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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:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20065H0111990-09-28028 September 1990 Offers to Perform Work Under NRC Contract 26-89-289,Task Order 4 Re Diagnostic Evaluation at Plant ML20246M7331989-03-15015 March 1989 Responds to NRC Info Notice 88-082, Torus Shells W/ Corrosion & Degraded Coatings in BWR Containments. Summary of Relevant Projects for Various Utils Successfully Employing Underwater Alternative to Draining Vessel Encl ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20236S4291987-10-20020 October 1987 FOIA Request for Listed Documents,Including Encls from NRC Requesting Addl Info on Gpu Topical Repts TR-033 & TR-040 & Encl to NRC Meeting Summary Re SPDS ML20215L7401987-05-0101 May 1987 Forwards EGG-NTA-7617, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety Related Components:Oyster Creek, Final Informal Rept.Rept Concludes Licensee Conforms to Generic Ltr on Item ML20214R3581987-03-12012 March 1987 Forwards Follwup SEP Evaluation of Part of Remaining Open Items for Oyster Creek Nuclear Power Plant. Reported Results Indicate That Licensee Actions in Response to Open Items Will Be Acceptable If Recommended Actions Taken ML20133H0871985-10-10010 October 1985 Requests Ltr Stating That Listed Facilities Do Not Have Fuel Element Transfer Tubes.Documentation Needed for IE Bulletin 78-08 Closeout Rept ML20134P3451985-08-26026 August 1985 Forwards Original & Revised Versions of Lecture 3 Re Interactions W/Nrc for Containment Sys Leakage Testing Course ML20063J0811982-06-28028 June 1982 Summarizes Comparison of Control Rod Drive Pump Discharge Line as-built Drawings W/Analytical Model Used by Eg&G. Marked-up Copy of Gpu Nuclear Sketch SK-F-M-0020 Encl ML20054H0221982-05-12012 May 1982 Forwards Revised SEP Topic III-5A,High Energy Piping Sys Inside Containment, Providing Info Per 810610 Request ML20084C0531969-03-22022 March 1969 Forwards Metallurgical Exam & Review of Casting Defects in Stainless Steel Valves Bodies .., Evaluation of Welding & Insp Techniques... & Rept of Participation in Intensive QA Audit by Region Iii,Div of Compliance... W/O Repts ML20084C7611967-11-16016 November 1967 Clarifies Participation at ANS Chicago,Il Meeting.No Employees or Consultants Registered Nor Attended Any Formal Sessions Sponsored by ANS or Aif.Not Responsible for Disclosure of Info 1990-09-28
[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] |
Text
K. Morton, ECGG wn.~ -? t-: 7.:
M P R ASSOCIATES, INC.
June 29, 1982 Mr. Thomas Cheng Systematic Evaluation Program Branch U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014
Subject:
Oyster Creek Nuclear Generating Station, Systematic Evaluation Program (SEP)
Dear Mr. Cheng:
At the request of GPU Nuclear (Mr. Y. Nagai) , we are encicsing the results of our review and comparison of the control rod drive (CRD) pump discharge line as-built drawings with the analytical model used by EG&G in their analysis of this piping. Included in the enclosure is a marked-up copy of the GPU Nuclear Sketch (SK-F-M-0 0 2 0 )
showing the CRD pump discharge as-built geometry and support locations with corresponding locations of node numbers used in the EG&G model (marked in red) and five sheets of CRD as-built support detail drawings (SK-F-5-0028 Sheets 1 through 5). Table 1 in the enclosure is a summary of as-built piping geometry and support locations compared to the modeled locations. The Table 1 summary references the node numbers that are marked on the enclosed sketch. Table 2 in the enclosure is a summary of the as-built support information (support type and direction) compared to modeled support input.
Results of the review and comparison are summarized as
.'follows:
- 1. The piping system modeled by EG&G starts at the elbow of the CRD pump discharge line. Seven and one half inches of piping from the pump discharge
- nozzle to the elbow was left out. This can be i
seen by looking at nodes 5 and 1230 on the marked- ,
up as-built support location sketch. The addition j of this pipe section in the EG&G model could -
reduce stresses by adding local flexibility in the area of the socket weld-elbow.
l l
1 L _
i 8209020276 820831 PDR ADOCK 05000219 P PDR y 114 o CON N ECTICUT AVENUE. N. W. WAS HINGTON. D. C. 20036 4091! 2o2 6*9 2320
1 P R AOsOCIATEs. INC.
Mr. Yoshito Nagai June 28, 1982
- 2. The piping system modeled by EG&G does not model the one inch recirculation lines coming out of the discharge line approximately 5-1/2 feet above the pump anchor points. This can be seen at nodes 45 and 1195 on the marked-up as-built support location ske.ch. The addition of the recirculation lines coult pr(vide both vertical and horizontal support whici .s not included in the EG&G model.
