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Category:Report
MONTHYEARL-2023-089, Refueling Outage Owners Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owners Activity Report (OAR-1) Unit 2 for Inservice Inspections L-2023-028, And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML21214A0432021-08-0202 August 2021 SLRA June 30, 2021, Public Meeting Discussion Questions ML21126A2392021-05-0606 May 2021 Subsequent License Renewal Application, Aging Management Supplement 2 ML21040A4842021-02-0909 February 2021 Fws to NRC, Point Beach Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location And/Or May Be Affected by Your Project ML21040A4852021-02-0909 February 2021 Fws to NRC, Verification Letter for Point Beach SLR Under Programmatic Biological Opinion for Northern Long-eared Bat NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds NRC 2019-0002, Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2019-01-24024 January 2019 Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2017-0045, Updated Final Response to NRC Generic Letter 2004-022017-12-29029 December 2017 Updated Final Response to NRC Generic Letter 2004-02 NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report2017-08-0202 August 2017 High Frequency Seismic Evaluation Confirmation Report NRC 2017-0032, Focused Evaluation for Local Intense Precipitation2017-06-22022 June 2017 Focused Evaluation for Local Intense Precipitation ML17136A3222017-05-19019 May 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood-Causing Mechanism Reevaluation L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 ML17018A2712017-02-0909 February 2017 Flood Hazard Mitigation Strategies Assessment NRC 2016-0041, Submittal of 10 CFR 50.59 Summary Report for 20152016-08-31031 August 2016 Submittal of 10 CFR 50.59 Summary Report for 2015 NRC 2015-0072, Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan2015-12-16016 December 2015 Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan ML15300A1402015-11-0303 November 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15211A5932015-08-0303 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force NRC 2015-0043, Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 10072015-07-20020 July 2015 Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 1007 NRC 2014-0041, 10 CFR 50.59 Summary Report for 20132014-08-27027 August 2014 10 CFR 50.59 Summary Report for 2013 ML14147A0342014-06-0606 June 2014 Review of the 2013 Steam Generator Tube Inspections NRC 2014-0024, NextEra Energy Point Beach, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the F2014-03-31031 March 2014 NextEra Energy Point Beach, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukush ML13338A5102014-01-27027 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14006A1872014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 NRC 2013-0069, Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding2013-07-15015 July 2013 Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding ML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R342013-07-0303 July 2013 Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 NRC 2013-0061, CFR 50.59 Summary Report for 20122013-06-28028 June 2013 CFR 50.59 Summary Report for 2012 NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic2012-11-26026 November 2012 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic NRC 2011-0059, 10 CFR 50.59 Summary Report for 20102011-07-0101 July 2011 10 CFR 50.59 Summary Report for 2010 2023-07-24
[Table view] Category:Technical
MONTHYEARL-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report2017-08-0202 August 2017 High Frequency Seismic Evaluation Confirmation Report NRC 2017-0032, Focused Evaluation for Local Intense Precipitation2017-06-22022 June 2017 Focused Evaluation for Local Intense Precipitation ML13338A5102014-01-27027 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14006A1872014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 ML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R342013-07-0303 July 2013 Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic2012-11-26026 November 2012 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic ML14006A3192010-03-31031 March 2010 LTR-PAFM-10-50-NP, Rev. 0, Section XI Flaw Evaluation of Indication Recorded on RC-32-MRCL-ALL-03 of the Point Beach Unit 1 Inlet Nozzle to Pipe Weld. NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation2010-03-0303 March 2010 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation ML0935704152009-12-31031 December 2009 WEP-09-133 Np, Point Beach Unit 1 & Unit 2 (Wep/Wis) Extended Power Uprate License Amendment Request Responses to Request for Additional Information. ML0912505662009-04-0707 April 2009 Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Introduction Through Chapter 2, Section 2.5.7 ML0912505692009-04-0707 April 2009 Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Chapter 2, Section 2.5.8 Through Appendices ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0822406862008-06-30030 June 2008 WCAP-16541-NP, Revision 2, Spent Fuel Pool Criticality Safety Analysis. NRC 2008-0029, Pressure and Temperature Limits Report2008-05-30030 May 2008 Pressure and Temperature Limits Report NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair2008-05-28028 May 2008 License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report2007-06-13013 June 2007 Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program2006-07-11011 July 2006 LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program NRC 2006-0054, Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis2006-06-0606 June 2006 Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis ML0600400192005-12-14014 December 2005 Westinghouse LTR-RCDA-873-NP Attachment Point Beach, Unit 1 - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature (Non-Proprietary) ML0533203122005-11-18018 November 2005 Reactor Vessel CMTRs (Non-Proprietary) NRC 2005-0117, Request for Withholding of Proprietary Information from Public Disclosure2005-09-0707 September 2005 Request for Withholding of Proprietary Information from Public Disclosure NRC 2005-0068, Submittal of Supporting Analyses Regarding Control of Heavy Loads2005-06-0303 June 2005 Submittal of Supporting Analyses Regarding Control of Heavy Loads ML0435700172004-12-14014 December 2004 from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations ML0514002682004-10-0808 October 2004 Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material NRC 2004-0004, Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 20042004-08-30030 August 2004 Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 2004 NRC 2004-0081, Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 42004-08-13013 August 2004 Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 4 ML0426603132004-07-31031 July 2004 BAW-2467NP, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of Point Beach Units I and 2 for Extended Life Through 53 Effective Full Power Years. ML0508800622004-05-0707 May 2004 Licensee Procedure, HPIP 4.58, Issuance of Respiratory Equipment Revision 14 ML0508800432004-04-30030 April 2004 NMC Incident Response Team for Issues Encountered During Unit 1 Reduced Inventory and Nozzle Dam Installation at Pbnp 2022-07-29
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f CAMP 701 SECONDARY SYSTEM AND WATER TREATMENT PLANT SAMPLE POINTS DOCUMENT TYPE: Technical NNSR CLASSIFICATION:
REVISION: 17 7, 2002 EFFECTIVE DATE: May REVIEWER: N/A Manager of Chemistry APPROVAL AUTHORITY:
Manager of Chemistry PROCEDURE OWNER (title):
OWNER GROUP: Chemistry Verified Current Copy:
Signature Date Time Controlling Work Document Numbers List pages used for Partial Performance C *.*"
CAMP 701 POINT BEACH NUCLEAR PLANT NNSR CHEMISTRY ANALYTICAL METHODS & PROCEDURES Revision 17 May 7, 2002 SECONDARY SYSTEM AND WATER TREATMENT PLANT SAMPLE POINTS 1.0 PURPOSE minimum purge This procedure provides a list of approved sample points, their location, guidance as appropriate for volumes for secondary sample collection, and additional sampling secondary water chemistry and water treatment.
2.0 PREREQUISITES Appropriate collection bottles 3.0 PRECAUTIONS AND LIMITATIONS Chemistry lab supervisor NOTE: Sample points not included in this procedure require approval prior to use.
to determine the effects, if 3.1 In certain instances, alternate sample points may be required any, of sample tubing runs.
Care should be taken when sampling at points other than the sample panels. These points 3.2 may also be under "willnot have gone through a heat exchanger and may be hot. They
, :pressure.
to work under a standing 3.3 Sampling in the primary sample room requires the technician RWP procedure (NP 4.2.21).
RWP. All steps shall be taken to comply with the standing Beta/Gamma or, 3.4 When samples have activity greater than 1.00 E-3 icilcc 602 shall be followed.
1.00 E-3 vici/cc 1H3 , the handling precautions of CAMP are to be considered 3.5 Secondary samples collected in the primary sample room contaminated until verified not to be cofritaminated.
away from the sampler when 3.6 The discharge of sink sample hoses shall always be directed first opening any sink sample valve.
when obtaining steam generator 3.7 Wear heavy gloves to protect hands from possible bums blowdown filter outlet samples.
of a thoroughly flushed 3.8 Samples for anion analysis may be grabbed on the discharge problems.
cation column if the cations present in the sample cause matrix 3.2.1.
