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| ., Commonwe.Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 | | ., Commonwe.Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 |
| * Chicago, Illinois 60690 .--r-~ | | * Chicago, Illinois 60690 .--r-~ |
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| Repairs included replacing the pipe stub and strengthening the support by weld"ing the stub . to _the cleanup line with a full penetratiC>il weld. The failed weld was only a fillet weld. There are a total of ten (10) similar -welded snubber supports in the Unit #3 drywall. Eight (8) of the ten (10) including the one failed support were non-destructively exami~ed utilizing dye penetrant. The one failed support is unique to both Units 12 and 13 iniithat it has two "snubbers" attached to one support. | | Repairs included replacing the pipe stub and strengthening the support by weld"ing the stub . to _the cleanup line with a full penetratiC>il weld. The failed weld was only a fillet weld. There are a total of ten (10) similar -welded snubber supports in the Unit #3 drywall. Eight (8) of the ten (10) including the one failed support were non-destructively exami~ed utilizing dye penetrant. The one failed support is unique to both Units 12 and 13 iniithat it has two "snubbers" attached to one support. |
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| A. Giambusso August 16, 1973 | | A. Giambusso August 16, 1973 The High Pressure Coolant Injection (HPCI) line in both Unit 12 and 13 dry* |
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| The High Pressure Coolant Injection (HPCI) line in both Unit 12 and 13 dry* | |
| wells has one support with three (3) attached snubbers. .These two supports were dye penetran~~examined. All examinations were performed on August 8 and 9. No indications of faulty welds were detected. | | wells has one support with three (3) attached snubbers. .These two supports were dye penetran~~examined. All examinations were performed on August 8 and 9. No indications of faulty welds were detected. |
| Based on this representative sample the station believes all supports to be in satisfactory condition. During the next shutdown when the Bergen-Patterson "snubbers" are inspected, as stated in the referenced letter, the rep4'ired support for the Unit #3 cleanup line will again be examined. | | Based on this representative sample the station believes all supports to be in satisfactory condition. During the next shutdown when the Bergen-Patterson "snubbers" are inspected, as stated in the referenced letter, the rep4'ired support for the Unit #3 cleanup line will again be examined. |
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| *superintendent Dresden Nuclear Power Station WPW:slb cc: File/AEC Corr.Cat I 6350 | | *superintendent Dresden Nuclear Power Station WPW:slb cc: File/AEC Corr.Cat I 6350 |
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Latest revision as of 10:59, 4 February 2020
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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
MONTHYEARML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0552024-11-0101 November 2024 Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0432024-11-0101 November 2024 Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0472024-11-0101 November 2024 Letter to G. Cheatham, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0152024-11-0101 November 2024 Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0202024-10-31031 October 2024 NRC Letter to J. Loichinger Achp Request for Comments Concerning the Environmental Review of DNPS Units 2 and 3 Subsequent License Renewal Application ML24291A0272024-10-31031 October 2024 NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3 IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-5912024-10-21021 October 2024 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24225A2132024-09-26026 September 2024 Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval ML24253A0942024-09-23023 September 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID L-2024-Sle-0002) (Docket Numbers: 50-237 and 50-249) SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2152024-09-16016 September 2024 Confirmation of Initial License Examination ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24215A2912024-08-14014 August 2024 Request for Withholding Information from Public Disclosure Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 2024-09-06
[Table view] |
Text
Regutatory D~et ~File
., Commonwe.Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767
I\ s Dresden Nuclear Power Station R. R.- *fif - -
Morris, IL WPW Ltr. #592-~3 August 16, 1973 A. Giambusso Deputy Director for Reactor Projects Director of Licensing u.s. Atomic Energy Commission Washington, D.C. 20545
SUBJECT:
Inspection of Bergen-Patterson llydraulic Shock Suppressor at Dresden Nuclear Power Station, AEC Dkt 50-249
Reference:
Letter from Byron Lee, Jr. to Boyce H. Grier dated August 6, 1973, concerning Bergen-Patterson Shock Suppressors
Dear Mr. Giambusso:
- This letter is to report additional information concerning Bergen-Patterson "snubbers" subsequent to the referenced August 6 letter.
on August 4, J973, two Bergen-Patterson hydraulic shock suppressors, size 2.5 inch bore 3~25 inch stroke, (station identification nos. 23 and 25) were removed from the Unit #3.drywell for overhaul. At the time of re*
moval it was noticed that the 3 inch diameter pipe stub to which the two "snubbers" were affixed was broken at a circumferential weld. The broken weld was a saddle weld.benween the pipe stub and the cleanup line (figure 1).
The failed weld was examined by the company's Operational Anajysis Department. Tbe failure is believed to have.occurred due to fatigue. The crack initiation and propagation appears to be related to loss of fluid in the "snubbers". the fillet weld left a crack initiation site between the stub tube face and the cleanup pipe surface. Since there was no dampening by the "snubbers" (the two "snubbers" were out of oil) vibrations in the system imposed cyclic loading on the weld which ultimately caused a fatigue failure of the weld.
Repairs included replacing the pipe stub and strengthening the support by weld"ing the stub . to _the cleanup line with a full penetratiC>il weld. The failed weld was only a fillet weld. There are a total of ten (10) similar -welded snubber supports in the Unit #3 drywall. Eight (8) of the ten (10) including the one failed support were non-destructively exami~ed utilizing dye penetrant. The one failed support is unique to both Units 12 and 13 iniithat it has two "snubbers" attached to one support.
A. Giambusso August 16, 1973 The High Pressure Coolant Injection (HPCI) line in both Unit 12 and 13 dry*
wells has one support with three (3) attached snubbers. .These two supports were dye penetran~~examined. All examinations were performed on August 8 and 9. No indications of faulty welds were detected.
Based on this representative sample the station believes all supports to be in satisfactory condition. During the next shutdown when the Bergen-Patterson "snubbers" are inspected, as stated in the referenced letter, the rep4'ired support for the Unit #3 cleanup line will again be examined.
The referenced letter of August 6 contains some information which must be updated. It states that two of the eleven other. snubbers on Unit #2 and one of the eleven other snubbers on Unit #3 were inoperable. This information was based on the fact the snubber accumulators indicated no oil.
This is the same criteria used f 0r determining inoperable snubbers in the drywell. Subsequent to the station's determination the manufacturer's representative came to the station and examined the snubbers. He reported that they were operable, however, oil was needed in the accumulator.
Based on these facts it is now stated that all "other" snubbers were operable.
Sincerely,
?-~JWl~1
- w. P.* Worden *
- superintendent Dresden Nuclear Power Station WPW:slb cc: File/AEC Corr.Cat I 6350
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