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Category:Calculation
MONTHYEARML24214A0702024-08-0101 August 2024 Enclosure 19: Technical Basis Document, Instrument Efficiency Determination for Use in Minimum Detectable Concentration Calculations in Support of the Final Status Surveys at OCNGS Revision 0, February 14, 2024 ML24214A0612024-08-0101 August 2024 Enclosure 15: ENG-OCS-014 Revision: 0, Basement Fill Model: Probabilistic Analysis for Embedded Pipes Scenario Oyster Creek Station, January 2024 ML24214A0792024-07-0808 July 2024 Enclosure 23: Tsd 24-063, Basement Fill Model: Calculation of Dcglw/F Values Assuming Industrial Use Scenario Exposure Pathways, Revision 0 ML24214A0492024-03-0606 March 2024 Enclosure 7: ENG-OCS-002 Revision 1, RESRAD-Build Input Parameter Sensitivity Analysis - Ocs, March 6, 2024 ML24214A0642024-03-0606 March 2024 Enclosure 16: ENG-OCS-015 Revision: 1, Basement Fill Model: Calculation of Embedded Pipe Dcgl Values Oyster Creek Station, March 6, 2024 ML24214A0602024-03-0606 March 2024 Enclosure 14: ENG-OCS-013 Revision: 1, Basement Fill Model: Calculation of Dcglw/F Values Assuming Industrial Use Scenario Exposure Pathways Oyster Creek Station, March 6, 2024 ML24214A0652024-02-20020 February 2024 Enclosure 17: ENG-OCS-016 Revision: 0, Calculation of Buried Pipe Dcgl Values Oyster Creek Station, February 20, 2024 ML24214A0582023-11-0101 November 2023 Enclosure 13: ENG-OCS-012 Revision: 0, Basement Fill Model Probabilistic Analysis for Instantaneous Release Scenario Assuming Industrial Use Exposure Pathways Oyster Creek, November 1, 2023 ML24214A0542023-07-26026 July 2023 Enclosure 11: ENG-OCS-008 Revision: 0, Derived Concentration Guideline Levels Values for Soil – Industrial Use Scenario Oyster Creek, July 26, 2023 ML24214A0532023-07-25025 July 2023 Enclosure 10: ENG-OCS-007 Revision 0, RESRAD-Onsite Probabilistic Analysis - Industrial Use Scenario Oyster Creek Station, July 25, 2023 ML24214A0572022-08-0404 August 2022 Enclosure 12, ENG-OCS-009 Revision: 0, Area Factors for Soil – Industrial Use Scenario, August 4, 2022 ML24214A0522022-04-14014 April 2022 Enclosure 9: ENG-OCS-006 Revision: 1, Area Factors for Use with Oyster Creek Dcgl Values for Buildings/Structures, April 14, 2022 RA-10-096, Submittal of Analytical Evaluation for a Reactor Recirculation Line Weld2010-12-15015 December 2010 Submittal of Analytical Evaluation for a Reactor Recirculation Line Weld ML1007004872010-02-24024 February 2010 Oc Generating Station Radiation Protection Calculation ML0932208222009-11-10010 November 2009 Calculation C-1302-822-E310-081, Revision 1, Oyster Creek Onsite Atmospheric Dispersion (X/Q) for Fuel Handling Accident (Fha), Attachment 5 ML0932208232009-11-10010 November 2009 Calculation C-1302-822-E310-082, Revision 2, Oyster Creek Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms (Ast), Attachment 6 RA-10-002, CY-OC-170-301, Revision 4, Offsite Dose Calculation Manual2009-08-19019 August 2009 CY-OC-170-301, Revision 4, Offsite Dose Calculation Manual ML1020203312009-05-19019 May 2009 Oc Liquid Individual Effluent Dosages RA-10-002, Oyster Creek, CY-OC-170-301, Revision 3, Offsite Dose Calculation Manual2009-04-28028 April 2009 Oyster Creek, CY-OC-170-301, Revision 3, Offsite Dose Calculation Manual ML1012411402009-04-28028 April 2009 Oyster Creek, CY-OC-170-301, Revision 3, Offsite Dose Calculation Manual ML0914103822009-04-28028 April 2009 Revision 3 of Offsite Dose Calculation Manual ODCM) RA-09-011, Submittal of Analytical Evaluation in Accordance with IWB-3134(b)2009-03-0909 March 2009 Submittal of Analytical Evaluation in Accordance with IWB-3134(b) ML0731804742007-10-0505 October 2007 Amergen/Exelon Calculation C-1302-822-E310-081, Revision 0, Oyster Creek Onsite Atmospheric Dispersion (X/Q) for Fuel Handling Accident (Fha), Attachment 3 ML0731804072007-10-0505 October 2007 Amergen/Exelon Calculation C-1302-822-E310-082, Rev. 0, Oyster Creek Analysis of Fuel Handling Accident Using Alternative Source Terms, Attachment 1 ML0713102152007-03-23023 March 2007 Enclosure 1, Oyster Creek - Calculation No. Psat 05201H.08, Revision 3, Dose Assessment for Oyster Creek Control Room Habitability. ML0709200712007-03-23023 March 2007 Calculation No. Psat 05201H.08, Revision 3, Dose Assessment for Oyster Creek Control Room Habitability ML0708508202007-03-15015 March 2007 Calculation No. C-1302-826-E310-018, Revision 0, Oyster Creek Offsite Atmospheric Dispersion (X/Q) for Alternative Source Terms (Ast). ML0634903062006-12-0808 December 2006 License Renewal Project, Drywell Monitoring Program, Information for ACRS Subcommittee Reference Material, Volume 3, Calculation ML0634500752006-11-0404 November 2006 Oyster Creek: Licensee Final Document - Water Found in Drywell Bay 5 Trench 00546049-02 (PD) ML0726704002006-06-13013 June 2006 Ttnus. 