- 3. The U-bolt type supports modeled by EG&G do not take into account friction between the bolt and piping for the direction parallel to the pipe. An example is shown on the marked-up as-built support loca, tion sketch, for a U-bolt support at node 1105, where the system is assumed to be free to move in the X-direction. This very conservative
, assumption should be re-evaluated and some credit for friction in these supports considered.
l 4. Geometry variations from the as-built locations vary significantly from the modeled system starting at node location number 235. The as-built dimensions show the piping system turning through a 45 degree turn where the modeled system does not. The maximum geometry variations from as-built drawings, from Table 1, are as follows:
Maximum Maximum Maximum .
X-Direction Y-Direction Z-Direction variation variation Variation 5 ft 5 ft 8 ft at at at j Node 1065 Node 410 Node 585
- 5. The piping system modeled by EG&G fails to model eight supports at various points along the piping system. Piping supports that were not modeled by EG&G are shown in the marked-up as-built supporte location sketch by red circled letters (3 , D , E ,
F,G,H,I, and J).
At your request, copies of this letter and enclosure are being transmitted directly to EG&G, Idaho, Mr. Keith Morton. '.
M P R ACsoCIATES, INC.
Mr. Yoshito Nagai -
3- June 28, 1982 Please contact us if you have any questions on the attached. -
Sincerely, S-Wm. R. Schmidt Enclosure cc: Y. Nagai, GPUN K. Morton, EG&G S
e ,
M
,y - ..--a- - - .n-,- -
..-,, , , e, , , - - . . ,,, - - . - , , .
. TA8LE 1
SUMMARY
OF AS-BUILT PIPING AND SUPPORT LOCATIONS COMPARED TO MODELED LOCATIONS Page 1 of 3 AS-8UILT LOCATIONS MODELED LOCATIONS 10DE POINT X Y Z X Y Z (ft) (ft) (ft) (ft) (ft) (ft)
- 5 0.0 0.0 0.0 0.0 0.0 0.0
5.167 0.0 0.0 6.167 0.0 0.0 30 .167 5.208 0.0 .167 4.290 0.0
.167 4.290 .75 1205 6.334 5.208 0.0 6.334 4.290 0.0
6.334 4.290 .75 45 .167 6.333 0.0 .167 6.413 0.0 1195 6.334 6.333 0.0 6.334 6.413 0.0
- S5 .167 6.5 .458 .167 6.580 -1.0
- 1185 6.334 6.5 .458 6.334 6.580 -1.0 60 .167 6.5 -1.25 .167 6.580 -1.5 1175 6.334 6.5 -1.25 6.334 5.580 -1.5
- 110 .167 6.5 -8.75 .167 6.580 -10.0
- 1135 6.334 6.5 -8.583 6.334 6.580 -9.0
- 1105 3.917 6.5 -10.833 3.334 6.580 -11.0 140 .167 6.5 -13.75 .167 6.580 -13.931 150 417 6.5 -14.00 .264 6.580 -14.167
- 170 .417 6.5 -18.125 .264 6.580 -18.098 175 .417 6.5 -18.583 .264 6.580 -18.931
- 230 .417 16.208 -18.750 .264 16.580 -19.098 235 .417 17.417 -18.750 .264 17.413 .-19.098 (A) -3.119 17.583 -22.286 - -
- (B) -3.119 17.583 -29.786 - - -
- 295 -3.119 17.583 -36.953 .264 17.580 -30.348
- (D) . -3.119 17.583 -40.286 - - -
port Location - Refer to Table 2 for support type _,and direction.
