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Category:Report
MONTHYEARML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML21036A1692021-01-29029 January 2021 ISFSI Only Security Plan, Training Qualification Plan, Safeguards Contingency Plan Supplemental Information ML20153A2282020-05-29029 May 2020 Biological Opinion for Oyster Creek Shutdown and Decommissioning ML19214A0452019-08-0202 August 2019 NRC to NMFS, Revised Proposed Action for Oyster Creek Endangered Species Act Section 7 Consultation ML19029B3332019-01-29029 January 2019 Security Inspection Plan for Oyster Creek Station - 2019 RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018 Secondary Containment Capability Test ML18033B7442018-02-21021 February 2018 Staff Assessment of the Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation RA-17-032, Submittal of Biennial 10 CFR 50.59 and 1 O CFR 72.48 Change Summary Reports - January 1, 2015 Through December 31, 20162017-05-16016 May 2017 Submittal of Biennial 10 CFR 50.59 and 1 O CFR 72.48 Change Summary Reports - January 1, 2015 Through December 31, 2016 ML15350A3532016-02-17017 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force... RA-15-042, Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 20142015-05-26026 May 2015 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 2014 ML15093A2842015-02-23023 February 2015 Enclosure 2: Flood Hazard Reevaluation Report for Oyster Creek Nuclear Generating Station, Rev. 1 RA-14-078, Secondary Containment Capability Test2014-10-24024 October 2014 Secondary Containment Capability Test RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 RA-14-068, Sea Turtle Incidental Take Report 2014-32014-08-0101 August 2014 Sea Turtle Incidental Take Report 2014-3 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14065A2322014-06-16016 June 2014 Staff Assessment of Response to Enclosure 4 of the March 12, 2012, 10 CFR 50.54(F) Information Request - Flooding Walkdowns ML14030A5132014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14038A1112014-02-11011 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Oyster Creek Nuclear Generating Station, TAC No.: MF0824 NEI 99-04, Oyster Creek Nuclear Generating Station, Commitment Change Summary Report - 20122013-12-23023 December 2013 Oyster Creek Nuclear Generating Station, Commitment Change Summary Report - 2012 RA-13-127, Commitment Change Summary Report - 20122013-12-23023 December 2013 Commitment Change Summary Report - 2012 RA-13-088, Sea Turtle Incidental Take Report 2013-52013-09-0909 September 2013 Sea Turtle Incidental Take Report 2013-5 RA-13-074, Sea Turtle Incidental Take Reports 2013-1 and 2013-22013-08-0909 August 2013 Sea Turtle Incidental Take Reports 2013-1 and 2013-2 ML15093A2832013-07-0303 July 2013 Enclosure 1: Local Intense Precipitation Evaluation Report for Oyster Creek, Rev. 6 RS-12-177, E Plan for Future Seismic Walkdown of Inaccessible Equipment2013-04-26026 April 2013 E Plan for Future Seismic Walkdown of Inaccessible Equipment ML13120A1862013-04-0909 April 2013 Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal # 1 for the Oyster Creek Generating Station Correspondence No. RS- ML13098A2092013-04-0505 April 2013 2.206 Petition by New Jersey Environmental Federation (Et.Al.) for Oyster Creek Nuclear Generating Station Exelon Generation Company, LLC IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12355A1422012-12-31031 December 2012 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 1 of 2 RS-12-217, 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 2 of 22012-12-31031 December 2012 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 2 of 2 RS-12-217, 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 1 of 22012-12-31031 December 2012 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 1 of 2 RA-12-117, Company, Llc'S 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-19019 November 2012 Company, Llc'S 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12359A0082012-11-0606 November 2012 Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 1 of 4 ML12359A0062012-11-0606 November 2012 Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 3 of 4 ML12359A0052012-11-0606 November 2012 Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 2 of 4 RS-13-065, Core Spray/Auto Depress'N System Relay Logic Panel2012-10-10010 October 2012 Core Spray/Auto Depress'N System Relay Logic Panel RA-13-022, D Area Walk-By Checklists (Awcs)2012-10-10010 October 2012 D Area Walk-By Checklists (Awcs) ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. 2023-10-13
