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MONTHYEARW3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Request ML1131204702011-11-0808 November 2011 Email, Supplemental Information Request for Acceptance Review, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Acceptance Review W3F1-2011-0082, Supplement to License Amendment Request Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-11-25025 November 2011 Supplement to License Amendment Request Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Supplement ML12023A0802012-01-18018 January 2012 Calculations Requested for License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Request ML1202303452012-01-23023 January 2012 Acceptance Review Following Supplement Email, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Acceptance Review ML1205807382012-02-27027 February 2012 Request for Additional Information License Amendment Request for Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: RAI ML1205807292012-02-27027 February 2012 Email, Request for Additonal Information License Amendment Request for Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Other W3F1-2012-0019, Response to Request for Additional Information, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-04-0303 April 2012 Response to Request for Additional Information, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Response to RAI W3F1-2012-0028, Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Supplement ML1217105922012-06-19019 June 2012 Email, Request for Additional Information, Round 2, License Amendment Request for Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: RAI W3F1-2012-0053, Response to a Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2012-07-17017 July 2012 Response to a Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Response to RAI ML12250A4352012-10-31031 October 2012 Issuance of Amendment No. 237, Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Approval 2012-10-31
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Category:Letter type:W
MONTHYEARW3F1-2024-0049, Notification of Readiness for Supplemental Inspection2024-10-21021 October 2024 Notification of Readiness for Supplemental Inspection W3F1-2024-0042, License Amendment Request to Extend Allowable Outage Times for One or More Control Room Air Conditioning Units Inoperable2024-10-16016 October 2024 License Amendment Request to Extend Allowable Outage Times for One or More Control Room Air Conditioning Units Inoperable W3F1-2024-0038, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0039, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0041, Reply to a Notice of Violation, EA-24-0522024-09-19019 September 2024 Reply to a Notice of Violation, EA-24-052 W3F1-2024-0040, Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days2024-09-0303 September 2024 Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0019, (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 252024-07-22022 July 2024 (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0032, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-07-17017 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation W3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0013, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program2024-05-0808 May 2024 Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0014, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20242024-04-29029 April 2024 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2024 W3F1-2024-0015, Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure2024-04-24024 April 2024 Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure W3F1-2024-0016, Annual Radiological Environmental Operating Report (AREOR) - 20232024-04-24024 April 2024 Annual Radiological Environmental Operating Report (AREOR) - 2023 W3F1-2024-0017, Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.22062024-04-23023 April 2024 Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.2206 W3F1-2024-0020, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20232024-04-11011 April 2024 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 W3F1-2024-0008, Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0009, Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0012, Response to NRC Integrated Inspection Report 05000382/20230042024-03-11011 March 2024 Response to NRC Integrated Inspection Report 05000382/2023004 W3F1-2024-0006, Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days2024-02-28028 February 2024 Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0056, Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. 2024-09-03
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Text
Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504 739 6660 Fax 504 739 6678 Djacob2@entergy.com Donna Jacobs Vice President, Operations Waterford 3 W3FI-2012-0053 July 17, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Response to a Request for Additional Information Regarding License Amendment Request to revise Technical Specification 3/4.7.4 Table 3.7-3, "Ultimate Heat Sink Minimum Fan Requirements per Train" [TAC No. ME7342]
Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
In Email request from N. Kalyanam to M. Mason (ADAMS Accession Number ML121710592), Waterford 3 received a request for additional information regarding its License Amendment Request to revise Technical Specification 3/4.7.4 Table 3.7-3, "Ultimate Heat Sink Minimum Fan Requirements per Train." Please find attached, the additional information requested.
There are no commitments associated with this submittal. Should you have any questions or comments concerning this submittal, please contact Michael E. Mason at (504) 739-6673.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July 17, 2012.
Sincerely,
Attachment:
Response to NRC Request for Additional Information
W3F1 -2012-0053 Page 2 cc: Mr. Elmo E. Collins, Jr. RidsRgn4MailCenter@nrc.gov Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.
Arlington, TX 76011-4511 Marlone.Davis@nrc.gov NRC Senior Resident Inspector Dean.Overland@nrc.gov Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Kaly.Kalyanam@nrc.gov Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Louisiana Department of Environmental Ji.Wiley@LA.gov Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312
Attachment 1 to W3FI-2012-0053 Response to NRC Request for Additional Information to W3F1 -2012-0053 Page 1 of 6 Request for Additional Information and the Responses
RAI-1
Background The licensee has performed Calculation ECM95-008,"Ultimate Heat Sink Design Basis," to determine the Ultimate Heat Sink (UHS) design basis under LOCA conditions using the worst combination meteorological design parameters and to account for the impact of the replacement steam generators. When describing the heat transfer associated with the wet cooling towers, QWCT, the licensee used the relationship: QWCT =mCP (AT), where m is the mass flow rate of water, CP is the specific heat and, and AT is the cooling range.