2006. Ocean County Demographic and Economic Growth Report Calculation Package ML0612101142006-04-26026 April 2006 2006/04/26-Oyster Creek - Response to NRC Request for Additional Information, Dated March 30, 2006, Related to Plant License Renewal Application ML0819000842005-08-15015 August 2005 OC-05Q-307, Revision 0, Feedwater Nozzle Green'S Functions. ML0511700342005-04-12012 April 2005 Letter of Paul Gunter on Behalf of the Nuclear Security Coalition Submitting Additional Documents as Supplemental Material to the Emergency Enforcement Petition (10 CFR 2.206) of August 10, 2004 ML0508705982005-03-0101 March 2005 Attachment B, PORC 04-37 Meeting Notes, and CY-OC-170-301, Rev 1, Oyster Creek Offsite Dose Calculation Manual ML0634903092003-08-31031 August 2003 1002950, Aging Effects for Structures and Structural Components (Structural Tools), Revision 1, Final Report ML0611503431998-03-0606 March 1998 Calculation C-1302-215-E320-063, Rev 0, Rwcw HELB High Temperature Setpoint Error Calculation, Enclosure 2 ML0611503451994-02-18018 February 1994 Engineering Standard ES-002, Instrument Error Calculation and Setpoint Determination. ML0706003811992-12-11011 December 1992 GE Letter Report Re Sandbed Local Thinning and Raising the Fixity Height Analyses (Line Items 1 and 2 in Contact # PC-0391407) ML0721502871978-06-0101 June 1978 the Effects of Saline Cooling Tower Drift on Seasonal Variations of Sodium and Chloride Concentrations in Native Perennial Vegetation 2024-08-01
[Table view] Category:Graphics incl Charts and Tables
MONTHYEARML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML16035A2652016-02-0909 February 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request Flood Causing Mechanism Reevaluation ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T RA-13-081, Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term.2013-09-16016 September 2013 Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term. RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan ML1007005112010-02-24024 February 2010 Hot Lab - Tritium Analyzer ML0914002552009-04-17017 April 2009 License Renewal Review Board ML0914002542009-04-17017 April 2009 License Renewal Review Board ML0911807222009-03-20020 March 2009 Appendix a: Commitments for License Renewal of Ocgs with Handwritten Notes ML0911403512009-03-20020 March 2009 Appendix a, Commitments for License Renewal of Ocgs ML0911807172009-03-20020 March 2009 Amergen, 2006 Measurements Locations in the Sandbed Region ML0911807342009-03-20020 March 2009 Appendix a: Commitments for License Renewal of Ocgs, Including Handwritten Notes ML0914004662009-02-11011 February 2009 1R22 LRA WOs (101) ML0832307262008-11-13013 November 2008 Reactor License Renewal Oyster Creek Safety Review Track RA-08-087, Response to Draft Request for Additional Information - Amergen Application to Revise Technical Specifications Regarding Secondary Containment Operability Requirements During Refueling (Tscr 338)2008-09-22022 September 2008 Response to Draft Request for Additional Information - Amergen Application to Revise Technical Specifications Regarding Secondary Containment Operability Requirements During Refueling (Tscr 338) RA-08-057, Unit 1, Application for Approval of License Transfers2008-06-20020 June 2008 Unit 1, Application for Approval of License Transfers ML0914004722008-05-0707 May 2008 1R22 Related License Tasks ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0721503352007-07-17017 July 2007 NMFS - Guide to Essential Fish Habitat Designations in the Northeastern United States ML0720500792007-07-0303 July 2007 Public School Review: New Jersey Public Schools ML0720501612007-07-0202 July 2007 Standard and Poor'S School Matters ML0720501662007-07-0202 July 2007 Standard and Poor'S School Matters ML0720501752007-06-29029 June 2007 Pss: Search for Private Schools ML0720501682007-06-0808 June 2007 U.S. Census Bureau: County Business Patterns ML0718302282007-02-0202 February 2007 Letter and Report for Additional Analyses of Two of the Twelve Soil Samples from Oyster Creek (Inspection Report No. 50-219/2006-05) from Orise Dtd 2/2/07 ML0726703972006-12-31031 December 2006 Bureau of Economic Analysis. No Date. Table CA25 - Total Full-Time and Part-Time Employment - Ocean County, New Jersey. U.S. Department of Commerce ML0720501722006-12-0101 December 2006 Leading Employers in Ocean County, 2006 ML0633305142006-11-28028 November 2006 Excel Charts for Fish Kills at Oyster Creek Nuclear Generating Station Provided by Malcolm Brown, OCNGS ML0726406022006-11-22022 November 2006 Ttnus. 