[Table view] Category:Technical
MONTHYEARML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML21036A1692021-01-29029 January 2021 ISFSI Only Security Plan, Training Qualification Plan, Safeguards Contingency Plan Supplemental Information ML20153A2282020-05-29029 May 2020 Biological Opinion for Oyster Creek Shutdown and Decommissioning ML19214A0452019-08-0202 August 2019 NRC to NMFS, Revised Proposed Action for Oyster Creek Endangered Species Act Section 7 Consultation RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018 Secondary Containment Capability Test ML15093A2842015-02-23023 February 2015 Enclosure 2: Flood Hazard Reevaluation Report for Oyster Creek Nuclear Generating Station, Rev. 1 RA-14-078, Secondary Containment Capability Test2014-10-24024 October 2014 Secondary Containment Capability Test RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14030A5132014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14038A1112014-02-11011 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Oyster Creek Nuclear Generating Station, TAC No.: MF0824 ML15093A2832013-07-0303 July 2013 Enclosure 1: Local Intense Precipitation Evaluation Report for Oyster Creek, Rev. 6 RS-12-177, E Plan for Future Seismic Walkdown of Inaccessible Equipment2013-04-26026 April 2013 E Plan for Future Seismic Walkdown of Inaccessible Equipment ML13120A1862013-04-0909 April 2013 Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal # 1 for the Oyster Creek Generating Station Correspondence No. RS- ML12355A1422012-12-31031 December 2012 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 1 of 2 RS-12-217, 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 2 of 22012-12-31031 December 2012 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 2 of 2 RS-12-217, 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 1 of 22012-12-31031 December 2012 2012 Oyster Creek Nuclear Generating Station Emergency Planning Zone Evacuation Time Estimates Analysis. Part 1 of 2 RA-12-117, Company, Llc'S 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-19019 November 2012 Company, Llc'S 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12359A0082012-11-0606 November 2012 Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 1 of 4 ML12359A0062012-11-0606 November 2012 Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 3 of 4 ML12359A0052012-11-0606 November 2012 Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 2 of 4 RA-13-022, D Area Walk-By Checklists (Awcs)2012-10-10010 October 2012 D Area Walk-By Checklists (Awcs) RS-13-065, Core Spray/Auto Depress'N System Relay Logic Panel2012-10-10010 October 2012 Core Spray/Auto Depress'N System Relay Logic Panel ML1016001862010-06-23023 June 2010 Final ASP Analysis - Oyster Creek ML1007004922010-02-24024 February 2010 Reportable Event Rad 1.34, Rev. 10 ML1007004932010-02-24024 February 2010 Reportable Event Rad 1.4, Rev. 10 ML1007401482010-02-24024 February 2010 Attachment 9 Micro ALARA Plan Work Sheet, Rev. 9 ML1020204192009-06-0505 June 2009 Root Cause Evaluation Report for Tritium Leak at Oyster Creek ML1020203322009-05-20020 May 2009 Gamma Spectrum Analysis ML1020203632009-05-20020 May 2009 Gamma Spectrum Analysis ML1020203642009-05-20020 May 2009 Gamma Spectrum Analysis ML1020203282009-05-0707 May 2009 Gamma Spectrum Analysis ML1020203272009-05-0707 May 2009 Gamma Spectrum Analysis ML1020203262009-05-0707 