Issue This equation does not account for the evaporative cooling effect of a wet cooling tower (WCT) which is normally expressed in terms of a change in enthalpy. Thus the calculated temperature of the water out of the cooling tower basin is affected, which affects the UHS WCT cooling range, the component cooling water (CCW) heat exchanger fouling factor and the graph shown in attachment 7.3 of the base calculation, among possible other effects.
Request Please explain your use of the above described equation for the WCTs in calculation ECM95-008. What changes, if any, are necessary to calculation ECM95-008 and TS 3/4.7.4?
Response
Calculation ECM95-008 determines the wet bulb and dry bulb temperature combinations needed to produce the 11 5F CCW water supply temperature based on cooling tower manufacturer performance curves. The heat that needs to be transferred by the Auxiliary Component Cooling Water (ACCW) system, QACCW is the heat transferred by the CCW Heat Exchanger, QCCWHX, plus the heat rejected by the Essential Chiller, Qchiler.
QAccw = QCCWHX + QChiller QACCW, is also determined by subtracting the Dry Cooling Tower (DCT) capacity, QDCT, from the total plant heat load, QTOTAL.
QACCW = QTOTAL - QDCT to W3F1 -2012-0053 Page 2 of 6 The temperature increase in Auxiliary Component Cooling Water (ACCW) between the basin and the return nozzles results from the heat transfer from the CCW heat exchanger and the Essential Chiller and can be calculated from the equation:
ATACCW = (QCCWHX + QChiller) / mACCWCP.
Where mAccw is the mass flow rate of ACCW, CP is the specific heat and, ATACCW is the difference between the ACCW supply temperature and ACCW return temperature.
This ATACcW is also the temperature difference that would be seen across the WCT at equilibrium conditions. Therefore, ATACcW is the WCT cooling range, which is the difference between the equilibrium basin temperature and the hot water entering the tower.
The WCT guaranteed performance curves, which have been demonstrated by testing to be conservative, are used to determine the wet bulb temperature required to produce the required cooling range. Therefore, for the purpose of demonstrating the ability to transfer peak heat load under worst case meteorological conditions, it is not necessary to perform calculations that compute the evaporate cooling based on change in enthalpy. This has already been factored into the WCT performance curves. Therefore, it is appropriate to determine the WCT range using the equation:
QWCT =mCP (AT)
The calculations that determine water consumption and inventory margin appropriately consider the evaporative cooling based on change in enthalpy.
Therefore, no changes are necessary to calculation ECM95-008 and TS 3/4.7.4.
to W3F1-2012-0053 Page 3 of 6
RAI-2
Background In establishing the UHS design basis in Calculation ECM95-008,"Ultimate Heat Sink Design Basis," the licensee has assumed 100% tube capacity on the Dry Cooling Tower (DCT) and 95% tube capacity on the Component Cooling Water (CCW) heat exchanger and has used the manufacturer's performance curves for the DCT and Wet Cooling Tower (WCT). The calculation's intent is to show that the DCT with 15 fans and the WCT with 8 fans meets the LOCA heat removal requirements using the worst combination meteorological design parameters.
Issue Tube fouling and wet cooling tower fill fouling can adversely affect the heat transfer capabilities of the DCT, WCT and CCW heat exchanger and thus adversely affect the assumptions and performance curves described above.
Request Identify and describe the testing and maintenance that is performed on the DCT, WCT and CCW heat exchanger that verifies that these components are functioning as described in the design basis calculation ECM95-008.
Response
The CCW system temperature is controlled by the dry cooling tower fans and by modulating the flow through the CCW heat exchanger. The CCW water does not directly interact with the atmosphere, and is thus not subject to contamination. The CCW system chemistry is controlled per procedure CE-002-007 to assure heat transfer surfaces are not subject to contamination or biofouling.
The Auxiliary Component Cooling Water (ACCW) system also uses chemically treated water and does not intake from or discharge to any body of water. The system chemistry is controlled per procedure CE-002-003 to assure heat transfer surfaces are not subject to contamination or biofouling. Makeup water is demineralized potable water from the Condensate Makeup (CMU) system. A filtration system circulates, filters, and chemically treats the water stored in the wet cooling tower basins. However, the Wet Cooling Tower water inventory does directly interact with the atmosphere, thus the ACCW system is conservatively considered an open loop design.