2006. Analysis of Current and Historic Fish Data for the Purpose of Determining Similarity of Species Composition and Numbers of Fish Impinged and Entrained at Ocgs, 1975-1985 and 2005-2006 ML0720703732006-01-17017 January 2006 Summary of Essential Fish Habitat and General Habitat Parameters for Federally Managed Species ML0720500682005-01-0101 January 2005 NJDEP: Fact Sheet, Bureau of Point Source Permitting - Region I ML0726704042004-12-31031 December 2004 Energy Information Administration. 2004. State Energy Data 2002: Consumption. Table 7 Energy Consumption Estimates by Source, Selected Years, 160-2002, New Jersey. Us Department of Energy ML0720703782004-12-0909 December 2004 Wildlife Populations: Surf Clam ML0720500612004-04-30030 April 2004 Nj Pineland Commission: the Essential Character of the Oyster Creek Watershed ML0720703902003-03-31031 March 2003 NOAA Technical Memorandum NMFS-NE-179: Essential Fish Habitat Source Document: Winter Skate, Leucoraja Ocellata, Life History and Habitat Characteristics ML0726804482002-05-15015 May 2002 New Jersey Department of Environmental Protection. 2002. List of State Flood Hazard Area Delineations. May 15 ML0720703832000-01-31031 January 2000 Atlantic Surfclam by James Weinberg (January 2000) ML0720703891999-09-30030 September 1999 NOAA Technical Memorandum NMFS-NE-137: Essential Fish Habitat Source Document: Windowpane, Scophthalmus Aquosus, Life History and Habitat Characteristics ML0720706221999-09-30030 September 1999 NOAA Technical Memorandum NMFS-NE-138: Essential Fish Habitat Document: Winter Flounder, Psudopleuronectes Americanus, Life History and Habitat Characteristics ML0720706231999-09-30030 September 1999 NOAA Technical Memorandum NMFS-NE-151: Essential Fish Habitat Source Document: Summer Flounder, Paralichthys Dentatus, Life History and Habitat Characteristics ML0706003811992-12-11011 December 1992 GE Letter Report Re Sandbed Local Thinning and Raising the Fixity Height Analyses (Line Items 1 and 2 in Contact # PC-0391407) ML0705907151986-10-31031 October 1986 Gpu Nuclear Corporation, Oyster Creek Nuclear Generating Station Torus Shell Thickness Margin, MPR-953, 10/86 ML0720802101986-07-31031 July 1986 EA Report GPU44G Entrainment and Impingement Studies at the Oyster Creek Nuclear Generating Station, 1984-1985. ML0720703881983-10-31031 October 1983 Species Profiles: Life Histories and Evironmental Requirements of Coastal Fishes and Invertebrates (Mid-Atlandtic) - Surf Clam ML0726703621978-12-31031 December 1978 Jersey Central Power & Light Company. 1978. Oyster Creek and Forked River Nuclear Generating Stations 316(a) and (B) Demonstration, Initial Progress Report, December 1966, Through Third Progress Report, January 1968 ML0726801741978-12-31031 December 1978 Jersey Central Power & Light Company. 1978. Oyster Creek and Forked River Nuclear Generating Stations 316(a) and (B) Demonstration, Appendix C Continued Page C2-1 Through Page C6-51 ML0726801491978-12-31031 December 1978 Jersey Central Power & Light Company. 1978. Oyster Creek and Forked River Nuclear Generating Stations 316(a) and (B) Demonstration, Addendum to Appendix C1 Through Addendum to Appendix D1 ML0726705501978-12-31031 December 1978 Jersey Central Power & Light Company. 1978. Oyster Creek and Forked River Nuclear Generating Stations 316(a) and (B) Demonstration, Appendix a Through Appendix C1, Figure C1-1 ML0726704911978-12-31031 December 1978 Jersey Central Power & Light Company. 1978. Oyster Creek and Forked River Nuclear Generating Stations 316(a) and (B) Demonstration, Appendix E Through Appendix F, Figure 10 2016-03-11
[Table view] Category:Letter
