Letter Sequence Meeting |
---|
|
|
MONTHYEARML0428703722004-09-17017 September 2004 Amerenue - Callaway Plant OL Amendment #1248 Replacement Steam Generators, Non-Proprietary, NSSS Systems Project stage: Request ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project2004-09-17017 September 2004 Technical Specification Revisions Associated with Steam Generator Replacement Project Project stage: Request ML0428603522004-09-17017 September 2004 Amerenue - Callaway Plant OL Amendment #1248 Replacement Steam Generators, Non-Proprietary Project stage: Request ML0429304812004-10-20020 October 2004 Notice of Forthcoming Meeting with Union Electric Company on the Callaway Plant Project stage: Meeting ML0430903882004-11-0404 November 2004 Docket No. 50-483 - Licensee'S Slides for Meeting Held on November 4, 2004, to Discuss Its Application on the Steam Generators Replacement in Fall 2005 (Tac No. MC4437) Project stage: Meeting ML0431703532004-11-10010 November 2004 Letter, Request for Additional Information from Public Disclosure, CAW-04-1868, TAC No. MC4437 Project stage: RAI ML0431302892004-11-17017 November 2004 Summary of Meeting with Union Electric Company for the Licensee to Present Its Application Dated September 17, 2004, to Replace the Steam Generators in the Fall of 2005 Project stage: Meeting ML0434301682004-12-20020 December 2004 RAI, Containment Integrity for the Steam Generator Replacement in the Fall of 2005 (TAC MC4437),12/20/04 Ltr to G. Randolph Project stage: RAI ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-02-11011 February 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Other ML0512206202005-05-0404 May 2005 Forthcoming Meeting with Union Electric Co. to Discuss Revision of TSTF-449 and Response to Questions on Replacement of Steam Generators to Be Installed in Fall 2005 Project stage: Meeting ML0511501022005-05-0404 May 2005 RAI, Steam Generator Replacement License Amendment Request, TAC MC4437 Project stage: RAI ML0514301542005-05-18018 May 2005 Enclosure - 05/18/05, Meeting Summary -Plots Referenced in Licensee'S Response to Question 46 Project stage: Meeting ULNRC-05145, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-05-26026 May 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ML0514601112005-06-0303 June 2005 Summary of Meeting with Callaway on 05/18/05 for the Licensee to Discuss Its Draft Response to the Request for Additional Information on Its Application Dated 09/17/2004. Project stage: Draft RAI ML0517803282005-06-17017 June 2005 Supplemental Technical Specification Revisions for the Steam Generator Replacement Project Project stage: Request ULNRC-05169, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-07-15015 July 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ULNRC-05178, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-07-29029 July 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ULNRC-05188, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-08-16016 August 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project Project stage: Request ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project2005-09-0606 September 2005 Supplemental Technical Specification Revisions for the Steam Generator Replacement Project Project stage: Request ML0524201542005-09-0707 September 2005 Withholding from Public Disclosure, Responses to NRC Request for Additional Information on WCAP-16265-P, Rev. 0, 'Callaway Replacement Steam Generator Program NSSS Licensing Report,' Dated February 2005 (CAW-05-1944) Project stage: RAI ML0524300462005-09-0707 September 2005 Withholding from Public Disclosure, Setpoint Methodology Portion of the Response to (NRC) Request for Additional Information, Questions 1 and 2 (CAW-05-1998) Project stage: RAI ML0524301332005-09-0707 September 2005 Callaway - Request for Withholding Information from Public Disclosure (CAW-05-2007) (Tac. MC4437) Project stage: Withholding Request Acceptance ML0527300832005-09-29029 September 2005 Technical Specifications, Amendment Regarding the Steam Generator Replacement Project Project stage: Acceptance Review ML0525700542005-09-29029 September 2005 License Amendment, Regarding the Steam Generator Replacement Project Project stage: Acceptance Review 2005-05-26
