this event, the affected catch basins, s to rm drains, a~ d the air receiver drain line were isolated.
During the secondary decontamination of the air receiver using a hydrolazer, water (less than 5 gallons) leaked to the soil outside the building.
Approximately 30 f t of soil (3 f t.
x 10 ft. x 1 f t, deep) was collected and sampled; based on the sample results, all of the soil was returned to the original area.
Apparent Cause of Occurrence The cause of the event was attributed to a blocked vent line from the spent resin tank.
Si nc e the resin-water mixture level in the tank was above the level of the screen on the vent line, the air pressure in the tank apparently trapped enough resins against the screen to prevent the venting of the tank.
The vent valve in the line was checked af ter the event, and both the remote valve indication and valve operation checked out satisfactorily.
In addition, the check valve in the air system did not provide effective isolation of the spent resin tank from the Service Air System.
Analysis of Occurrence The first of the three interrelated events was the leak from the hose connection. All surveys taken of the soil from this leak (estimated at 10 ml) showed no appreciable readings above backgrout.d ievels.
Licensee Event Report Page 3 Report able Occurence No. 50-219/82-16/03L The second of these events was the leakage from the building to the soil.
Several soil samples were examined before returning the soil back to its location. The maximum concentrations of the two detetable isotopes, Mn 54 and Co 60, were 7.09 E-5 and 3.71 E-4 microcuries/gm, respectively.
Both of these values are within the limits set forth in 10 CFR 20 and 10 CFR 30 (10 CFR 30 is used to determine concentrations in the soil based on 1 gram.) Total volume leakage was estimated at approximately five (5) gallons.
The third of these events is the drainage to the discharge canal.
Total volume leakage was estimated at 300 gallons.
The isotopic analysis showed the following maximum concentrations:
Mn 54 9.46 E-3 microcurie s/ml Co 60 5.76 E-2 microcuries/ml Although these releases occurred during 3 separate flushes of the air receiver, the following analysis assumes that all 300 gallons were released in 15 m inu t e s.
It also assumes a minimum dilution flow of 460,000 gpm, even though actual dilution flow was higher.
Based on this, the concentrations of each isotope in the discharge are as follows, with their associated 10 CFR 20 limit:
Mn 54 4.11 x 10-7 microcuries/ml, limit 1.0 E-4 meirocuries/ml Co 60 2.29 x 10-6 microcuries/ml, limit 5.0 E-5 microcuries/ml
Corrective Action
The immediate corrective actions were to first isolate the affected spent resin tank and then prevent as much of the air system as possible from becoming
. contaminated. The air compressor was kept in operation, in order to prevent the syphoning of water into unaffected piping. A direct frisk was made of the ground under the total length of hose outside the building, and all readings 3 of soil outside the vere at or below background levels.
Approximately 30 f t building, af fected by the leak during flushing, was collected, sampled, and i
then returned once sample results were analyzed and it was determined that no 10 CFR 20 or 10 CFR 30 limits were exceeded.
The check valve in the air line to the spent resin tank was examined and no f ailures were detected.
The af fected storm drains and catch basins in the drainage system were decontaminated and the radiation levels in the air receiver have been reduced to background levels.
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Licensee Event Report Page 4 Report able Occurrence No. 50-219/82-16/03L In addition to these ef forts, the procedure for the transfer of spent resins has been reviewed, and has been changed to reflect two (2) important concepts:
- 1) the air mixing operation will be halted prior to starting the backflushing operation, so that air and condensate water are not being forced into the tank at the same time; 2) prior to transferring resins from the tank, the level in the tank will be lowered to insure that the resin slurry is below the screen on the vent line (i.e., prevent inadvertant vent line blockage).
An evaluation will be conducted to determine what constitutes acceptable isolation of noncontaminated systems from contaminated systems.
Based on the re sults' of this determination, modification of existing systems will be considered to prevent future incidents of contamination entering " clean" systems through designed interc onnections.
in all Additionally, procedural controls will be established to assure that nonroutine draining evolutions, the discharge point of the drain path will be verified prior to commencing the evolution. As an aid to implementing this requirement, a system of unique definition of noncontaminated drains will be evaluated.
