Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML052490347, ML052500298, ML052850352, ML061010180, ML062910513, ML062910522, ML063060251, ML073370317, ML073380152, ML090720869, ML101590556, ML11154A093, ML11230B250, ML14283A526, ML15191A183
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MONTHYEARML0630602512003-10-15015 October 2003 WB1-DWD-015A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1 Project stage: Other ML0629105222003-11-0505 November 2003 WB1-DWD-024A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1 Project stage: Other ML0629105132004-08-24024 August 2004 TVAW001-RPT-001, Rev. 0, Report on Watts Bar, Unit 1 Containment Building Walkdowns for Emergency Sump Strainer Issues Project stage: Other ML0506804622005-03-0707 March 2005 Request Biocide/Corrosion Treatment Plan Approval, NPDES Permit No. TN0026450 Project stage: Request ML0515205802005-06-0303 June 2005 Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors Project stage: RAI ML0520800652005-07-21021 July 2005 And Watts Bar Nuclear Plant - NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - RAI, Supplemental Information Project stage: Supplement ML0524903472005-09-0101 September 2005 NRC Generic Letter 2004-02; Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors - Second Response Project stage: Other ML0525002982005-09-0101 September 2005 NRC Generic Ltr (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR) - Second Response Project stage: Other ML0528503522005-09-30030 September 2005 Outage Start Date Change Related to Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR) Project stage: Other ML0603800822006-02-10010 February 2006 RAI, Response to GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors Project stage: RAI ML0603704802006-02-10010 February 2006 Request for Additional Information 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 ML0610203132006-04-11011 April 2006 Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information Project stage: Response to RAI ML0610402192006-04-11011 April 2006 Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information Project stage: Response to RAI ML0610101802006-05-10010 May 2006 Request for Additional Info the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modification Project stage: Other ML0629105082006-07-0303 July 2006 Generic Letter 2004-02 - Request for Additional Information Regarding NRC Staff Audit on Containment Sump Modifications Project stage: Request ML0621204722006-07-0303 July 2006 Generic Letter 2004-02 - Request for Additional Information Regarding the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modifications Project stage: Request ML0621800772006-08-11011 August 2006 Proprietary Letter, Request for Withholding Information from Public Disclosure, Containment Sump Modifications Project stage: Withholding Request Acceptance ML0636204112006-12-21021 December 2006 Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Supplemental Response Project stage: Supplement ML0721501092007-08-0101 August 2007 Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request ML0727604492007-10-0202 October 2007 Generic Letter 2004-02, Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request ML0733703172007-11-28028 November 2007 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR) - Notice of Completion Project stage: Other ML0733801522007-12-0606 December 2007 Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Extension Request Evaluation Project stage: Other ML0806402052008-02-29029 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors (PWR) - Notice of Completion Project stage: Supplement ML0811201592008-03-31031 March 2008 Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5343-S01, Rev. 0, Attachment D, Page 374 of 575 Through Calculation No. PCI-5343-S02, Rev 0, Attachment B, Page 100 of 631 Project stage: Supplement ML0810905002008-03-31031 March 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Notice of Completion Project stage: Supplement ML0810905032008-03-31031 March 2008 Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S01, Rev. 2, Attachments a and B, Page 384 of 680 Project stage: Supplement ML0810905082008-03-31031 March 2008 Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S02, Rev. 0, Attachment B Page 101 Through End Project stage: Supplement ML0810905052008-03-31031 March 2008 Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S01, Rev. 2, Attachment B, Page 385 Through 680 Project stage: Supplement ML0810905012008-03-31031 March 2008 Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Pages E1-1 Through Figure 4.24 - Case 3 Project stage: Supplement ML0810905022008-03-31031 March 2008 Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Figure 4.25 - Case 3 Through Calculation PCI-5464-S01, Page 107 Project stage: Supplement ML0832308232008-11-25025 November 2008 Request for Additional Information Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors (Tac Nos. MC4717 and MC4718) Project stage: RAI ML0833700332008-12-0303 December 2008 Request for Additional Information Regarding Generic Letter 2004-02. Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors (Tac No. MC4730) Project stage: RAI ML0905408572009-02-23023 February 2009 Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information Project stage: Response to RAI ML0907208692009-02-25025 February 2009 Calculation, ALION-CAL-TVA-2739-03, Rev. 4, Watts Bar Reactor Building GSI-191 Debris Generation Calculation Project stage: Other ML0907208682009-03-0303 March 2009 Response to Request for Additional Information Regarding Generic Letter 2004-02,.Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors Project stage: Response to RAI ML0926502602009-09-29029 September 2009 RAI, Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0936502182009-12-23023 December 2009 GL 2004-02 Final RAI Responses Due Date Project stage: RAI ML1000601162010-01-0707 January 2010 Change of Response Date Regarding Request for Additional Information for Generic Letter 2004-02 Potential Impact of Debris Blockage During Design-Basis Accidents at Pressurized Project stage: RAI ML1015905562010-06-0909 June 2010 Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02 Project stage: Other ML1016600442010-06-17017 June 2010 Summary of Conference Call with TVA on Proposed Response to Request for Additional Information on Generic Letter 2004-02 Project stage: RAI ML1104003842011-02-0707 February 2011 Enclosure 1, Hydrothermal Effects on the Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir Project stage: Request ML1104003832011-02-0707 February 2011 Submittal of Hydrothermal Effects on Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauge Reservoir, Report Project stage: Request ML11152A1702011-05-12012 May 2011 Meeting Slides from Meeting with TVA on Their Proposed Response to a Request for Additional Information on Generic Letter 2004-02 Project stage: Response to RAI ML11137A1222011-05-13013 May 2011 Annual Radiological Environmental Operating Report - 2010 Project stage: Request ML11143A0832011-05-19019 May 2011 Response to Request for Additional Information on Intake Pumping Station Water Velocity Project stage: Response to RAI ML11152A1602011-05-26026 May 2011 Response to Request for Information from Public Meeting on May 11, 2011 Project stage: Request ML1115303282011-06-0202 June 2011 Completion of Temporary Instruction (Ti) 184, Availability and Readiness Inspection of Severe Accident Mitigation Guidelines (Samgs) at Region II Facilities - Revision Project stage: Request ML11152A1632011-06-28028 June 2011 Summary of Meeting with TVA on Their Proposed Response to a Request for Additional Information on Generic Letter 2004-02 Project stage: RAI ML11154A0932011-06-28028 June 2011 Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02 Project stage: Other ML11215A0992011-07-28028 July 2011 NPDES Permit No. TN0020168, TVA - Watts Bar Nuclear Plant, Spring City, Rhea County, Tennessee Project stage: Request 2008-11-25
[Table View] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 May 19, 2011 10 CFR 51.50 10 CFR 51.92 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant (WBN) Unit 2 - Intake Pumping Station Water Velocity - Response to Request for Additional Information
References:
- 1. TVA letter to NRC dated February 15, 2008, "Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Supplemental Environmental Impact Statement for the Completion and Operation of Unit 2"
- 2. TVA letter to NRC dated April 29, 2011, "Watts Bar Nuclear Plant (WBN) Unit 2 - Intake Pumping Station Water Velocity - Response to Request for Additional Information" This letter responds to a staff request for additional information (RAI) regarding the Intake Pumping Station Flow Rates used for environmental reviews. This RAI was discussed during a public meeting between the NRC and TVA on May 11, 2011. provides the response to the RAI.
There are no new commitments made in this letter. If you have any questions, please contact Bill Crouch at (423) 365-2004.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1 9 th day of May, 2011.
Respectfully, David Stinson Watts Bar Unit 2 Vice President : Response to IPS Water Velocity RAI
"-1L5D*)
U.S. Nuclear Regulatory Commission Page 2 May 19, 2011 cc (Enclosure):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
-I ENCLOSURE I Response to Intake Pumping Station Water Velocity RAI Tennessee Valley Authority - Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391 Question:
At a meeting with the NRC on May 11, 2011, the NRC staff reviewing the impingement report had a number of basic questions concerning the physical configuration of the Watts Bar Nuclear Plant Intake Pumping Station (IPS) and pump alignment and operation.
Response
Eight Essential Raw Cooling Water (ERCW) pumps and seven Raw Cooling Water (RCW) pumps are located at and take suction from the IPS. ERCW serves safety-related loads such as Residual Heat Removal and Component Cooling System heat exchangers. RCW supplies non-safety loads such as cooling units of normal building ventilation systems and turbine oil cooling.
Many of the loads for both ERCW and RCW are systems that are shared between both units. These loads have to be supplied whether a single unit or both units are in operation.
