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Category:Drawing
MONTHYEARML1014705942010-05-25025 May 2010 Yard Diagram Showing Sample Points and Sample Results at Dresden ML1014705962010-05-25025 May 2010 Diagram of the CSTs in Relation to the Reactor Building and the Locations of the Storm Drains at Dresden SVPLTR 09-0045, Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows2009-10-0202 October 2009 Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows ML1017501172009-06-0808 June 2009 Email from C. Phillips to M. Ring and Others Dresden Station Diagram W/Attachment Site Diagram ML1015505552009-06-0606 June 2009 Drawing - Dresden Csts, Clean Demin Tank and Well Water Tank ML1017501152009-06-0505 June 2009 Email from C. Phillips to M. Ring and Others Potential Dresden Tritium Leak W/ Attachment ML0614501052006-05-12012 May 2006 Drawing, Dresden Sample Points ML0614501102006-05-12012 May 2006 Drawing, Dresden Ground Water Monitoring Wells Trending RS-03-001, RAI 2.1.1- Supplemental Information Request Boundary Diagrams - Dresden Units 2 & 3 - 3rd Drawing2003-01-0303 January 2003 RAI 2.1.1- Supplemental Information Request Boundary Diagrams - Dresden Units 2 & 3 - 3rd Drawing ML0226107092002-09-0606 September 2002 Fourth Interval Inservice Inspection Program Plan, Attachment C ML17252B5771978-04-14014 April 1978 Drawing 12E2079, Rev. AC, Elec. Installation Reactor Bldg. El. 545'-6 North. ML17252B5781977-06-0606 June 1977 Drawing 12E2161, Rev. AD, Instrument System Control Room-Plan. ML17252B5751977-04-14014 April 1977 Drawing 4E-6508, Rev. C, Electrical Installation Air-Seals and Fire-Stops Quad-Cities Station Units 1-2. ML17252B5761977-04-14014 April 1977 Drawing 4E-6508A, Rev. a, Electrical Installation Air-Seals and Fire-Stops Quad-Cities Station Units 1 and 2. ML17252B5791977-03-16016 March 1977 Drawing 12E6508, Rev. C, Electrical Installation Air-Seals and Fire-Stops Dresden Nuclear Station. ML17252B5801977-03-16016 March 1977 Drawing 12E6508A, Rev. a, Electrical Installation Air-Seals and Fire-Stops Dresden Nuclear Power Station. ML17252B5811975-09-0303 September 1975 Drawing 22E03130, Rev. a, Electrical Installation Air Seals and Fire Stops Zion Station Units 1 and 2. ML17252A9541973-08-16016 August 1973 Letter Regarding Inspection of Bergen-Patterson Hydraulic Shock Suppressor at Dresden Nuclear Power Station Unit 3 ML17252B5831967-09-19019 September 1967 Drawing 94D98OIED745 ML17252B5821967-08-22022 August 1967 Drawing 75C242679, Rev. 1, Turbine Bldg, MOC #25-1. 2010-05-25
[Table view] Category:Letter type:SVPLTR
MONTHYEARSVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 SVPLTR 23-0004, Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities2023-02-10010 February 2023 Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities SVPLTR 22-0037, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2022-09-0707 September 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 22-0024, Registration of Use of Casks to Store Spent Fuel2022-06-16016 June 2022 Registration of Use of Casks to Store Spent Fuel SVPLTR 22-0016, Unit 3, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 2 and Unit 3 Shroud Vertical Welds2022-06-0808 June 2022 Unit 3, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 2 and Unit 3 Shroud Vertical Welds SVPLTR 22-0017, Registration of Use of Casks to Store Spent Fuel2022-05-25025 May 2022 Registration of Use of Casks to Store Spent Fuel SVPLTR 21-0061, Core Operating Limits Report for Dresden Unit 2 Cycle 282021-11-19019 November 2021 Core Operating Limits Report for Dresden Unit 2 Cycle 28 SVPLTR 21-0057, Submittal of 10 CFR 72.48 Evaluation Summary Report2021-10-15015 October 2021 Submittal of 10 CFR 72.48 Evaluation Summary Report SVPLTR 21-0030, Registration of Use of Casks to Store Spent Fuel2021-06-0202 June 2021 Registration of Use of Casks to Store Spent Fuel SVPLTR 21-0028, 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 2020 Annual Radiological Environmental Operating Report SVPLTR 21-0027, Radioactive Effluent Release Report and Offsite Dose Calculation Manual2021-04-22022 April 2021 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 21-0005, Submittal of Analytical Evaluation of Isolation Condenser Nozzle to Shell Weld Flaw Indications (ISI Weld 3/2/1302A-12/12-8)2021-01-29029 January 2021 Submittal of Analytical Evaluation of Isolation Condenser Nozzle to Shell Weld Flaw Indications (ISI Weld 3/2/1302A-12/12-8) SVPLTR 20-0053, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 3 Top Guide Rim Weld2020-10-15015 October 2020 Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 3 Top Guide Rim Weld SVPLTR 20-0045, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-09-0101 September 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 20-0037, Response to Apparent Violation