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05000219/LER-1982-001-03, /03L-0:on 820128,during Testing,Containment Spray High Drywell Pressure Indicating Switches IP15A,IP15B & IP15C Found to Trip at Values Greater than Tech Spec Limits. Caused by Instrument Repeatability.Switches Reset | /03L-0:on 820128,during Testing,Containment Spray High Drywell Pressure Indicating Switches IP15A,IP15B & IP15C Found to Trip at Values Greater than Tech Spec Limits. Caused by Instrument Repeatability.Switches Reset | | 05000219/LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl | Forwards LER 82-001/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-002, Forwards LER 82-002/03L-0.Detailed Event Analysis Encl | Forwards LER 82-002/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-002-03, /03L-0:on 820118,installation of Mod Could Have Led to Possible Failure to Maintain Primary Containment Integrity.Change Defeated Automatic Withdrawal Function 3 & 4 TIP Detectors.Caused by Inadequate Safety Review | /03L-0:on 820118,installation of Mod Could Have Led to Possible Failure to Maintain Primary Containment Integrity.Change Defeated Automatic Withdrawal Function 3 & 4 TIP Detectors.Caused by Inadequate Safety Review | | 05000219/LER-1982-003-03, /03L-0:on 820122,containment Spray High Drywell Pressure Indicating Switch IP25B Found to Trip at Value Greater than Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset | /03L-0:on 820122,containment Spray High Drywell Pressure Indicating Switch IP25B Found to Trip at Value Greater than Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset | | 05000219/LER-1982-004-03, /03L-0:on 820121,reactor Bldg Closed Cooling Water Drywell Isolation Valve V-5-167 Failed to Fully Close.Caused by Lack of Stem/Stem Nut Lubrication &/Or Packing Problem. Stem,Stem Nut & Bearing Lubricated & Valve Repacked | /03L-0:on 820121,reactor Bldg Closed Cooling Water Drywell Isolation Valve V-5-167 Failed to Fully Close.Caused by Lack of Stem/Stem Nut Lubrication &/Or Packing Problem. Stem,Stem Nut & Bearing Lubricated & Valve Repacked | | 05000219/LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl | Forwards LER 82-004/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-005-03, /03L-0:on 820125,during Load Surveillance Test, Diesel Generator 1-1 Tripped on Engine Fault.Caused by Reduction of Water Inventory in Cooling Sys as Result of Radiator Tube Leak.Leaky Tubes Plugged | /03L-0:on 820125,during Load Surveillance Test, Diesel Generator 1-1 Tripped on Engine Fault.Caused by Reduction of Water Inventory in Cooling Sys as Result of Radiator Tube Leak.Leaky Tubes Plugged | | 05000219/LER-1982-005, Forwards LER 82-005/03L-0.Detailed Event Analysis Encl | Forwards LER 82-005/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-006-01, /01T-0:on 811203,one Trip Sys in Automatic Depressurization Sys Rendered Inoperable by Removal of Dc Control Power Fuses.Caused by Nonrating of Microswitches Inside IA83-A Replacement.All EMRV Switches Replaced | /01T-0:on 811203,one Trip Sys in Automatic Depressurization Sys Rendered Inoperable by Removal of Dc Control Power Fuses.Caused by Nonrating of Microswitches Inside IA83-A Replacement.All EMRV Switches Replaced | | 05000219/LER-1982-006, Forwards LER 82-006/01T-0.Detailed Event Analysis Encl | Forwards LER 82-006/01T-0.Detailed Event Analysis Encl | | 05000219/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl | Forwards LER 82-007/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-007-03, /03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered | /03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered | | 05000219/LER-1982-008-03, /03L-0:on 820210,monthly Channel Check of Secondary (Thermocouples) Safety & Relief Valve Position Monitoring Sys Not Performed as Required by Tech Spec. Caused by Lack of Administrative & Procedural Controls | /03L-0:on 820210,monthly Channel Check of Secondary (Thermocouples) Safety & Relief Valve Position Monitoring Sys Not Performed as Required by Tech Spec. Caused by Lack of Administrative & Procedural Controls | | 05000219/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-009-03, /03L-0:on 820210,overload Trip Occurred on Standby Gas Treatment Sys Exhaust Fan 