TABLE 1 (CONTINUED)
Page 2 of 3 AS-BUILT LOCATIONS MODELED LOCATIONS JE POINT X Y Z X Y Z (ft) (ft) (ft) (ft) (ft) (#t) 335 -3.119 17.583 -42.619 .264 17.580 -38.181
- 360 -3.119 23.500 -42.786 .264 23.580 -38.348
- 410 -3.119 42.458 -42.786 .264 37.580 -38.348 440 -3.119 46.042 -42.786 .254 46.413 -38.348 460 -1.354 46.208 -44.551 2.716 46.580 -40.800
- 470 -1.104 46.208 -44.551 3.765 46.580 -40.849
- 495 8.854 46.208 -44.551 10.765 46.580 -40.849
- (E) 15.438 46.208 -44.551 - - -
- 510 15.813 46.208 -44.551 15.265 d6.580 40.849
- (F) 21.021 46.208 -45.009 - - -
- 551 21.021 46.208 -45.551 25.765 46.580 -41.849
- (G) 21.021 46.208 -46.468 - - -
- 580 21.021 46.208 -58.718 25.765 46.580 -50.015
- 585 21.021 46.208 -59.593 25.765 46.580 -51.515
$635 21.021 46.208 -70.801 25.765 46.580 -66.515 650 21.021 46.208 -74.301 25.765 46.580 -70.946
- 660 22.082 46.208 -75.528 26.826 46.580 -72.076
- (H) 27.974 46.208 -81.421 - - -
- (I) 31.333 46.208 -84.780 - - -
730 38.404 46.208 -91.851 41.680 46.580 -86.930
- 755 46.473 46.208 -95.883 46.437 46.580 -89.522
- 780 51.343 46.208 -97.900 53.367 46.580 -92.392
- 805 56.334 46.208 -99.830 58.525 46.580 -94.114
- 830 59.334 46.208 -99.830 63.525 46.580 -94.114 835 59.917 46.208 -99.830 64.359 46.580 -94.114
60.084 45.208 -99.830 64.525 d5.330 -94.114 870 60.084 39.208 -99.830 64.525 40.247 -94.114 oport Location - Refer to Table 2 for support type and direction.
-e,- , , - - - - - ---*--*,-w-- - - - -
e-w~-- g-y y,,-- w-e----e,e-w-w-- ~~- -
TABLE 1 (CONTINUED)
Page 3 of 3 AS-BUILT LOCATIONS MODELED LOCATIONS DE POINT X Y Z X Y Z (ft) (ft) (ft) (ft) (ft) (ft)
- 900 61.141 39.041 -99.830 69.525 40.080 -94.114
- 920 69.375 39.041 -99.830 73.525 40.080 -94.114 925 70.084 39.041 -99.830 74.359 40.080 -94.114
- 945 70.250 37.499 -99.830 74.525 36.830 -94.114 960 70.250 34.791 -99.830 74.525 33.747 -94.114 971 70.250 34.624 -101.225 74.525 33.580 -94.864
- 1245 70.250 34.624 - 74.692 33.580 -95.322
- (J) 70.250 30.666 -101.225 - - -
995 70.250 27.082 -101.225 74.525 27.747 -95.864 1010 70.250 26.916 -102.308 74.525 27.580 -95.864
- 1250 69.417 26.916 -102.308 74.317 27.580 -95.864 1255 68.542 26.916 -102.308 73.817 27.580 -95.864
- 1290 65.083 26.916 -102.308 69.025 27.580 -95.864 1020 70.250 26.916 -103.641 74.525 27.580 -97.198
- 1025 69.417 26.916 -103.808 74.359 27.580 -97.364 1030 68.542 26.916 -103.808 73.775 27.580 -97.364
- 1065 63.542 26.916 -103.808 68.525 27.580 -97.364
- 1085 63.083 26.916 -102.308 66.525 27.580 -96.864 coort Location - Refer to Table 2 for support type and direction.
_ _ _ _ - . ~ . _ . _ _ . _ . _ _ _ _ _ _ _ . _ . _ . . _ . _ _ _ . _ , _ . . _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . -
TABLE 2
SUMMARY
OF AS-BUILT SUPPORT INFORMATION COMPARED TO THE MODELED SUPDORT INFORMATION 1
Page 1 of 4 AS-BUILT SUPPORTS MODELED SUPPORTS l DIRECTION TYPE DIRECTION STIFFNESS NODE POINT OF SUPPORT OF SUPPORT OF SUPPORT OF SUPPORT (1b/in or lb-in/ rad) 5 1,2,3,4,5,6* Pump Anchor 1,2,3,4,5,6 Rigid Pt.
1230 1,2,3,4,5,6 Pump Anchor 1,2,3,4,5,6 Rigid Pt.