in NRC Inspection Report 05000237/2020012 and 05000249/2020012; EA-20-0532020-07-0202 July 2020 Response to Apparent Violation in NRC Inspection Report 05000237/2020012 and 05000249/2020012; EA-20-053 SVPLTR 20-0027, Registration of Use of Casks to Store Spent Fuel2020-05-14014 May 2020 Registration of Use of Casks to Store Spent Fuel SVPLTR 20-0014, Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2020-04-21021 April 2020 Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 20-0010, Fifth 10-Year Interval 2019 Refueling Outage Activities2020-02-13013 February 2020 Fifth 10-Year Interval 2019 Refueling Outage Activities SVPLTR 19-0049, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-09-10010 September 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 19-0031, Registration of Use of Casks to Store Spent Fuel2019-06-14014 June 2019 Registration of Use of Casks to Store Spent Fuel SVPLTR 19-0020, Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2019-04-19019 April 2019 Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 19-0005, Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities2019-02-0808 February 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities SVPLTR 18-0025, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-08-15015 August 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 18-0020, Corrected 2017 Radioactive Effluent Release Report2018-06-28028 June 2018 Corrected 2017 Radioactive Effluent Release Report SVPLTR 18-0018, Registration of Use of Casks to Store Spent Fuel2018-06-14014 June 2018 Registration of Use of Casks to Store Spent Fuel SVPLTR 18-0012, Submittal of 2017 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2018-04-24024 April 2018 Submittal of 2017 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 18-0007, Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revisions 17 and 182018-03-0101 March 2018 Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revisions 17 and 18 SVPLTR 17-0033, Submittal of Corrected 2016 Radioactive Effluent Release Report for January Through December2017-08-29029 August 2017 Submittal of Corrected 2016 Radioactive Effluent Release Report for January Through December SVPLTR 17-0026, Registration of Use of Casks to Store Spent Fuel2017-06-0606 June 2017 Registration of Use of Casks to Store Spent Fuel SVPLTR 17-0017, Submittal of 2016 Radioactive Effluent Release Report2017-04-26026 April 2017 Submittal of 2016 Radioactive Effluent Release Report SVPLTR 16-0027, 2016 Dresden Nuclear Station Initial License Examination Proposed Exam Files - Licensee Letter Transmitting the Proposed Examination/Test to the NRC2016-12-0101 December 2016 2016 Dresden Nuclear Station Initial License Examination Proposed Exam Files - Licensee Letter Transmitting the Proposed Examination/Test to the NRC SVPLTR 16-0061, Core Operating Limits Report for Unit 3 Cycle 252016-11-21021 November 2016 Core Operating Limits Report for Unit 3 Cycle 25 SVPLTR 16-0018, Transmittal of 2015 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2016-04-25025 April 2016 Transmittal of 2015 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation2016-04-0808 April 2016 Submittal of Post Accident Monitoring Report Instrumentation SVPLTR 16-0001, Cyber-Security Ms 1 Thru 7 Inspection 2014 405; Notification of Completion of Corrective Actions2016-01-21021 January 2016 Cyber-Security Ms 1 Thru 7 Inspection 2014 405; Notification of Completion of Corrective Actions SVPLTR 15-0070, Core Operating Limits Report for Cycle 24A2015-12-15015 December 2015 Core Operating Limits Report for Cycle 24A SVPLTR 15-0065, Core Operating Limits Report for Cycle 252015-11-16016 November 2015 Core Operating Limits Report for Cycle 25 SVPLTR 15-0059, Core Operating Limits Report, Cycle 242015-10-25025 October 2015 Core Operating Limits Report, Cycle 24 SVPLTR 15-0056, 1, 2 and 3 - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2015-09-0404 September 2015 1, 2 and 3 - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 15-0055, Notification of Readiness for NRC 95001 Inspection2015-08-25025 August 2015 Notification of Readiness for NRC 95001 Inspection SVPLTR 15-0052, Response to Preliminary White Finding2015-08-14014 August 2015 Response to Preliminary White Finding SVPLTR 15-0046, ISFSI - Registration of Use of Casks to Store Spent Fuel2015-07-17017 July 2015 ISFSI - Registration of Use of Casks to Store Spent Fuel SVPLTR 15-0043, Registration of Use of Casks to Store Spent Fuel2015-06-12012 June 2015 Registration of Use of Casks to Store Spent Fuel SVPLTR 15-0034, 2014 Annual Radiological Environmental Operating Report2015-05-14014 May 2015 2014 Annual Radiological Environmental Operating Report SVPLTR 15-0020, Written Position on Preliminary White Finding Discussed in NRC Inspection Report 05000237/2014005; 05000249/20140052015-03-0202 March 2015 Written Position on Preliminary White Finding Discussed in NRC Inspection Report 05000237/2014005; 05000249/2014005 SVPLTR 15-0014, Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities2015-02-11011 February 2015 Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities 2023-06-20