May 2009 Gamma Spectrum Analysis ML1020203252009-05-0707 May 2009 Issue Entry, Oc ML1020203292009-05-0707 May 2009 Gamma Spectrum Analysis ML1020203242009-05-0101 May 2009 AR 00914559 Report ML1007401592009-04-28028 April 2009 Report of Analysis/Certificate of Conformance, L38101 ML1020203232009-04-27027 April 2009 Gamma Spectrum Analysis ML1020004662009-04-26026 April 2009 Gamma Spectrum Analysis ML1020004622009-04-25025 April 2009 Gamma Spectrum Analysis Oyster Creek ML1020004652009-04-25025 April 2009 Gamma Spectrum Analysis ML1020004642009-04-25025 April 2009 Gamma Spectrum Analysis Oyster Creek ML1020004632009-04-25025 April 2009 Gamma Spectrum Analysis Oyster Creek ML1020004592009-04-25025 April 2009 Gamma Spectrum Analysis Oyster Creek ML1020004602009-04-25025 April 2009 Gamma Spectrum Analysis Oyster Creek ML0910407272009-04-0606 April 2009 Document No. 17693-R-001, Revision 0, NJDEP Oyster Creek Drywell Review ML1007401572009-03-24024 March 2009 Report of Analysis/Certificate of Conformance, L38010 ML1007401582009-03-24024 March 2009 Report of Analysis/Certificate of Conformance, L38009 ML1007401542009-03-22022 March 2009 Report of Analysis/Certificate of Conformance, L37854 2023-10-13
[Table view] |
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EVALUATION NBR: 05 ORIG DATE ASSIGNED:
EVALUATING ORG : OERT EVAL DUE DATE: 260CT06 EVAL ASIGND TO: MARKOS/KESTER DATE ASSIGNED: 250CT06 EVAL REQUEST ORG: OERT EVAL REQUESTOR: MARKOS,S EVAL STATUS : ASIGND EVAL RETURNED BY:
IMPORTANCE C 0 D E : L 0EAP:- SCHEDULE CODE : DATE FIIXED:~
EVAL DESC: TECHNICAL BASIS FOR AWA FOR ECR 06-00879 THE CAVEATS LISTED IN THE FOLLOWING TECHNICAL EVALUATION PRKl 250CT06 MUST BE CAPTURED IN THE PLANNED WORK PACKAGE WITH PRKl 250CT06 APPROPRIATE SIGNOFFS. OV HOLD POINTS ARE REOUIRED. THE PRKl 250CT06 SCOPE OF THIS TECHNICAL EVALUATION IS NUCLEAR SAFETY PRKl 250CT06 RELATED. PRKl 250CT06 PRKl 250CT06
- HIS TECHNICAL EVALUATION IS PERFORMED IN ACCORDANCE WITH PRKl 250CT06 PROCEDURE CC-AA-309-101. PRKl 250CT06 A PRE-JOB BRIEF HAS BEEN CONDUCTED IAW KU-AA-1212. THIS PRKl 250CT06 TECHNICAL EVALUATION WAS SCREENED AGAINST HU-AA-1212AND PRKl 250CT06 DETERMINED TO BE MEDIUM CONSEQUENCE AND RISK RANKED A 4. PRKl 250CT06 ACCORDINGLY, EXISTING PROCESS REVIEW IS ACCEPTABLE AND NO PRKl 250CT06 THIRD PARTY REVIEW IS REQUIRED. PRKl 250CT06 ,
PRKl 250CT06 SCOPE AND REASONS FOR EVALUATION: PRKl 250CT06 PRKl 250CT06 THIS TECHNICAL EVALUATION PROVIDES THE TECHNICAL BASIS PRKl 250CT06 FOR THE ADVANCED WORK AUTHORIZATION ASSOCIATED WITH ECR PRKl 250CT06 0 6 - 0 0 8 7 9 FOR CAULKING THE JOINT AT THE OUTBOARD PERIMETER PRKl 250CT06 OF THE ELEV. 10'-3" DRYWELL CONCRETE SLAB CURB AND THE PRKl 250CT06 DRYWELL STEEL SHELL. THE EVALUATION WILL EXAMINE THE PRKl 250CT06 IMPACT OF THE ADDITION OF THE PROPOSED CAULKING ON THE PRKl 250CT06 DESIGN BASIS ANALYSIS (REFERENCE 2) FOR SUCTION STRAINER PRKl 250CT06 DEBRIS GENERATION AND TRANSPORT. THIS SCOPE OF THIS PRKl 250CT06 TECHNICAL EVALUATION IS LIMITED TO PROVIDING THE PRKl 250CT06 TECHNICAL BASIS FOR AWA AND SHALL NOT BE USED FOR PRKl 250CT06 TURNOVER TO OPERATION. PRKl 250CT06 PRKl 250CT06 DETAILED EVALUATION: PRKl 250CT06 PRKl 250CT06 AT THE OUTBOARD PERIMETER OF THE ELEV. 10'-3" DRYWELL PRKl 250CT06 FLOOR, THE CONCRETE SLAB MEETS THE DRYWELL SHELL, THIS PRKl 250CT06 INTERFACE HAS BEEN PREPARED FOR CAULKING UNDER AWA #3. PRKl 250CT06 THE SCOPE OF THIS AWA IS TO APPLY THE CAULK TO THE JOINT. PRKl 250CT06 THE CAULK WILL LAP ONTO THE CONCRETE AND STEEL SURFACES PRKl 250CT06 BY 1/4" TO 1" ON EACH SURFACE. THE APPLICATION OF THE PRKl 250CT06 CAULK WILL MINIMIZE WATER SEEPAGE THROUGH THE SUBJECT PRKl 250CT06 JOINT. PRKl 250CT06 PRKl 250CT06 THE COMPUTED AMOUNT OF THE REQUIRED CAULKING MATERIAL IS PRKl 250CT06 ABOUT 830 OZ, WHICH IS ABOUT 81 LBS OF THIOKOL 2235M BY PRKl 250CT06 POLYSPEC, OUALIFIED MATERIAL FOR INSIDE DRYWELL PRKl 250CT06