1-8.Apparently Caused by Change in Breaker Trip Setpoint.Further Testing Underway | /03L-0:on 820210,overload Trip Occurred on Standby Gas Treatment Sys Exhaust Fan 1-8.Apparently Caused by Change in Breaker Trip Setpoint.Further Testing Underway | | 05000219/LER-1982-009, Forwards LER 82-009/03L-0.Detailed Event Analysis Encl | Forwards LER 82-009/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-010-01, /01T-0:on 820218,deluge Sys for Reactor Bldg Elevation 51 Ft Actuated Due to Smoke from Overheated Bearing in Cleanup Sys Auxiliary Pump Motor.Caused by Inadequate Electrical Sealing Techniques | /01T-0:on 820218,deluge Sys for Reactor Bldg Elevation 51 Ft Actuated Due to Smoke from Overheated Bearing in Cleanup Sys Auxiliary Pump Motor.Caused by Inadequate Electrical Sealing Techniques | | 05000219/LER-1982-010, Forwards LER 82-010/01T-0.Detailed Event Analysis Encl | Forwards LER 82-010/01T-0.Detailed Event Analysis Encl | | 05000219/LER-1982-011-03, /03L-0:on 820208,three Hydraulic Snubbers Were Inoperable & Accelerated Surveillance of Tech Spec 4.5.0.3 Was Not Performed.Caused by Component Failure.Snubbers Replaced W/Certified Operable Snubbers | /03L-0:on 820208,three Hydraulic Snubbers Were Inoperable & Accelerated Surveillance of Tech Spec 4.5.0.3 Was Not Performed.Caused by Component Failure.Snubbers Replaced W/Certified Operable Snubbers | | 05000219/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-012-01, /01P-0:on 820226,air Operated Vacuum Breaker V-26-18 Exceeded Allowable Leak Rate.Caused by Improper Alignment of Valve Shaft & Operator Due to Inadequate Maint Instructions.Valve Realigned & Procedures Will Be Revised | /01P-0:on 820226,air Operated Vacuum Breaker V-26-18 Exceeded Allowable Leak Rate.Caused by Improper Alignment of Valve Shaft & Operator Due to Inadequate Maint Instructions.Valve Realigned & Procedures Will Be Revised | | 05000219/LER-1982-012, Forwards LER 82-012/01P-0.Detailed Event Analysis Encl | Forwards LER 82-012/01P-0.Detailed Event Analysis Encl | | 05000219/LER-1982-013-03, /03L-0:on 820128,low Voltage Annunciator Relay Setting for Main Station Batteries B & C & Diesel Generator 2 Battery Relay & Setting Found Below Tech Specs Limit. Caused by Annunciation Setpoints Out of Spec | /03L-0:on 820128,low Voltage Annunciator Relay Setting for Main Station Batteries B & C & Diesel Generator 2 Battery Relay & Setting Found Below Tech Specs Limit. Caused by Annunciation Setpoints Out of Spec | | 05000219/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Encl | Forwards LER 82-014/01T-0.Detailed Event Analysis Encl | | 05000219/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-016-03, /03L-0:on 820611,during Transfer of Spent Resin, Svc Air Piping Became Cross Contaminated W/Water,Resulting in Three Leaks to Environ.Caused by Blocked Vent Lines on Tank.Affected Sys Isolated | /03L-0:on 820611,during Transfer of Spent Resin, Svc Air Piping Became Cross Contaminated W/Water,Resulting in Three Leaks to Environ.Caused by Blocked Vent Lines on Tank.Affected Sys Isolated | | 05000219/LER-1982-016, Responds to NRC Re Violations Noted in IE Insp Rept 50-219/82-17.Corrective Actions:Utilization of Drain Path for Release of Radioactive Water Discontinued.Forwards Re Future Corrective Actions & LER 82-016/03L-0 | Responds to NRC Re Violations Noted in IE Insp Rept 50-219/82-17.Corrective Actions:Utilization of Drain Path for Release of Radioactive Water Discontinued.Forwards Re Future Corrective Actions & LER 82-016/03L-0 | | 05000219/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-017-03, /03L-0:on 820325,normal Auxiliary Power Bus 1C Relay Failed Totally & Svc Water Pump Trip Time Delay Relay SK8A Failed to Operate within Tech Spec Limits.Power Bus Failure Caused by Normal End of Life | /03L-0:on 820325,normal Auxiliary Power Bus 1C Relay Failed Totally & Svc Water Pump Trip Time Delay Relay SK8A Failed to Operate within Tech Spec Limits.Power Bus Failure Caused by Normal End of Life | | 05000219/LER-1982-018, Forwards LER 82-018/03L-0.Detailed Event Analysis Encl | Forwards LER 82-018/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-019-01, /01T-0:on 820331,local Leak Rate Test for Valves V-1-106 & V-1-111 Found Leakage Exceeding