[Table View] |
|
---|
Category:Slides and Viewgraphs
MONTHYEARML24157A0642024-06-13013 June 2024 Earls 2024 Workshop Presentation ML22249A3292022-09-0606 September 2022 Presentation Information for Planned Pre-Application Meeting ML22174A3472022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ML22047A0942022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML22047A0952022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21271A6122021-09-28028 September 2021 Enclosure 1: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21271A6132021-09-28028 September 2021 Enclosure 2: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21211A6012021-07-30030 July 2021 Annual Assessment Meeting (Public) ML21123A2622021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21123A2602021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML20248H4672020-09-0404 September 2020 Rict & 50.69 LARs - NRC Pre-Submittal Meeting Slides ML20170A2032020-06-24024 June 2020 6/24/2020 - Pre-Submittal Meeting for Callaway Plant License Amendment Request to Defer Steam Generator Eddy Current Testing ML19247B3842019-09-12012 September 2019 GSI-191 / GL 2004-02 Licensing Amendment Request ML18158A5532018-06-14014 June 2018 Pre-Submittal Meeting for Full Implementation of Alternative Source Term ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16152A1232016-06-0101 June 2016 Strainer Testing for GSI-191 ML14050A4022014-02-20020 February 2014 License Renewal Public Meeting Slides 2 20 2014 ML13042A1882013-02-11011 February 2013 01/31/2013 Summary of the Public Meeting to Discuss the Results of the Grand Gulf Nuclear Station License Renewal Inspection IR 05000483/20120092013-01-25025 January 2013 1/17/2013 - Summary of Public Meeting to Discuss the Results of the Callaway Nuclear Plant License Renewal Inspection (05000483-12-009) ML12320A3052012-11-15015 November 2012 Licensee Slides for November 15, 2012 Public Meeting to Discuss License Amendment to Use Reg Guide 1.6 Revision 1 ML12241A2912012-08-29029 August 2012 UHS Meeting Slides August 29, 2012 ML12241A2922012-08-29029 August 2012 Class 1E AC Meeting Slides August 29, 2012 ML12096A3942012-03-14014 March 2012 Enclosure 5: Callaway Public Meeting Slides ML1115400922011-06-0303 June 2011 Summary of Annual Performance Assessment Meeting with Union Electric Company to Discuss the Callaway Plant Performance for the NRC Inspection Period Ending December 31, 2010 ML1115304052011-05-26026 May 2011 Licensee Slide'S from 5/26/11 Pre-Application Meeting ML1008804082010-03-25025 March 2010 Licensee Slides Pre-LAR Submittal Telecon ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S ML0932104872009-11-17017 November 2009 Summary of Regulatory Conference with Ameren Ue Regarding Callaway Plant ML0927302752009-10-15015 October 2009 Summary of Meeting with Union Electric Company to Discuss Proposed Risk-Informed Technical Specification License Amendment for Callaway Plant, Unit 1, and Future Adoption of Initiative 4b ML0910502042009-04-14014 April 2009 Summary of Meeting with Amerenue to Discuss Engineering Related Topics Pertaining to Callaway ML0904400462009-01-13013 January 2009 Public Scoping Meeting Presentation Slides ML0815404352008-06-0202 June 2008 Summary of Meeting to Discuss Annual Safety Performance Assessment for Callaway for 2007 ML0802504052008-01-23023 January 2008 Licensee Handout for Meeting with Union Electric Company on the Callaway Plant Relief Request I3R-10 to Use Plastic Pipe in the Safety-Related Essential Service Water (ESW) System ML0729505272007-10-22022 October 2007 Summary