MONTHYEARML24274A0822024-09-25025 September 2024 Independent Spent Fuel Storage Installation Security Plan, Training Qualification Plan, Safeguards Contingency Plan, Revisions 1 and 2 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000219/20240022024-09-0505 September 2024 – NRC Inspection Report 05000219/2024002 and 07200015/2024001 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24214A0372024-08-0101 August 2024 License Amendment Request to Revise Renewed Facility Operating License to Add License Condition 2.C.(18) to Include License Termination Plan Requirements ML24179A1842024-07-23023 July 2024 June 20, 2024, Clarification Call on Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000219/20240012024-05-14014 May 2024 Decommissioning Intl, LLC Oyster Creek Nuclear Generating Station - NRC Inspection Report No. 05000219/2024001 ML24120A0412024-04-29029 April 2024 Annual Radioactive Environmental Operating Report for 2023 L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24120A0402024-04-29029 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24094A2142024-04-19019 April 2024 Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan ML24089A2492024-03-29029 March 2024 Reply to Notice of Violation EA-2024-024 L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24085A7902024-03-28028 March 2024 – Preapplication Readiness Assessment of the License Termination Plan ML24081A2882024-03-21021 March 2024 Request Preliminary Review and Feedback on Chapter 6 of the Draft License Termination Plan ML24046A1242024-02-29029 February 2024 – NRC Inspection Report 05000219/2023003 ML24033A3272024-02-0202 February 2024 Request Preliminary Review and Feedback on Chapter 5 of the Draft License Termination Plan ML23342A1162024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 IR 05000219/20230022023-11-0909 November 2023 EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23249A1212023-09-0606 September 2023 NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076) ML23242A1162023-08-30030 August 2023 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022 ML23214A2472023-08-22022 August 2023 NRC Inspection Report 05000219/2023002 IR 05000219/20230012023-05-31031 May 2023 NRC Inspection Report No. 05000219/2023001 IR 07200015/20234012023-05-16016 May 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 ML23114A0912023-04-24024 April 2023 Annual Radioactive Effluent Release Report for 2022 ML23114A0872023-04-24024 April 2023 Annual Radioactive Environmental Operating Report for 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000219/20220022023-02-0909 February 2023 NRC Inspection Report No. 05000219/2022002 ML23031A3012023-02-0808 February 2023 Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System ML23033A5052023-02-0202 February 2023 First Use Notification of NRC Approved Cask RT-100 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22347A2732022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 ML22297A1432022-12-15015 December 2022 Part 20 App G Exemption Letter L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 IR 07200015/20224012022-12-0606 December 2022 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1) ML22280A0762022-11-0202 November 2022 Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22286A1402022-10-13013 October 2022 NRC Confirmatory Order EA-21-041 IR 05000219/20220012022-08-11011 August 2022 NRC Inspection Report 05000219/2022001 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22214A1732022-08-0202 August 2022 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML22207B8382022-07-26026 July 2022 NRC Confirmatory Order EA-21-041 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 2024-09-05
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i . - . . __ . ___ . . - . . . - -__-I- .. December 1 1, I992 To: Dr. Stephen Tumminelli Manager, Engineering Mechanics GPU Nuclear Corporation 1 Upper Pond Road Parsippany, NJ 07054
Subject:
Dear Dr. Tumminelli:
Sandbed Local Thinning and Raising the Fixity Height Analyses (Line Items 1 and 2 in Contract # PC-0391407)
The attached letter report documents the results of subject analyses.
The original purchase order called for the analyses to be conducted on a spherical panel model rather than on the full pie slice model. However, the results are more useful when conducted on the full pie slice model since in that case no interpretation is required regarding the relationship between the spherical panel results and the pie slice model results. The pie slice model we have used in these studies has the refined mesh in the sandbed region. A 3.5" PC Disk containing three ANSYS input files (0.636" case, 0.536" case and I foot wall case) is also enclosed with this letter. The detailed calculations have been filed in Chapter 10 of our Design Record File No. 00664. This transmittal completes the scope of work identified in the subject PO. If you have any questions on the above item, please give me a call. Sincerely, I H.S. Mehta, Principal Engineer Materials Monitoring
& Structural Analysis Services MaiI Code 747; Phone (408) 925-5029
Attachment:
Letter Report cc: D.K. Henrie (w/o Attach.) J.M. Miller (w/o Attach.) S. Ranganath (w/o Attach.) HSMOC-57.