- ACTION REQUEST *** PAGE: 02 A/R TYPE : CM ECR A/R NUMBER : A2152754 REQUEST ORG : OED A/R STATUS : ASIGND REQUEST DATE: 210CT06 STATUS DATE: 250CT06 REQUESTED BY: TAMBURRO LAST UPDATE: 270CT06 I PRINT DATE : 270CT06
- ACTION REQUEST *** PAGE : 03 A/R TYPE : CM ECR A/R NUMBER : A2152754 REQUEST ORG : OED A/R STATUS : ASIGND REQUEST DATE: 210CT06 STATUS DATE: 250CT06 REQUESTED BY: TAMBURRO LAST UPDATE: 270CT06 PRINT DATE : 270CT06
The following calculation is estimate for the volume and weight of caulk applied around the perimeter of the drywell at the concrete slab / steel shell interface.
Iupper curb provide sealant at concrete/ drywell shell junction (Detail 1)
Curb around perimeter of Drywell floor see ,
sections b Floor Elevation 10'-3. I smslmAu o.rlnuurd.(.l Dia := 49.R approximate diameter at concrete/shell interface at upper curb h3Vd Length1 := Length1 = 153.9fi circumference Length2 := 2-10-(12.254 - 11.00-ft) ~ e n =~25 fi 2 summation of vertical lengths from lower curb to upper curb Lengthtotal := Length1 + Length;! Len&od = 178.9ft Using a caulk bead 1" high and a gap equal to 0.3"(approximate gap due to deterioration at the corner of the concrete slab) and caulk extending 1" horizontally beyond the gap (see Detail 1).
Use two triangular areas to approximate area of caulk t
-74I d Area :=& )
2 - d
+ (0.3.in).(0.3-h) 2 kea=/ ,439 y := 12.5.- Ibf density of sealant per vendor e-mail gal Weight := Volume-y weight $1, ~4
Data Pack K Issued November 7998 1502324320
,426275&-05 CtjldEidr z)\ / I Fire stop 3-6548 silicone RTV foam
/
~
Data Sheet RS stock numbers 779-037 and 779-043 Introduction Specifications 3-6548 silicone RTV foam is specially formulated to Has been blast tested in various seal configurations have fire resistant properties coupled with good and has been shown able to withstand explosive over flexibility under the most demanding conditions. It's pressures of up to 148kN/mzdepending on seal most effective when used to seal gaps and holes of all design.
sizes through which cables, wires, ductwork and It successfully passes many fire sealing tests.
'piping pass. Whilst it has been made to withstand high including:
temperatures and confine such hazards as smoke, fire 0 Factory Mutual Test ASTM E-I 19 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rating and gases, it can also be used to seal buildings and rooms from other damaging contaminants like dirt, 0 BS 476 (part 8 - 1972) - 1 through 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> rating dust and water. 0 Mobil hydrocarbon curve - 1 through 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A two-part product supplied in liquid A and B rating components in one unit, can be easily mixed on-site, 0 NePia (Nuclear Energy Liability Insurance expanding rapidly to surround and completely seal off Association) - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rating cables, conduits or piping within only minutes of being 0 Lloyd's Register of Shipping for Class A bulkheads, applied. for piping, and Class H bulkheads for cable trays and piping - 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> rating 0 UL (Underwriters Laboratory) rating per Typical properties ASTM E-814.2and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Below are properties of hand mixed equal parts of part 0 Swedish National Authority for testing (Statens A and B at 25°C. Provningsanstalt) - 1, 1 % and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ratings Working time Densltv I 1.O-2.0 min 14.0-20.0Ib/W I 0 SINTEF - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rating 0 CSTB - 3% hours rating.
3-6548 RTV foam is approved to meet the Benefits requirements for use in the construction of nuclear 0 Up to 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> fire-rating can be achieved power plants and their safety control systems.It is a FM 0 Forms an airtight seal - prevents spread of smoke, and UL-classified material. (Factory Mutual Serial No.
water and other liquid or gaseous contaminants 26543 from DC Corporation and UL 10 B.)