of Meeting with Amerenue Callaway Plant to Discuss Various Topics, Including: Essential Service Water; Current Problem Identification & Resolution Crosscutting Issue; Recent Human Performance Improvements ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0628602302006-10-12012 October 2006 Handout for Meeting with Nuclear Energy Institute (NEI) to Discuss Concerns Related to Operability Determination of Main Steam and Feedwater Isolation Valves with Dual Actuator Trains ML0622804372006-08-16016 August 2006 Handouts from Wolf Creek Nuclear Operating Corporation and from Union Electric Company for Meeting with NRC on the Main Steam Isolation Valve (MSIV) Operability Determination ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0611002222006-04-18018 April 2006 Summary of Meeting with Union Electric Company Regarding Callaway Plant, Which Discussed Recent Plant Performance and Various Topics ML0533202252005-12-0101 December 2005 Ri Schedule 05- Mcmurtray; Lessons Learned from Security-Based Table Top Drills ML0520804072005-07-27027 July 2005 Summary of Meeting with Union Electric Company Concerning Callaway Plant ML0430903882004-11-0404 November 2004 Docket No. 50-483 - Licensee'S Slides for Meeting Held on November 4, 2004, to Discuss Its Application on the Steam Generators Replacement in Fall 2005 (Tac No. MC4437) ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0408501912004-03-23023 March 2004 Docket No. 50-483 - Slides from Meeting Held on March 23, 2004, to Discuss Licensee'S License Amendment Request Application Dated December 17, 2003 ML0316806212003-07-17017 July 2003 Licensee'S Handouts, Slides and Viewgraphs, 53 Pages, S107210 ML0316806062003-07-17017 July 2003 NRC Handout, Slides and Viewgraphs, 103 Pages, S107211 ML0211402982002-04-24024 April 2002 Annual Performance Assessment Meeting for Callaway Plant ML0206503632002-03-0606 March 2002 02-27-02 Callaway/Ameren Ue Meeting Summary 2024-06-13
[Table view] |
Text
Introduction AGENDA General Description of Replacement Steam Generators (RSG)
Why Replace/Improvements Replacement Steam Generator/Original Steam Generator comparison Replacement Steam Generator Features Westinghouse NSSS RSG Analyses:
- RSG Licensing Activities
. T/S Changes Methodology Changes Application of Leak Before Break to the Pressurizer Surgeline Plans to address Alloy 600 weld Schedule for re-submittal of WCAP-15983 Other Refuel 14 OL Submittals MSIV Technical Specifications stroke time increase Inclusion of Feedwater Control Valves into Technical Specifications Nonproprietary 1
General Description of RSGs
-Why Replace?
Stress Corrosion Cracking Identified in 1995
- Model F S/G, 80% Mill Annealed I-600 Tubes
- Extensive Maintenance and Repair Required for 40 year life
- S/G Replacement Study Completed in Feb. 2000
- Base Case showed replacement is Cost Justified when considered over life of plant Nonproprietary Vendor Support and Structure
- March 2001 - SGT Selected for Installation
.* December 2001 - Westinghouse Selected for Accident Analysis / Licensing Nonproprietary 2
WAmerenUE hRAUA T OMAH x - Framatome 73119T RSQ Improved Performance All Forged Construction
[ aIntegral Steam Nozzle and Flow Restrictor High Efficiency Moisture Separators
- F Anti-Stratification Feedwater Inlet Foreign Object Capture System Optimized Level Control Taps Improved U-Bend Support System Increased Tube Surface Area Alloy 690 Thermally Treated Tubing Increased Circulation Ratio Access Ports at Each Support Plate Elevation Elimination of the Tubelane Blowdown Pipe Grooved Nozzle Dam Retention Ring Electro-Polished Channel Head Bowls v Self-Draining Channel Heads (No Belly Drain)