WP LETTER REPORT ON ADDITIONAL SAiiDBED REGION ANALYSES 1 .O SCOPE AND BACKGROUND Structural Analyses of the Oyster Creek drywell assuming a degraded thickness of 0.736 inch in the sandbed region (and sand removed) were documented in GENE Report Numbers 9-3 and 9-4. A separate purchase order was issued (Contract
- PC-0391407) to perform additional analyses.
The PO listed the additiond analyses under two categories:
Line Item 001 and Line Item 002. This letter report documents the results of these analyses.
The additional analyses are the following:
(1) Investigate the effect on the buckling behavior of drywell from postulated local thinning in the sandbed region beyond the uniform projected thickness of 0.736" used in the above mentioned reports (Line Item 001). (2) Determine the change in the drywell buckling margins when the fixity point at tbe bottom of the sandbed is moved upwards by = 1 foot to simulate placement of concrete (Line Item 002). The original PO called for the Line Item 001 analyses to be conducted on a spherical panel. The relative changes in the buckling load factors were to be assumed to be the same for the global pie slice model. However, the mesh refinement activity on the global pie slice model and the availability of work station, has given us the capability to conduct the same analyses on the global pie slice mode1 itself, thus eliminating the uncertainties regarding the correlation between the panel model and the pie dice model. All of the results reported in this report are based on the pie slice model with a refined mesh in the sandbed region. 2.0 LINEITEM001 Figure la shows the local thickness reductions modeled in the pie slice model. A locally thinned region of = 6"x12" is modeled. The thickness of this region is 0.636" in one case and 0.536" in the other case, The transition to the sandbed projected thickness of 0.736" occurs over a distance of 12" (4 elements).
The various thicknesses indicated in Figure la were incorporated in the pie slice model by defining new real constants for the elements involved. The buckling analyses conducted as a result of mesh refinement indicated that the refueling loading condition is the governing case from the point of view of ASME Code margins.
Therefore, the stress and buckling analyses were conducted using the refuehg condition loadings.
The center of the thinned area was located close to the calculated maximum displacement point in the refueling condition buckling analyses with uniform thickness of 0.736 inch. Figure lb shows the location of the thinned area in the pie slice model. 2.1 0.536 Inch Thickness Case Figures 2 through 5 show the membrane meridional and circumferential stress distributions from the refueling condition loads. As expected, the tensile circumferentia1 stress (Sx in element coordinate system) and the compressive meridional stress (Sy in element coordinate system) magnitudes in the thinned region are larger than those at the other edge of the model where the thickness is 0.736 inch. However, this is a local effect and the average meridional
'stress and the average circumferential stress is not expected to change significantly.
Figures 6 and 7 show the first buckling mode with the symmetric boundary conditions at both the edges of the model (sym-sym). This mode is clearly associated with the thinned region. The load factor value is 5.562. The second mode with the same boundiry conditions is also associated with the thinned region. Figure 8 shows the buckled shape. The load factor value is 5.872. Next, buckling analyses were conducted with the symmetric boundary conditions specified at the thinned edge and the asymmetric boundary conditions at the other edge (sym-asym).
The load factor of the first mode for this case was 5.58. Figure 9 shows the buckling mode shape. It is clearly associated with the thinned region. Figure 10 shows the buckled mode shape with asymmetric boundary conditions at the both edges (asym-asym).
As expected, the load factor for this case is considerably higher (7.037).
Thus, the load factor value of 5.562 is the Iowest value obtained.
The load factor for the same loading case (refueling condition) with a uniform thickness of 0.736 was 6.141. Thus, the load factor is predicted to change from 6.141 to 5.562 with the postulated thinning to 0.536". 2.2 0.636 Inch Thickness Case Figures 11 through 14 show the membrane meridional and circumferential stress distributions from the refueling condition loads. As expected, the tensile circurnferentiat stress (Sx in element coordinate system) and the compressive meridional stress (Sy in element coordinate system) magnitudes in the thinned region are larger than those at the other edge of the model where the thickness is 0.736 inch. However, this is a Iocal effect and the average meridional stress and the average circumferential stress is not expected to change significantly, Figures 15 and 16 show the first buckling mode with the symmetric boundary conditions at both the edges of the model (sym-sym).
This mode is clearly associated with the thinned region. The load factor value is 5.91. Next, buckling analysis was conducted with the symmetric boundary conditions specified at the thinned edge and the asymmetric boundary conditions at the other edge.
The load factor of the first mode for this case was 5.945. Figure 17 shows the buckling mode shape. It is clearly associated with the thinned region. Based on the results of 0.536" case, the load factor for asym-asym case is expected to be considerably higher. Thus, the load factor value of 5.91 is the Iowest value obtained.