Tech Spec Limit. Caused by Deterioration of Valve Internals.Valves Repaired | /01T-0:on 820331,local Leak Rate Test for Valves V-1-106 & V-1-111 Found Leakage Exceeding Tech Spec Limit. Caused by Deterioration of Valve Internals.Valves Repaired | | 05000219/LER-1982-019, Forwards LER 82-019-/01T-0.Detailed Event Analysis Encl | Forwards LER 82-019-/01T-0.Detailed Event Analysis Encl | | 05000219/LER-1982-020-01, /01T-0:on 820328,MSIV Leak Rate Testing Disclosed Deterioration of Valve Internals on NS03-A & Packing Leak on Outboard Valve NS04-A.Caused Not stated.NS03-A Disassembled & repaired.NS04-A Repacked | /01T-0:on 820328,MSIV Leak Rate Testing Disclosed Deterioration of Valve Internals on NS03-A & Packing Leak on Outboard Valve NS04-A.Caused Not stated.NS03-A Disassembled & repaired.NS04-A Repacked | | 05000219/LER-1982-020, Forwards LER 82-020/01T-0.Detailed Event Analysis Encl | Forwards LER 82-020/01T-0.Detailed Event Analysis Encl | | 05000219/LER-1982-021-01, /01P:on 820416,primary Containment Atmosphere Not Reduced to Less than 5% Oxygen within 24-h After Reactor Mode Selector Switch Placed in Run Position.Caused by Insufficient Nitrogen & Blown Rupture Disc | /01P:on 820416,primary Containment Atmosphere Not Reduced to Less than 5% Oxygen within 24-h After Reactor Mode Selector Switch Placed in Run Position.Caused by Insufficient Nitrogen & Blown Rupture Disc | | 05000219/LER-1982-021, Forwards LER 82-021/01T-0.Detailed Event Analysis Encl | Forwards LER 82-021/01T-0.Detailed Event Analysis Encl | | 05000219/LER-1982-022-03, /03L-0:on 820416,after 1B Breaker Closed & Startup Transformer S1B Breaker Failed to Operate,Operator Determined That Fuse Had Blown.Caused by Mild Momentary Overload.Fuse Replaced & Breaker Reset & Returned to Svc | /03L-0:on 820416,after 1B Breaker Closed & Startup Transformer S1B Breaker Failed to Operate,Operator Determined That Fuse Had Blown.Caused by Mild Momentary Overload.Fuse Replaced & Breaker Reset & Returned to Svc | | 05000219/LER-1982-022, Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-023, Forwards LER 82-023/03L-0.Detailed Event Analysis Encl | Forwards LER 82-023/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-024, Forwards LER 82-024/03L-0.Detailed Event Analysis Encl | Forwards LER 82-024/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-024-03, /03L-0:on 820414,while Performing Surveillance on Electromatic Relief Valve Pressure Switches,Three of Five Switches Tripped Below Tech Spec Limit.Caused by Instrument Repeatability & Drift.Instruments Reset | /03L-0:on 820414,while Performing Surveillance on Electromatic Relief Valve Pressure Switches,Three of Five Switches Tripped Below Tech Spec Limit.Caused by Instrument Repeatability & Drift.Instruments Reset | | 05000219/LER-1982-026-03, /03L-0:on 820507,thermocouple for Safety Valve NR28J Found Open During Surveillance Testing.Caused by Broken Lead Wire at Thermocouple.One of Adjacent Valve Acoustic Monitor Setpoints Reduced.Thermocouple Replaced | /03L-0:on 820507,thermocouple for Safety Valve NR28J Found Open During Surveillance Testing.Caused by Broken Lead Wire at Thermocouple.One of Adjacent Valve Acoustic Monitor Setpoints Reduced.Thermocouple Replaced | | 05000219/LER-1982-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl | Forwards LER 82-027/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-028, Forwards LER 82-028/03L-0.Detailed Event Analysis Encl | Forwards LER 82-028/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-032, Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-033, Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | | 05000219/LER-1982-034-03, /03L-0:on 820616,300 Gallons of Contaminated Water Leaked to Environs Due to Broken Fitting.Caused by Failure of Threaded Connection on 1-2 Condensate Transfer Pump Discharge.Connection Replaced | /03L-0:on 820616,300 Gallons of Contaminated Water Leaked to Environs Due to Broken Fitting.Caused by Failure of Threaded Connection on 1-2 Condensate Transfer Pump Discharge.Connection Replaced | | 05000219/LER-1982-034, Forwards LER 82-034/03L-0.Detailed Event Analysis Encl | Forwards LER 82-034/03L-0.Detailed Event Analysis Encl | |
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