The following information describes the testing and maintenance that is performed on the DCT, WCT and CCW Heat Exchanger that verifies these components are functioning as described in the design basis calculation ECM95-008.
to W3F1 -2012-0053 Page 4 of 6 Dry Cooling Tower (DCT) Heat Exchanger CE-002-007, Maintaining Component Cooling Water Chemistry - This procedure provides steps for controlling the chemistry of CCW, which is the process medium cooled by the DCT. The Chemistry department samples the CCW system every 7 days. Maintaining CCW chemistry within acceptable parameters ensures DCT performance is maintained.
The Dry Cooling Tower "A" & "B" Heat Exchangers have several tasks under Preventative Maintenance Task (PM) #14508 and PM #14509 that are performed.
The tasks include the following:
" Pressure Wash DCT "A" and "B" Coils as determined by Engineering.
Preventative Maintenance Tasks direct the Engineering Department to perform a cleanliness inspection of the Dry Cooling Tower coils every 2 years. Additionally, the System Engineer inspects the Dry Cooling Tower for any excessive dirt, soot and/or debris during his monthly walkdown. Also, it is an expectation that the DCT equipment is monitored for proper operation daily by the plant Operations staff. If any of the inspections/tours identifies potential degradation of coil cleanliness, the Engineering department determines if pressure washing is necessary. Pressure washing is effective in removing any dirt or soot on the Dry Cooling Tower coils. The Engineering Department also evaluates the effectiveness of the pressure washing performed. Pressure washing the DCT coils has historically been proven to be very effective in removing dirt and soot from the DCT coils in the past.
- Inspect and paint all piping in area every two years.
" Cleanliness inspection every two years (look for any debris or staged equipment that might impact the designed function of the DCTs and resolve any issues).
The System Engineer monitors Meteorological conditions and ensures design margins are met and performs walkdowns in accordance with EN-DC-1 78, System Walkdowns, on the CCW system, including the inspection of the DCT and DCT Fans.
to W3F1 -2012-0053 Page 5 of 6 Wet Cooling Tower (WCT) Heat Exchanger CE-002-003, Maintaining Auxiliary Component Cooling Water (ACCW) Chemistry -
This procedure provides instructions for maintaining corrosion and biological control in the ACCW system, which is the process medium cooled by the WCT. The Chemistry department samples the ACCW system every 7 days. Maintaining ACCW chemistry within acceptable parameters ensures WCT performance is maintained.
WCT "A" & "B" Heat Exchangers have several tasks under PM # 5814 and PM #
5815 that are performed. The tasks include the following:
" Perform a Thermal Performance test on the WCT per procedure PE-004-033.
The Thermal Performance Analysis was last performed on 3/30/09 & 12/10/08 respectively. The test is currently scheduled to be nominally performed every 4 years.
- Inspect the WCT in accordance with Tech Manual every two years.
- The WCT Basin & submerged components are inspected for silt, corrosion and degradation that could affect component function every three years.
- Inspect WCT Fans every two years for degradation of equipment and paint (as necessary) all piping in area.
The System Engineer performs walkdowns per EN-DC-1 78, System Walkdowns, on the ACCW system, including the WCT.
Component Cooling Water (CCW) Heat Exchanger CE-002-007, Maintaining Component Cooling Water Chemistry and CE-002-003, Maintaining Auxiliary Component Cooling Water (ACCW) Chemistry - These procedures provide steps for controlling the chemistry of CCW and ACCW, which are the process mediums that transfer heat in the CCW Heat Exchanger. The Chemistry department samples the CCW and ACCW systems every 7 days.
Maintaining CCW and ACCW chemistry within acceptable parameters ensures the CCW Heat Exchanger performance is maintained.
Eddy Current testing is performed on CCW Heat Exchangers "A" & "B" tubes under PM # 7404 (last performed 11/18/09) and PM # 5440 (last performed 11/04/09). The Eddy Current test is currently scheduled to be nominally performed every 6 years on each train.
to W3F1 -2012-0053 Page 6 of 6 CCW Thermal Performance Analysis testing is performed per procedure PE-004-021 under PM # 5814 (last performed on 3/30/09) and PM # 5815 (last performed on 12/10/08). The test is currently scheduled to be nominally performed every 4 years on each train.
The System Engineer monitors Meteorological conditions and ensures design margins are met and performs walkdowns per EN-DC-1 78, System Walkdowns, on the CCW system, including the inspection of the DCT and DCT Fans.