The load factor for the same loading case (refueling condition) with a uniform thickness of 0.736" was 6.141. Thus, the load factor is predicted to change from 6.141 to 5.91 with the postulated thinning to 0.636". , 2.3 Summary The load factors for the postulated 0.536" and 0.636" thinning cases are 5.562 and 5.91, respectively.
These values can be compared to 6.141 obtained for the case with a uniform sandbed thickness of 0.736 inch.
The objective of this task was to determine the change in the drywell buckling margins when the fixity point at the bottom of the sandbed is moved upwards by = 1 foot to simulate placement of concrete. The elements in the sandbed region are approximately 3-inch square. Thus the nodes associated with the bottom four row of elements (nodes 1027 through 1271, Figure 18) were fixed in all directions.
The buckling analyses conducted as a result of mesh refinement indicated that the refueling loading condition is the governing case from the point of view of ASME Code margins. Therefore, the stress and buckling analyses were conducted using the refueling condition loadings.
Figure 19 through 22 show the membrane meridional and circumferential stress distributions from the refueling condition loads. Figure 23 shows the Caicuiated average values of meridional and circumferential stresses that are used in the buckling margin evaluation.
Figure 24 shows the first buckling mode with sym-syrn boundary conditions.
The load factor for this mode is 6.739. The load factor with asym-sym boundary conditions is 6.887 and the mode shape shown in Figure 25. It is clear that the sym-sym boundary condition gives the least load factor. Figure 26 shows the buckling margin calculation.
It is seen that the buckling margin is 5.3% compared to 0% margin in the base case calculation.
To summarize, the load factor changes to 6.739 for the refueling condition when the fixity point at the bottom of the sandbed is moved upwards by margin of 5.3% above that required by the Code. 1 foot. This results in an excess
... . .I . ....... .-. .. .. . ........ ._.I . .- . .. :> ...
-2LL-L OYSTER CREEK DW AWtALYSIS - OCRFTHl (NO SAND, REFUELING)
AMSYS 4.4A1 DEC 9 1992 17:41:51 POST1 STRESS STEP=l ITER-1 MIDOL (EAVG) ELEM CS SMN 1-3561 SMX =7614 OMX =n.zzzn5 XV =1 OIST-718.786 XF 1313.031 ANGZ- - 9 0 CEMTROID HIDDEN YV -0.8 ZF 439.498 m iEEI 5131 6372 7614 -3561 -2319 -1078 163.887 1406 2647 388 9 OYSTER CREEK MJ ANALYSIS - OCRFTHl (MO !WOgD, REFUELING)
AMSYS 4.4A1 DEC 9 1992 17;43:35 POST1 STRESS STEP=l LTER=1 SX (AVG) MIDDLE ELEM CS Dt4X -0.222715 SMW --3561 SMX =7614 HV -1 2v =-1 aDIST*121.539 3XF 046.39 'YF =-1.382 52~ -382.857 APBCZ--SO CENTROID HIDDEN -3561 -2319 -1078 163.887 1406 2647 34389 I v C z b c I c L* p: c c t LBWZ- OEOP- 212s- S6E9- LLSL- 09fU- E8'66-
, ,
EO-39LZ'O EO-32BL'O-868200'0-9S6EQQ. 0 = ~1:OSOO'O-zf0900'0-m ~~100- o- N3QUIH llIOpllQ133 Q 6 - =ZDNV 22*ie59*=
fZcr $S6U9PWO-JAo fStr'ti2-4XP $00'Dlt=,LSI0a 1-5 A2 T= AX SV*OQ*fl=
XMS zL0900*0-=
NWS &t090O'O=
x#a 1tlQOW a 295'S=13VSa T=831I T=d3IS SS3241S TlSOd 2661: 01: 330 xn UT: f s: 9 TW'P SASNQ ecRf ow395 OYSTER CREEK DRYWELL ANALYSIS - (NO SAND, REFUELING)
ANSYS 4.4A1 DEC 10 1992 POST1 STRESS STEP-1 ITER=Z UX D MODAL DMX *0.00643.4 SMld --0.006414 SMX =0.0[12261 a:io:a4 ~~~~~5.872 xv =l ZY =-1 *DfST=lLO.