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Exekln Exelon Generation Company, LLC www.exeloncorp.com Nuclear Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 SVPLTR: #09-0045 1 OCFR.54 October 2, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington D.C. 20555-0001 Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-19 NRC Docket No. 50-237 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Revised License Renewal Commitment for the Testing of Drywell to Suppression Chamber Vent Lines Expansion Bellows
Reference:
(1) Letter (RS-03-180) from Mr. Patrick R. Simpson (Exelon Generation Company, LLC), to the NRC, "Additional Information for the Review of the License Renewal applications for Quad Cities Nuclear Power Station, Units 1 and 2 and Dresden Nuclear Power Station, Units 2 and 3", dated October 3, 2003 (2) NUREG 1796, "Safety Evaluation Report Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2" (3) NUREG 1856, "Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 and 2' The purpose of this letter is to inform the NRC that Exelon Generation Company, LLC (EGC) is revising a commitment identified in References (1) and (2) for Dresden Nuclear Power Station (DNPS).
In Reference (1), as a part of EGC's license renewal application for DNPS, EGC identified that the primary containment Drywell to Suppression Chamber Vent Lines expansion bellows (vent line bellows) were constructed of two plies of Type 304 stainless steel and as two-ply expansion bellows, their testing required the use of a plant unique methodology. Based on that information, the NRC in Reference (2), Section 3.5.2.2.1, "Containments," credited that specific testing as the basis for a safety decision in the safety evaluation.
It has been subsequently determined that the vent line bellows at DNPS are constructed of only a single-ply of Type 304 stainless steel, which prevents them from being tested as described in Reference (1).
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October 2, 2009 U.S. Nuclear Regulatory Commission Page 2 of 2 The vent line bellows (quantity 8 per unit) penetrate the torus shell and connect to the vent header within the torus. The vent line bellows attach between the exterior of the vent line and the exterior of the torus shell, providing the required differential movement between these items without developing significant interaction loads. One end of each bellows is welded to the outside of each vent line. The other end is welded to the torus shell. Based on this arrangement, the interior air space between the bellows and the vent line is open to the torus air space.
The interior of the bellows is not accessible due to the small gap between it and the vent pipe. The exterior of the bellows is covered by protective plates to prevent accidental mechanical damage during operation. Two drawings showing the construction details of the bellows are attached to this letter. These single-ply expansion bellows can only be properly pressure tested by a 10 CFR Part 50, Appendix J, Type A test.
The remainder of the information regarding the vent line bellows as described in Reference (1) is unaffected. Therefore, the conclusions reached in Reference (2) for both susceptibility to stress corrison cracking (Section 3.5.2.2.1) and fatigue analyses (Section 4.6.2.3) remain accurate. The vent line bellows remain within the scope of License Renewal but are not part of the scope of the pressurized testing being performed for two-ply mechanical penetrations expansion bellows.
EGC's review of the matter concludes that the use of the combination of the ASME Section Xl, Subsection IWE Program and 10 CFR Part 50, Appendix J Program, Type A testing will adequately assure the detection of cracking should it occur for the vent line bellows. The NRC has previously accepted the use of Appendix J Type A testing for single-ply vent line bellows, (as documented in Reference (3), Section 3.5.2.2.1).
Therefore, EGC is revising the commitment to test the vent line bellows for DNPS Units 2 and 3 to credit its Appendix J Type A testing.
Should you have any questions concerning this letter, please contact Ms. Marri Marchionda at 815-416-2800.
Respectfully, Tim Hanley Site Vice President Dresden Nuclear Power Station Attachement: Construction Details of Drywell to Suppression Chamber Vent Lines Bellows cc: Regional Administrator- NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
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