Improved Manufacturing Techniques Nonproprietary General Description of RSGs RSG vs. OSG Comparison W Model F Framatome 73/19 T Tube Material Alloy 600MA Alloy 690TT Tube OD (in.) 11/16 3/4 Tube Wall Thickness (in.) 0.040 0.043 Tube Pitch (in.) 0.98 square 1.031 triangular Number of Tubes 5626 5872 Tube Surface Area (f 2) 55,000 78,946 Bundle Height (in.) 348 433.9 Weight. Dry (lbs.) 715,000743,100 Circulation Ratio 3.64 4.00 Best Est. RCS Flow (gpm) 101.900 104.400 Steam Press (psia) @ T-hot of 614 IF (0%
SG tube plugging) 970 1,021 Specified MCO (%) <0.25 <0.10 Nonproprietary 3
General Description of RSGs RSG vs. OSG Comparison W Model F Framatome 73/19 T Steam Generator Areas and Volumes Primary Side SG Volume, f 3 /SG 962 1.352 Secondary Side SG Water Volume (no load). ft3 /SG 3,560 3,322 Secondary Side SG Steam Volume (100%
power), ft3/SG 3,814 3,491 Main Steam and Feedwater Conditions Full Load Main Steam Temperature, IF 538.4 547 Full Load Main Steam Flow (100% power),
lb/hr-SG 3.99E+06 4.01E+06 Feedwater Flow (100% power), lb/hr-SG 3.99E+06 4.05E+06 Blowdown Capacity, lb/hr-SG 44,000 120.000 Nonproprietawy Z %,,
WAmerenUE iCRAMATOMKAM Anti-Stratification Device (Helix)
LiŽA '1 Nonproprietary 4
AmerenWE ARANAATO C Anti-Stratification Device (Helix) l The Helix Is an anti-stratification device which minimizes the effects of thermal stratification, particularly during the Injection of cold Auxiliary Feedwater during plant transients. It also acts as a feedwater flow restrictor In the case of a feedwater pipe break.
hel I--
Nonproprietary
.M ,-
merenfllE iRAMATOME A";
Foreign Object Capture System Nonproprietary 5
AmerenEf ARAMATOME SP Foreign Object Capture System Caliaway was the first plant to require a foreign object capture system be Included In the RSG design.
The purpose of the system is, of course, to prevent the Introduction of foreign objects Into the secondary I0 side of the steam generators In order to protect against .M. A__
loose parts damage to the tubes.
-ZN i§\ Eliminating foreign objects and their associated risk Is a key component In the justification of extended operating cycles after the completion of the SGR.
Downcomer Nonproprietary Cyclone Separator
__s=_
SANDVIKI Welcomreto H -i Sandvik Steel ',r ngjV~--
Tubing The RSG tubing was manufactured In Sweden by Sandvik Steel. The tubing Is the most critical part of the RSG design and fabrication. Alloy 690TT Is used as It has been demonstrated to have much higher resistance to corrosion than does Alloy 600. The tubing has a nominal diameter of 0.75' with a nominal wall thickness of 0.043".
Stringent requirements were been placed on the quality of the tubing, Including the number and size of Imperfections and the minimal signal-to-noise ratio for eddy current examination. The tubing has Its own detailed specification for smelting, machining and Inspecting. It Is Included In the Certified Design Specification as Appendix S.
Nonproprietary 6
wAmerenYE M K .RATO Tube Bundle The bundle consists of 5872 Ailoy 690TT tubes, each having anominal OD of 314'and a nominal wall thickness of2 0.043. A total heat transfer area of 78,948 ft provides the required steam exit pressure (1010 psla) at a reduced T., of 614F.
The tube bundle Is of the 'incremented type".
which uses Increased straight length of tubes as their bending radii Increase.
Eight 41OSS Tube Support Plates (TSPs) are utilized to avoid vibration. The TSPs have broached holes, with three fat lands per broached opening, for tube support TSPs are laser aligned prior to tube Installation.
The top portion of the tube bundle is supported by three sets of 405SS Anti-Vibration Bars (AV~s). All U-bends, Including Row 1, are supported. A very small tube IAVB gap of 4.1
. , inmleIs used to prevent fretting and wear of the tube.
Broached plate Nonproprictary
%"merenUEj'.RAMA OMIr^0 T Primary Channel Head The primary channel head is a low allow steel forging with two (each) Integral nozzles and manways. After cladding, the channel head will be mechanically finished to 40 Ra, followed by electro-polishing. The channel heads are self-draining, allowing the elimination of the belly drains.