35 1,2,3 ** 1,2,3 1&2 .333 x 10 3 3 .7378 x 10 1235 1,2,3 ** 1,2,3 1&2 .333 x 103 3 .7378 x 100 55 2 Spring 2 50 1185 2 Spring 2 50 110 2 Hanger 2 10 5
1135 2 Hanger 2 10 5
1105 1,2,3 U-Bolt 2,3 10 5
1 = Pipe ***
170 1,2,3 U-Bolt 1,2 105 3 = Pipe 230' 1,2,3 U-Bolt 1,3 105 2 = Pipe (B) 2 Hanger None -
295 1,2,3 U-Bolt 1,2 10 5
3 = Pipe (D) . 2 Hanger None -
~
1 l
l TABLE 2 (CONTINUED) i Page 2 of 4 AS-BUILT SUPPORTS MODELED SUPPORTS DIRECTION TYPE DIRECTION STIFFNESS
' NODE POINT OF SUPPORT OF SUPPORT OF SUPPORT OF SUPPORT (1b/in or lb-in/ rad) 1,2,3 5 360 U-Bolt 1,3 10 2 = Pipe 5
410 1,2,3 U-Bolt 1,3 10 2 = Pipe 470 2 Spring 2 50 5
495 2 Hanger 2 10 (E) 2 Hanger None -
5 510 1,2,3 U-Bolt 2,3 10 1 = Pipe (F) 2 Hanger None -
5 551 2 Hanger 2 10 (G) 1,2,3 U-Bolt None -
3 = Pipe 5
' 580 1,2,3 U-Bolt 1,2 10 3 = Pipe 585 2 Hanger 2 105 635 1,2,3 U-Bolt 1,2 105 3 = Pipe ,
5 660 2 Hanger 2 10 (H) 1,2,3 U-Bolt None -
(Z) ., 1,2,3 U-Bolt None -
5 730 2 Dead Weight 2 10 l
Support _
l l
4 r
TABLE 2 (CONTINUED)
Page 3 of 4 AS-BUILT SUPPORTS MODELED SUPPORTS DIRECTION TYPE DIRECTION STIFFNESS NODE POINT OF SUPPORT OF SUPPORT OF SUPPORT OF SUPPORT (lb/in or 1b-in/ rad) 755 1,2,3,4,5,6 Concrete Angled Support 105 Wall 780 No Support Angled Support 10 5
805 1,2,3 Pipe Clamp 2,3 10 5
1 = Pipe 830 No Support 2 105 845 1,2,3 U-Bolt 1,3 10 5
. 2 = Pipe 900 1,2,3 Pipe Clamp 2,3 10 5
1 = Pipa 920 2 Spring 2 50 945 1,2,3 U-Bolt 1,3 10 5
l 2 = Pipe (J) 1,2,3 U-Bolt None 105 2 = Pipe 1025 1,2,3 U-Bolt 2,3 105 1 = Pipe l 1250 1,2,3 U-Bolt 2,3 105 1 = Pipe ,
1065 1,2,3 U-Bolt 2,3 105 1 = Pipe .
1290 1,2,3,4,5,6. CR0 Filter 1,2,3,4,5,6 Rigid Pt.
1085 1,2,3,4,5,6 CRD Filter 1,2,3,4,5,6 Rigid ,
Pt. _.
4 TABLE 2 (CONTINUED)
Page 4 of 4 AS-BUILT SUPPORTS MODELED SUPPORTS DIRECTION TYPE DIRECTION STIFFNESS NODE POINT OF SUPPORT OF SUPPORT OF SUPPORT OF SUPPORT (lb/in or lb-in/ rad) 1,2,3 ** 1,2,3 3 1245 1&2 .333 x g 3 .7378 x 10
- Support Direction 1 X Trans lb/in 2 Y Trans lb/in 3 Z Trans 1b/in 4 X Rot lb-in/ rad 5 Y Rot lb-in/ rad 6 Z Rot lb-in/ rad
= (Parallel to) l m
i
/
REVIEW OF THE MPR ASSOCIATES, INC. COMMENTS ON THE ORIGINAL CRD RETURN LINE ANALYSIS At the request of GPU Nuclear, MPR Associates, Inc. (MPR) reviewed and made comments on the original analysis of the CRD return line. The following is a review of the MPR comments and their utilization in the current analysis.
Comments 1, 2, and 4 deal with piping geometry variations in the original model. The system was accurately modeled based upon the information available.
These geometry variations were not shown on the original isometric drawings.
However, they have been incorporated into the current model based upon the as-built drawings.
The third comment indicates that the friction between U-bolts and the piping, parallel to the pipe, should be taken into account. Due to the lack of information concerning frictional values and their behavior during a seismic event, it was deemed appropriate to assume free movement in the axial direction of the pipe at U-bolt locations. This assumption was made for both the original and current analyses.
Comment 5 shows several supports that were not incorporated into the original model. Again, the support cor. figuration was modeled accurately l based upon the information available. With the exception of support "J",
these supports were not shown on the isometric drawings. For the current analysis, all of these supports have been incorporated except for two. At each of the points designated "E" and "J" the piping is supported off of adjacent piping. The information provided is insufficient to determine the response of the adjacent piping during a seismic event, and its effects upon the CRD return line. As shown in the results, the stresses are very low at these points, thus leaving a margin of safety in the event the adjacent piping might cause adverse effects.
- , - - - - ._