004 @XF -29.455 @YF 10.4609SQ
@ZF =365.922 ANGZI-90 CENTROID HIDDEN -a. 006ai4 -a. 00545 -a. 003~22 -0.0112558
-0.004486
-0.001598
-0.630E-03 0.333*-03 0.001297 a. ao22si 289F.00 Q TS200'0 s OYSTER CREEK DW AWALYSLS - OCRFOSM (NO SAND, REFUELING)
AMSYS 4.4Al DEC 10 1992 l0:12:22 POST1 STRESS STEP-1 ITER31 FACT-7.037 ux D NODAL DMX 10.003492 SWN --0.0021188 SMX =u. 002164 xv -1 zv =-l *DIST=IlO.OOQ
- XF 029.455 aYF PO. 460954 "ZF a365.922 ANCZ- - 9 0 CENTROID HIDDEN -0.0021388
-0.001615
-0.0011113
-0.670E-03
-0.198E-03 0.274E-03 0.747E 0.001219 0.0016g1 Q.QO2164 1 OYSTER CREEK DEl AfMaLYSIS
= OCRFOGS ~N>&d. REFUELING)
DIST~718.786 2F =C39.498 AMCZn-SO HF =303.03i 1 CENTROID HIDDERI AMSYS 4.4Al 8:18:30 DEC 10 1992 POST1 STRESS STEP-1 ITER=l SX (AVG) MIDDLE ELEM CS DMX PO. 222456 SWN --3554 SMX a6950 4615 5783 6950 U ! n -3554 -2387 -1220 809 1114 2281 3448 8btrE 1822 BITT 608'2s- OZZT- f8EZ- PSSE- U m IE L WSTER CREEK DW BMALYSIS - OCWFOGS (IMO SAND, REFUELING)
ANSYS 4.4A1 8:18:45 DEC ia 1992 POST1 STRESS STEP-l ITER-1 SY (AUG) MIDDLE ELEM CS OMX =0.222456 SHN 9-8767 SHX -694.653 HV =1 YV =-0.8 DIST-718.786 XF -303.031 ZF ~639.498 AMGZ=-911 CENTROID HIDOEN -a767 -7716 -6664 -5613 -4562 -3511 -2459 6SbZ- TIS&- Z9SP- ETSS- 9999- 91Lf- 6918-
ANSYS 4.4A1 DEC 10 1392 10 : 37 : 5 6 POST1 STRESS STEP=l ITER= 1 FACT-5.91 ux 0 NODAL OMX -0.005175 SMX -0.00326 SHN -0.oasi74 OYTER CREEK DRWELL AQjalYSIS - OCRFOGBSS (NO SAND, REFUELING)
... xv =I zv =.I-1 *DIST=100.004
- XF -29.455 *YF =O. 46O¶54 *ZF ~365.922 AMGZ- - 9 0 CEMTROID HIDDEN -0.00Sl.74
-0.004237
-0.01133 -0.002362
-0.001425 0 - 449E-03 -0.4aa~ 0.001386 0.002323 0.00326
i -+9 C # P F 3 OWVER CREEK DRYWELL ANALYSIS - OYCRlS (NO SAND, REFUELIWG)
ANSYS 4.4Al DEC 7 1992 12 : 44: 31 POST1 STRESS STEP=l ITERa.1 SX (AW) MIDDLE ELEM CS D#X =0.211959 SPON --3547 SMX -6041 xv =1 DIST1718.786 ZF t639.498 AMCZ-- 9 0 CENTROID HIDOEM YV -0 .a XF -3113.031.
-3547 -2482 -1416 -350.884 714.437 1980 2845 I OYSTER CREEK ORYWLL AWLVSIS = OYCRlS (NO WPQD, REFUELING)
I AMSYS 4.4A1 DEC 7 1992 12 : 33: 33 POST1 STRESS STEPml ITER= 1 SX (AVG) MIDDLE ELEM cs DMX -0.211959 SMN a-3547 SM% =6041 xv =I LV =-I *DIST-121-539 *XF 046.39 VF a-1.382 *ZF -3132 .as7 ANCZm - 9 0 CENTROID HIDDEN -3547 -2482 -1416 714.437 1780 -350.884 284s - 3910 4976 6041 c. 4 0 TbT2- O'EIE- 6f OP- 6PQS- 8109- L869- BStiL- U m OYSTER CREEK DRYWELL AMLYSIS - OYCRlS IN0 SAND. REFUELING1 AMSYS 4.4A1 DEC 7 1992 12 :34: 18 POST1 STRESS STEP-1 ITER=l SY (AVG) MIDDLE ELEM CS RWX -0.211959 SMM -.-7956 SMX 5766.953 xv -1 zv =-I *DIST=121-539 *XF ~46.39 *YF 0-1.382 @ZF ~382.857 ANCZ--90 CENTROID HIDDEN " 0 \ -7956 -6987 -6018 -5049 -4079 -3110 n -2141 -1172 -202.3U1
- 766.953 APPLIED MERIDIONAL AH0 CIRCUHFEREHllAL STRESSES - REFUELING CCNOlTION ONE FOOT IMCREASE !N FIXITY CASE; STRESS RUN: 0CRFRLSB.CUT AVERAGE APPLIED MERIDIONAL STRESS: The average meridional stress is defined as the average stress across the elevation inctuding nodes 1419 through 1467. Stresses at nodes 1419 and 1467 are weighted only one half as nuch as the ather nodes because they Lie on the edge of the mcdeLed l/lOth section of the drywelt and thus represent only 1/2 of the area represented by the other nodes. Nodes ..--. 1419-1667 1 423 - 1 663 1427-1659 1431
- 1455 3435.145 1 7439- 1447 1443 _____ Total: # of Meridional Nodes Stress (ksi) ....................
