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MONTHYEARW3F1-2004-0075, Reissue of Report BAW-2177, Analysis of Capsule W-97 Entergy Operations, Inc. Waterford Generating Station Unit 3 - Reactor Vessel Material Surveillance Program2004-09-13013 September 2004
Reissue of Report BAW-2177, Analysis of Capsule W-97 Entergy Operations, Inc. Waterford Generating Station Unit 3 - Reactor Vessel Material Surveillance Program
Project stage: Request
W3F1-2005-0005, 90 Day Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2005-03-0303 March 2005
90 Day Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML0515305472005-05-27027 May 2005
RAI Related to GL 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at pressurized-water Reactors
Project stage: RAI
ML0516605012005-06-0202 June 2005
RAI Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0521402772005-07-28028 July 2005
Part 21 Deficiency Report Re Framatome Anp Supplied Pressurizer Heaters with Internals Manufactured by Thermocoax. Initially Reported on 07/22/05
Project stage: Request
ML0603903862006-02-0909 February 2006
Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accident at Pressurized-Water Reactors
Project stage: RAI
ML0733900652007-12-10010 December 2007
Approval of Extension Request, Corrective Actions Due Date, GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0801400072008-01-28028 January 2008
Report on Results of Staff Audit of Corrective Actions to Address GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs
Project stage: Other
ML0801403182008-01-28028 January 2008
Staff Audit Report on Results of Corrective Actions to Address GSI-191 GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs
Project stage: Other
ML0917302832009-06-11011 June 2009
Email, Draft Request for Additional Information Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors
Project stage: Draft RAI
ML0917302852009-06-11011 June 2009
Draft Request for Additional Information Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors
Project stage: Draft RAI
ML0920901072009-08-0606 August 2009
Notice of Conference Call with Entergy Operations, Inc. to Discuss Draft Request for Additional Information on Generic Letter 2004-02 for Waterford, Unit 3
Project stage: Draft RAI
ML0925101242009-09-22022 September 2009
RAI, Regarding Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents
Project stage: RAI
ML0927200322009-10-0101 October 2009
Notice of Forthcoming Conference Call with Entergy Operations, Inc. to Discuss Waterford Steam Electric Station, Unit 3, Planned Response to Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML1005400832010-02-24024 February 2010
Forthcoming Conference Call with Entergy Operations, Inc. to Licensees Responses to NRC Generic Letter 2004-02 for Waterford Steam Electric Station, Unit 3
Project stage: Request
ML1006903722010-03-0808 March 2010
Licensee Slides from 3/8/2010 Meeting Generic Letter 2004-02 Response to RAIs
Project stage: Response to RAI
ML1007003012010-04-0707 April 2010
Summary Follow-Up Conference Call with Entergy Operations, Inc. to Discuss Draft Response for Waterford, Unit 3, to the Request for Additional Information for Generic Letter 2004-02
Project stage: Draft RAI
ML1013400612010-05-18018 May 2010
Notice of Forthcoming Conference Call with Entergy Operations, Inc. to Discuss Draft Response on GL-2004-02 for Waterford Steam Electric Station, Unit 3
Project stage: Draft Other
ML1015204762010-06-0101 June 2010
Email, Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML1015302322010-06-0909 June 2010
Summary of Conference Call Meeting with Entergy Operations, Inc. to Discuss Draft Response on GL-2004-02 for Waterford Steam Electric Station, Unit 3
ML1017301902010-06-17017 June 2010
Revised Responses to the Request for Additional Information Related to GL-2004-02
Project stage: Request
ML1017301952010-06-17017 June 2010
Revised Responses to the NRCs Request for Additional Information Related to GL-2004-02
Project stage: Request
ML1017302002010-06-17017 June 2010
Chemical Effects Summary Related to RAI Response to GL-2004-02
Project stage: Other
W3F1-2010-0032, Response to Request for Additional Information Regarding Final Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2010-11-23023 November 2010
Response to Request for Additional Information Regarding Final Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Supplement
2009-06-11
[Table View] |
Text
Waterford 3 Chemical Effects Summary The evaluation of chemical effects involves a two step process. The first step is to determine the plant specific chemical precipitate loading utilizing the WCAP-16530 model. The second step is to perform plant specific head loss testing utilizing the WCAP-16530 precipitate loading. This summary document only addresses the first step of this process.