0 Fast foaming - liquid foams and expands rapidly to Other ratings include HF-I according to UL 94 and a fill any size or shape of penetration Class I flame spread by ASTM E84.
0 Easy to repair - can be removed and replaced at will for changes or repair. Excellent adhesion to itself 0 Long lasting thermoset cure elastomer does not melt or soften at high temperature and has excellent UV and weathering resistance.
%ical Properties Typical properties of the LDSE can be found in the table to the right.
Fire Qualification Numerous full-scale fire tests have been successfully performed at nationally recognized, independent and accredited laboratories for various seal configurations including electrical and mechanical elements in large complex block out openings, gaining major insurance company and regulatory body acceptance.
Seal designs have been qualified both with and without permanent damming materials.
Pressure Testing Differential testing for electrical block out and mechanical penetrations with this design indicate a 20-psi pressure resistance with zero leakage using a four-inch depth of LDSE. Other configurations may vary with regard to pressure resistance.
Radiation Resistance LDSE has been subjected to substantial radiation exposure levels (2 x lo* Rads Gamma) with no significant changes reported to the material's physical properties.
Reparability LDSE can be selectively removed with relative ease using blunt non-conductive tools and devices.
Additions or deletions of elements can be easily accomplished, and new LDSE material can then be applied to previously cured material to become an integral matrix with the already installed LDSE.
Decontaminability Surface can easily be decontaminated.
Cure Time As indicated in the table above the cure time for the fast curing version is as little as 10 minutes, whereas the cure time for the regular cure is as long as 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. By special request, custom cure times can be formulated.
Packaging I DESCRIPTION NET WEIGHT CONTAINER AVG. SEAL VOLUME LDSE A 8 B Set 60 Lbs. 2 ea. 5 gal. (Set) 1.0 cu. Ft.
~~
Page 14
Kester. Paul R.
From: Cheryl Gilbert [cgilbert@polyspec.com] I Sent: Wednesday, October 25,2006 9:25 AM To: jrcpe@aol.com
Subject:
/ Thiokol2235M
- John, The density of the Thiokol 2235M is 12.5 lbs./gal.
Sorry for the delay.
Cheryl Gilbert Customer Service Manager PolySpec, L P .
6614 Gant Road Houston, TX 77066 ,
Tel: 281-397-0033 F a : 281-397-6512 Email: cgilbert@polyspec.com Legal Notice Any recommendation or suggestion relating to the use of the products made by PolySpec, whether in its technical literature, or in response to specific inquiry, or otherwise, is based on data believed to be reliable; however, the products and information are intended for use by Buyers having requisite skill and know-how in the industry, and therefore it is for the Buyer to satisfy itself of the suitability of the products for its own particular use, and it shall be deemed that Buyer has done so, at its sole discretion and risk.
Variation in environment, changes in procedures of use, or extrapolation of data may cause unsatisfactory results. PolySpec warrants its products to be free from defects in material and workmanship. PolySpec makes no other warranties concerning this product. NO other warranties, either express or implied, or statutory, such as warranties of merchantability or fitness for a particular purpose, shall apply.
1
P A2 152754-05, ATTACHMENT 5, PAGE 1 OF 3 October 25, 2006 CORROSION
/ CONTROL CONSULTANTS AND IABS, INC.
Howie Ray Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC Forked River, NJ Transmitted Electronically EVALUATION OF POLYSPEC/THIOKOL 2235M INDUSTRIAL POLYSULFIDE JOINT SEALANT FOR USE IN THE DRYWELL OF THE OYSTER CREEK NUCLEAR GENERATING STATION This letter report has been prepared at your request to provide my independent opinion concerning the suitability of PolyspecKhiokol2235M Industrial Polysulfide Sealant for use in the Oyster Creek Nuclear Generating Station (hereinafter Oyster Creek)
Drywell. My work on this effort is in accordance with your Contract No. 01003193 dated May 30,2006.
GENERAL INFORMATION As part of the Technical Evaluation associated with A2152754 ECR06-00879, I was asked to recommend a caulking material suitable for application to the drywell shell to concrete interface at Elevation 10. The recommended caulking must be suitable for the normal and accident environment in the Oyster Creek drywell and comply with the Oyster Creek licensing basis.