1 -7.726 2 -7.?38 2 -7.760 2 -7.682 2 s7.394 2 -7.011 1 -6.831 ---I. 12 Average Heridionel Stress: # of Nodes Meridional Stress (ksi) X ...............
-7.726 -15.476 -15.520 -15.364 -14.788 -16.028 -6.834 -89.736 12 ...............
...............
-7.478 tksi) AVE3AGE APPLIED CIRCUMFERENTIAL STRESS: The circmferential stress is averaged along the vertical line frem node 1223 to ncde 2058. Modes ___._ 1223 1419 1615 181 1 2058 Total: # of Nodes --.-- 0 1 1 1 1 4 ..... Average Circunferential Stress: # of Nodes Ci rcumferentiel Stress (ksi) X 0.000 0.505 4.165 5.866 5.024 15-54 4 ...............
...............
3.W (ksi) OCRFSTOL.UK1 OYSTER CREEK ORYWELL ANALYSIS - ocrfs-s (NO SAND, REFUELING)
ANSYS 4.4A1 6:15:38 DEC 8 1992 POST1 STRESS STEP= 1 I TER= 1 FACT=6.739 ux D NQDGL DMX =0.003681 SMN =-0,00368 SMX =0.001848 xv =t zu =-I ~DZST=l10,004 wXF =29.455 *YF =O .46O954 wZF =365,922 ANGZ=-F)O CENTROID HIDOEN -0 00368 -0.003065
-0.00 1837 -0.00 1223 -0,609E-03 0.567E-05
-0 , a02451 - 0,620E-03 0.001 234 0.001848 ANSYS 4.4A1 DEC 9 1992 I1 :35 :17 POSTl STRESS STEP-I. ITER=1 FACT-6.887 ux D NODAL DMX =OIOO!i136 SMN =-0.005134 St4X =O. 003244 xv -1 zv --1 3DIST=110.004 WF -29.455 VF =O. 46O954 92F -365.922 MGZ= - 9 0 CENTROID HIODEW -0.005134
-0.003273
-0.002342
-1.480E-03 -a. 004203 -a. oamii 0.451E-03 4 , . i " 0.001382 a. 003244 O.OO2313 CALCUUTION OF ALLOWABLE BUCKLING STRESSES - REFUELING CASE, NO SAND ONE FOOT INCREASE IN FIXITY CASE; STRESS RUN OCRFRLSB.OUT, BUCKLING RUN 0YCRSBBK.OUT LOAD ITEM PAHAMETER UNITS VALUE FACTOR I----- ................................................
------- ------ *** DRYWELL GEOMETRY AND MATERIALS 1 Sphere Radius, R 2 Sphere Thickness, t 3 Material Yield Strength, Sy 4 Material Modulus of Elasticity, E 5 Factor of Safety, FS (in.) 420 (in.) 0.736 (ksi) 38 (ksi) 29600 2 - *** BUCKLING ANALYSIS RESULTS 6 Theoretical Elastic Instability Stress, Ste (ksi) 50.394 6.739 +** STRESS ANALYSIS RESULTS 7 Applied Meridional Compressive Stress, sm (ksi) 7.478 8 Applied Circumferential Tensile Stress, Sc (ksi) 3.885 *** CAPACITY REDUCTION FACTOR CALCULATION 9 Capacity Reduction Factor, ALPHAi - 0.207 10 Circumferential Stress Equivalent Pressure, Peq (psi) 13.616 11 'XI Parameter, X= (Peq/4E) (d/t)"2 ... 0.075 12 Delta C (From Figure - ) - 0.064 13 Modified Capacity Reduction Factor, ALPHA,i,mod - 0.313 14 Reduced Elastic Instability Stress, Se (ksi) 15.753 2.107 *** PLASTICITY REDUCTION FACTOR CALCULATION 15 Yield Stress Ratio, DELTA=Se/Sy - 0.415 17 Inelastic Instability Stress, Si. = NUi x Se (ksi) 15.753 2.107 16 Plasticity Reduction Factor, NUi - 1.000 *** ALLOWABLE COMPRESSIVE STRESS CALCULATION 18 Allowable Compressive Stress, Sal1 = Si/FS (ksi) 7.877 1.053 19 Compressive Stress Margin, M=(Sall/Sm
-1) x 100% (%I 5.3 4 k REFNSND2 .WK1