Letter Sequence Request |
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MONTHYEARML0515305472005-05-27027 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
Waterford - RAI Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
Project stage: RAI
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
W3F1-2007-0051, Request for Extension of Completion Date for Corrective Actions Required by Generic Letter 2004-022007-11-14014 November 2007
Request for Extension of Completion Date for Corrective Actions Required by Generic Letter 2004-02
Project stage: Request
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
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
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
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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
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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 Licensee'S 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
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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 Nrc'S 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
2009-08-06
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Category:- No Document Type Applies
MONTHYEARML22034A3952022-02-16016 February 2022
Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion
ML22034A3972022-02-16016 February 2022
Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion
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Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion
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Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 15 of 18
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CNRO-2016-00024, Entergy - Form 10-K for Fiscal Year Ended December 31, 20152016-12-20020 December 2016
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Attachment 5 - W3F1-2014-0005 - Waterford Steam Electric Station, Unit 3, List of Regulatory Commitments
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2022-02-16
[Table view] |
Text
NRC RAI 18:
The October 23, 2008, supplemental response identified on page 59 that the assumptions made about the settling of particulate down to 100 microns in size were benchmarked against NRC-sponsored settling tests. Please identify the NRC-sponsored tests being referenced in this discussion.
WF3 Response 18:
The "NRC-sponsored settling tests" is referring to NUREG/CR-6916, titled "Hydraulic Transport of Coating Debris", Naval Surface Warfare Center, Carderock Division. The particulate settling size for the various materials is based on a force balance that accounts for hydraulic drag, gravity, and hydrostatic forces as prescribed in WCAP-16406-P. The developed relationship is compared (benchmarked) to the data in NUREG/CR-6916 Table 3-2 to demonstrate that the relationship produces conservative results. The data from NUREG/CR-6916 was not used as a basis for any materials settling size or depletion determination. Particulate settling is only analyzed to occur in the reactor lower plenum.
NRC RAI 33:
The supplemental response dated October 23, 2008, stated that flashing at the strainer would not occur because the strainer submergence is 8 inches and the maximum head loss is about 6 inches. This is true for a large-break LOCA, but does not address a small-break LOCA, which has a bounding submergence of about 2 inches. Please provide an evaluation for flashing during a small-break LOCA at the most limiting condition. This may require an evaluation of head loss versus submergence over time or credit for accident-generated pressure.
WF3 Response 33:
Credit for 1 psi of containment overpressure will provide > 2 ft flashing margin when submergence is less than the bounding head loss. Sump temperature will exceed 210 degrees Fahrenheit for only ~11 hrs during the event and the time to reach 210 degrees post Recirculation Actuation Signal is ~2.2 hrs. The maximum temperature profile is based on; (1) 1 of 2 Containment Spray Trains operating, (2) 1 of 4 Containment Fan Coolers operating, and (3) minimum Safety Injection flow. Waterford 3 Technical Specifications require containment pressure to be maintained between 14.275 psia and about 1 psig (27 inches water).
When expected containment pressure is compared to the saturation pressure of the sump fluid throughout the duration of an event it can be seen that adequate margin exists to support the 1 psi overpressure credit. Two cases are presented below. The first graph shows the comparison for the maximum sump temperature evaluation. The second shows the comparison for the minimum sump temperature evaluation.
Maximum Containment Profile 0 10 20 30 40 50 60 1 10 100 1000Time (hrs)Pressure (psia0 0 50 100 150 200 250Temperature (°F)Atm PressureMax Sat PressLiquid Temp Minimum Containment Profile 0 5 10 15 20 25 30 1 10 1001000Time (hrs)Pressure (psia) 0 20 40 60 80 100 120 140 160 180 200Temperature (°F)Atm PressureMin Sat PressLiquid Temp
NRC RAI 33a:
Please provide an evaluation of gas evolution downstream of the strainer that could reach the pump suction. Please provide the percentage of evolved gas estimated at the pump inlet. Evaluate the effects of any potential gas ingestion to the pumps taking suction from the sump as described in RG 1.82, Appendix A. The staff is concerned that any gasses that are stripped from the fluid as it passes through the strainer could collect within the strainer and eventually transport to the pump suction as larger air pockets. In addition, the staff has not received information that would characterize the redissolution of air or gas as the static head on the fluid increases as it flows to the pumps suction. If re-dissolution of air is credited, please provide an evaluation of the variables that could affect the redissolution.
WF3 Response 33a:
The solubility of air in water is a maximum at the lowest temperature of interest. The table of dissolved air in water at 25 °C clearly shows that the solubility is proportional to absolute pressure. The difference of solubility is 0.023 g Air / kg Water per one atm. A conservatively bounding pressure difference across the strainer of 2.5 ft (0.07 atm) is used in this analysis.
Assuming conservatively that the water entering the strainer is fully saturated with air, the bounding difference of solubility of air in water is:
0.07
- 0.023 = 0.00169 g Air / kg Water or 1.69E-6 kg Air / kg Water Dissolved Air in Water (25 °C)(77 °F) Gauge Pressure (atm) 0 1 2 3 4 5 Dissolved Air (g/kg) 0.023 0.045 0.068 0.091 0.114 0.136 The densities are:
Air - 1.169 kg/m3 at 25 °C and one atm Water - 997 kg/m3 at 25 °C The volume ratio therefore becomes; (1.69E-6 kg Air / kg Water) * (997 kg/m3) / (1.169 kg/m3) = 0.0014 or 0.14%
As the flow stream leaves the sump it travels downward where it experiences an increase in pressure due to the elevation difference (~30 ft). This increase in pressure would promote some of the air re-dissolving back into the water and void size reduction due to compression. Conservatively neglecting the re-dissolution of air and using the ideal gas law to evaluate the void compression, the 0.14% void fraction equates to a 0.07% void fraction at the pump suction.
P 1 V 1 = P 2 V 2; therefore V 2 = P 1 V 1/P 2 P 1 = 14.7 psia
- 2.31 ft/psi = 34 ft P 2 = P 1 + 30 ft = 64 ft V 2 = 0.14%
Using the relationship from Regulatory Guide 1.82, it can be seen that the 0.07% void fraction will have a negligible effect (<1 ft) on pump required net positive suction head.
NPSHrequired' = NPSHrequired * (1+0.5*) where is the air ingestion rate in percent by volume Highest NPSHrequired for any ECCS pump operating at runout conditions is 21.765 ft 21.765 ft * (1 + 0.5
- 0.07%) = 22.527 ft or an increase of 0.762 ft