BASIS OF MY OPINIONS To form my opinions, I reviewed the following References concerning PolyspecKhiokol2235M Industrial Polysulfide Sealant:
- 1. Polyspec Thiokol2235M Technical Data Sheet
- 2. Polyspec Tliiokol2235M Material Safety Data Sheets (MSDS) (part A)
- 3. Polyspec Thiokol2235M Material Safety Data Sheets (MSDS) (part B) 1
A2152754-05,AlTACHMENT 5, PAGE 2 OF 3
- 4. Korea Atomic Energy Research Institute Certificate of Radiation qrocessing dated July 7, 1994
- 5. Thiokol TD-569N 5/69, Radiation Resistance of LP Liquid Polysulfide Polymer Based Compounds
- 6. Engineering Paper No. 893, The Effect of Nuclear radiation on Sealants
- 7. NSF International Letter dated November 20, 1997 with NSF Test Report concerning Thiokol2235-M
- 8. NSFIANSI 61-05 with Addendum 1.0 (2005) I
- 9. Environmental Parameters - Oyster Creek NGS (ES-027 Rev. 4)Tables 1 ,
and 2 GENERAL DESCRIPTIONS OF POLYSPEC/THIOKOL 2235111 INDUSTRIAL POLYSULFIDE SEALANT.
Thiokol2235M Industrial Polysulfide Joint Sealant, manufactured by Polyspec, is a high-performance, non-sag, NSF approved chemical resistant elastomericjoint sealant (Reference 1). Thiokol2235M is not soluble in water and is suitable for use in critical services such as drinking water (NSF approved) and jet fuel.
Based upon the NSF testing per Reference 10 of PolyspecKhiokol2235M Industrial Polysulfide Sealant for drinking water service (Reference 7), no leachable ionic species or chemicals in unacceptable quantities would be expected to be released from the PolyspedThiokol2235M Industrial Polysulfide Sealant if in service in the Oyster Creek drywell.
According to References 1,2 and 3, Polyspec/Thiokol2235M Industrial Polysulfide Sealant contains no solvents and, as such, will not chemically contaminate the Oyster Creek charcoal filters during application and cure.
I investigated the use of Polyspec!l%iokol2235M Industrial Polysulfide Sealant in similar applications as that proposed for Oyster Creek at nuclear power plants in the United States and overseas. This sealant is approved for use comparable to that proposed for Oyster Creek at a number of commercial nuclear power plants, including Peach Bottom (Exelon), Turkey Point 3&4 (FPL), St. Lucie 1 & 2 (FPL), Oconee 1,2 8z 3 (Duke), Catawba 1 & 2 (Duke), McGuire 1&2 (Duke), and Wolsong 1-6 (KHNP).
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A2 152754-05, AlTACHMENT 5, PAGE 3 OF 3 I
IRRADIATION AND PHYSICAL PROPERTIES REOUIREMENTS Reference 4 indicates that PolyspeclThiokol2235M Industrial Polysulfide Sealant was irradiation tested at 0.5 M R A D h (average) to a total absorbed dose of 200 MRAD (2E8 RADS), which envelopes the anticipated remaining plant life radiation exposure at I
the drywell shell to concrete interface at Elevation 10' (Reference 9).
I Reference 5, which contains information concerning the base polysulfide resin used in the formulation of Polyspec/Thiokol2235M Industrial Polysulfide Sealant, indicates that the physical properties of the sealant (particularly tensile strength and elongation) will be satisfactory after irradiation to a total absorbed dose of 1E$, which also envelopes the anticipated remaining plant life radiation exposure at the drywell shell to concrete interface at Elevation 10'.
I According to Thiolcol, the formulator of Polyspec/Thiokol2235M Industrial Polysulfide Sealant, the cured polysulfide polymer in Polyspec/Thiokol2235M Industrial Polysulfide Sealant exhibits acceptable mechanical properties after exposure to 250 deg F for one week (Reference 5). As such, the Polyspec/Thiokol2235M Industrial Polysulfide Sealant is acceptable for use on the drywell shell to concrete interface at Elevation 10'.
CONCLUSIONS It is my independent opinion that Polyspec/Thiokol2235M Industrial Polysulfide Sealant is suitable for application to the drywell shell to concrete interface at Elevation 10'.
Should you require additional information, please contact me.
Jon R Cavallo, PE, PCS Vice President 3