The tubesheet forging Is extended several Inches to allow the primary circumferential weld (and PWHT) to be performed at a distance from the expanded tubes.
Nonproprietary 7
RSG Safety Analysis Scope Westinghouse NSSS analysis and licensing efforts to support the RSG which included:
- Analyses and evaluations to support RSG
- Analysis of LBLOCA and SBLOCA events using updated Westinghouse Appendix K Methodology
- Re-analysis of most Non-LOCA events using the RETRAN-02 computer code
- Analyses to support a 15-second MSIV stroke time for a future plant modification and T/S change Nonproprietary RSG Safety Analysis Scope Westinghouse NSSS analysis and licensing efforts to support the RSG which included (continued):
- Calculation of T/S instrumentation uncertainties and protection system setpoints
-* Updating the Containment P/T and Steam Tunnel Subcompartment Analysis using the GOTHIC computer code
- Removal of the SG Trip Time Delays from the Callaway design and from the T/S Nonproprietary 8
Licensing Activities The proposed amendment would revise the following Technical Specifications ( TS):
- TS 3.4.5, "RCS Loops - MODE 3" TS 3.4.6, "RCS Loops - MODE 4" Nonproprientary Licensing Activities The proposed amendment would revise the following Technical Specifications (continued):
- TS 5.5.16, "Containment Leakage Rate Testing Program"
Licensing Activities The proposed amendment would also add new TS 3.4.17, "Steam Generator Tube Integrity",
pursuant to Technical Specifications Task Force (TSTF) Improved Standard Technical Specifications Change Traveler TSTF-449,
'Revision 2.
Nonproprictary Licensing Activities The following analyses for the Callaway RSG Project use first-time methodology applications:
- Excessive Increase in Secondary Steam Flow Event This analysis was performed using a simplified statepoint hand calculation analysis instead of an explicit analysis via the RETRAN code. Results show that the acceptance criteria are met.
- Loss of Normal Feedwater Event Previously, an overly-conservative single analysis was performed to bound the FSAR Chapter 15 analysis and the AFW System Reliability analyses. For the RSG, a dual-analyses approach that separately addresses both scenarios was implemented. Results show that all acceptance criteria are met. Nonproprietary
Licensing Activities The following analyses for the'Callaway RSG Project use first-time methodology applications (continued):
- Although these two methodologies are being employed at Callaway for the first time, they have been used in numerous submittals for other plants to the NRC in the recent past.
Nonproprietary Other Refuel 14 OL Submittals A revision to'TS 3.7.3 that will add the main i feedwater control valves and bypass valves to LCO 3.7.3. These valves are backup and diverse equipment in the RSG MFLB analysis, being added to LCO 3.7.3 as Criterion 4 equipment credited in the event of an MFIV failing open. Submittal was signed 27 Oct 2004.
- A revision to TS 3.7.2 that will increase the allowed MSIV closure to 15 seconds in support of plans to install new MSIV actuators during Refuel 14. This additional time delay has been accounted for in the RSG analyses. Submittal is scheduled for 15 Dec 04.
Nonproprietary 11
LBB for the Pressurizer Surge Line Mitigation measures to be applied at the Alloy 82/182 pressurizer nozzle safe end weld are being evaluated:
-Replace Alloy 600 Weld with a Stainless Steel Weld o.. .n Nonproprietary LBB for the Pressurizer Surge Line Proposed schedule for implementation mitigation
- measures and approval of WCAP-1 5983:
- Evaluation of the effects of this mitigation measure on the surge line LBB analysis and an update to the WCAP if necessary - January to Mid February
- NRC approval of WCAP-15983 and any relief requests if required - prior to outage start
- Implementation of mitigation measure - Callaway Refueling Outage 14 scheduled for Fall 05 Nonproprietary 12