Waterford 3 chemical effects precipitate loading was analyzed by Alion Science & Technology utilizing the guidance provided in WCAP-16530 and version 1.1 of the associated spreadsheet tool. Plant specific inputs were used in a conservative manner to maximize precipitate loading. The following three notable conservatisms are applied to the analysis.
x The sump is assumed to not be mixed throughout the model. The difference in precipitate generation between assuming a mixed pool and non-mixed pool is small; however, assuming a non-mixed pool conservatively maximizes the amount of material dissolved and thus maximizes the amounts of precipitates generated.
x Per WCAP-16530 Section 6.4, due it was assumed that all dissolved aluminum will form precipitates.
x To account for NRC observations and recommendations in the SER of WCAP-16530 regarding the use of a time-based aluminum dissolution analysis, the release rate of aluminum is doubled in the analysis for the first 15 days for both submerged and unsubmerged metallic aluminum to bound the ICET 1 test data.
Table 1 list the Waterford 3 specific input utilized in the analysis. Based on the results of the WCAP-16530 analysis of the WF3 debris load and post-LOCA containment sump chemistry, aluminum is the limiting reactant in the formation of sodium aluminum silicate, and no aluminum oxyhydroxide is formed.
The corrosion/dissolution sources contributing to elemental release quantities and precipitates for the limiting case (Maximum volume, Maximum pH) are included as Figure 1 and Figure 2. Nukon and MEI, which are composed of E-Glass, are the primary sources of calcium and silicon. The TSP buffer reacts with the dissolved calcium released from E-glass, as well as from concrete, to form calcium phosphate precipitate. Unsubmerged aluminum is the primary source of dissolved aluminum, followed by E-glass and submerged aluminum.
Parameter Value Time of Recirculation Actuation 3253.19 sec Time at which spray is terminated 30 days Max. Recirculation Water Volume 102,810 ft³ Min. Recirculation water Volume 42,938 ft³ Buffering Agent TSP Boric Acid Concentration of RWSP 2040 - 2900 ppm Maximum Sump pH 8.1 Minimum Sump pH 7.1 (1h - 10d); 7.0 (20d - 30d)
Metallic Aluminum Submerged 10 ft² / 10 lb Unsubmerged 140 ft² / 340 lb Fiberglass Insulation (MEI/Nukon/Latent) 786.23 ft³ Silica Powder (Min-K/Microtherm) 4.6 ft³ Concrete (exposed & submerged total) 81,558 ft² Aluminum Silicate None Calcium Silicate None Table 1: Plant Specific Inputs
Figure 1: Elemental Release by Material Figure 2: Precipitate by Material 0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 80.00 90.00 100.00 Ca3(PO4)2 NaAlSi3O8 AlOOH M
ass (kg)
Precipitate Contributions to Precipitates by Material Concrete Silica Powder E-Glass Metallic Aluminum Not-Submerged Metallic Aluminum Submerged Material Class Ca3(PO4)2 NaAlSi3O8 AlOOH Metallic Aluminum Submerged 0.00 1.36 0.00 Metallic Aluminum Not-Submerged 0.00 24.76 0.00 E-Glass 47.70 61.02 0.00 Silica Powder 0.00 1.00 0.00 Concrete 2.91 0.34 0.00 Precipitate (kg) 0.00 20.00 40.00 60.00 80.00 100.00 120.00 140.00 160.00 180.00 Ca Si Al Release (kg)
Element Contribution to Elemental Releases by Each Material Concrete Silica Powder E-Glass Metallic Aluminum Not-Submerged Metallic Aluminum Submerged Releases in kg Material Class Ca Si Al Metallic Aluminum Submerged 0.00 0.00 0.28 Metallic Aluminum Not-Submerged 0.00 0.00 5.09 Calcium Silicate 0.00 0.00 0.00 E-Glass 18.49 157.40 3.69 Silica Powder 0.00 3.67 0.00 Concrete 1.13 0.57 0.04 Release (kg)
Mass (kg)