Spent Fuel Pool heat removal and building ventilation heat loads are examples of shared loads.
The ERCW system is safety-related and is required to have two independent trains to meet single failure requirements. The IPS as a consequence has two physically separated independent bays. The four train A ERCW pumps are located in one bay and the four train B ERCW pumps are located in the other bay. The RCW pumps are not safety-related, but they are divided between the two bays to even the flow load. There are four RCW pumps located in one bay and three located in the other bay. The RCW pumps are physically separated from the ERCW pumps but share common suction paths from the river through the traveling screens.
The IPS has four entrance openings at the river, four intake channels that are always submerged, four traveling screen wells, and four traveling screens. These features are evenly divided between the two bays. This arrangement is shown in Figure 1. Figure 2 shows an elevation schematic. The figures are provided to aid in understanding the arrangement. They are not intended to reflect the detailed physical configuration of the IPS.
Each entrance opening is 7.33 feet (ft) wide. Each intake channel has a rectangular cross section with a width of 5.17 ft and a height of 17.5 ft. The bottom elevation of the channel is 652 mean sea level (msl) and the top of the channel is at 669.5 msl. Each channel empties into a well that includes a traveling screen. The bottom elevation of the well is 652 msl and the top of the well is above the normal maximum lake level. Each well is 5.17 ft wide. Each traveling screen is four ft wide. The height of the water column through the well and through the traveling screen varies with the lake level. The minimum summer pool elevation is 681 msl and the minimum winter pool elevation is 677 msl. The minimum seasonal pool elevations were used for calculating the velocities through the traveling screen. The specific height values used were 29 ft for the summer and 25 ft for the winter. Since there are two flow paths into each bay, the flow area per bay is twice the width times the height for each path. The area through the traveling screen is also multiplied by a factor from the manufacturer to account for the effective flow area. This value is 0.503 for the WBN screens. The velocity in the wells was not calculated but would be the velocity of the intake channel multiplied by the ratio of 17.5 ft/29 ft for the summer and 17.5/25 for the winter.
Typical summertime operation for two units would have two ERCW pumps and three RCW pumps operating per bay. If temperatures were high or due to maintenance alignments, four RCW pumps in one bay could be in operation resulting in a flow rate of 73 cfs. This was the
ENCLOSUREI Response to Intake Pumping Station Water Velocity RAI Tennessee Valley Authority - Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391 configuration chosen for determining velocities. The resulting velocities were 0.62 fps through the screens, 0.17 fps at the IPS entrance, and 0.4 fps in the intake channels. The flow through the other bay would be 61 cfs, giving a total IPS intake flow of 134 cfs. Thus choosing the bay with more pumps operating will produce higher velocities. A typical summertime operation for a single unit would have two ERCW pumps and two RCW pumps operating per bay. The total ERCW flow would be lower than would exist for two-unit operation. Because it is physically possible, although unlikely, that all four RCW pumps could be running on one bay; it can be assumed that the velocities for the four RCW pump bay for two-unit operation also apply to single unit operation.
The normal system alignment for winter operation would be two ERCW pumps and two RCW pumps per bay. The ERCW flow rate is less than would be required during summer operation.
Similar to single unit operation, all four RCW pumps on one bay could be in operation with none operating in the other bay. This configuration results in a flow rate of 68 cfs through the four RCW pump bay with resulting velocities of 0.67 fps through the traveling screens, 0.18 fps at the IPS entrance, and 0.37 fps in the intake channel. For this alignment, the flow rate in the other bay would be 45 cfs resulting in a total IPS intake flow of 113 cfs. The values discussed in the preceding paragraphs were taken from the reference.
Reference:
TVA Calculation EPMRCP052992, R2, "Sizing of Traveling Water Screen"
ENCLOSURE 1 Response to IPS Water Velocity RAI Tennessee Valley Authority - Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391 IPS Plan View Schematic 0000 RCW Pumps RCW Pumps 000 ERCW Pumps 00 00 ERCW Pumps 00 00 Intake Channel r]
I Traveling Screens T-7 1 Entrance E1-1
ENCLOSURE 1 Response to IPS Water Velocity RAI Tennessee Valley Authority - Watts Bar Nuclear Plant - Unit 2, Docket No. 50-391 IPS Elevation Schematic E1-2