3.9 Sampling and handling shall be done in accordance with NP REFERENCE USE Page 3 of 12
CAMP 701 POINT BEACH NUCLEAR PLANT NNSR CHEMISTRY ANALYTICAL METHODS & PROCEDURES Revision 17 May 7, 2002 SECONDARY SYSTEM AND WATER TREATMENT PLANT SAMPLE POINTS both NOTE: Steps 5.2.3 and 5.2.4 can be completed concurrently if sampling steam generators.
5.2.3 IF sampling the A S/G in the Primary Sample Sink, THEN perform the following:
flow.
NOTE: RE-219 might alarm in the control room due to low to low flow.
- a. Inform the control room that RE-219 might alarm due
- b. Open SS-148 and SS-151.
Controlled Side
- c. Purge the line per Attachment A for "A" Steam Generator Sample Room.
- d. Shut SS-148 and SS-151.
- e. Open SS-146 and SS-152.
- f. Collect appropriate sample volume.
- g. Shut SS-146 and SS-152.
- h. IF RE-219 alarmed, reset the alarm.
T-HEN contact the control room to see if you should 5.2.4 IF sampling the B S/G in the Primary Sample Sink, THEN perform the following:
low flow.
NOTE: RE-219 might alarm in the control room due to due to low flow.
- a. Inform the control room that RE-219 might alarm
- b. Open SS-149 and SS-151.
Generator Controlled Side
- c. Purge the line per Attachment A for "A" Steam Sample Room.
- d. Shut SS-149 and SS-151.
- e. Open SS-147 and SS-153.
- f. Collect appropriate sample volume.
g, Shut SS-147 and SS-153.
Page 5 of 12 REFERENCE USE
CAMP 701 POINT BEACH NUCLEAR PLANT NNSR CHEMISTRY ANALYTICAL METHODS & PROCEDURES Revision 17 May 7, 2002 SECONDARY SYSTEM AND WATER TREATMENT PLANT SAMPLE POINTS ATTACHMENT A TABLE OF PURGE VOLUMES FOR SECONDARY SYSTEM conductivity cell.
NOTE: Hotwell conductivity verification to be sampled at outlet of installed Unit 1 Grab Samples Valve Number Location Min. Purge Volume (ml)
Sample JK/K/*
Condensate Pump Discharge
- 4 ISS-68 Sample Panel lUrbine a-lal8 1TSS-69 Sample Panel -TurbineHall 8' 11100' 111001 Steam Generator Feed Pump Suction Sample Panel Turbine Hal] 8' I _________________________________________ 137OO 4 ISS-70 Sample Panel Turbine Hall 8' 13700W 5B Feedwater Heater Outlet 8500' ISS-71 Sample Panel Turbine Hall 8' 8800i Heater Drain Tank 4000' lSS-72 Sample Panel Turbine Hall 8' 36300' Atixiliary Feed 81 ISS-73 -SamplePanel Turbine Hall 3200' Main Steam 1CS84F 8' Level U1 Turbine Hall N/A Hotwell 1. 2, 3, 4 1CS84G 145000 SGBD Panel Turbine Hall 8' "A" Steam Generator5 IFI-4251A 137000' 1FI-4253A SGBD Panel Turbine Hall 8' 3W "B" Steam Generatorj U1 Controlled Side Sample "A" Steam Generator 1SS-152 Room 3W ISS-153 U1 Controlled Side Sample "B" Steam Generator Room 200 L Aux. Bldg- 8"Level South Steam Generator Blowdown Filter I-MS-310 Out 1700 I-MS-302 Aux. Bldg. 8' Level South Steam Generator Blowdown Filter Inlet 1600 I-MS-306 Aux. Bldg. 8"Level South Steam Generator Blowdown Filter Inlet 2300 RW-7 8' U1I Turbine Hall Radwaste Steam Condensate Return Samples that have continuous flow.
FI-04251A (minimum purge volume when NOT Minimum purge volume when there is continuous flow through continuous is 72900mn).
3 Minimum purge volume when there is continuous flow through FI-04253A (minimum purge volume when NOT continuous is 65900 ml).
Integrated samples for condensate pump discharge, 5B feedwater heater outlet, and heater drain tank are taken from ISS-38, 1SS-40, and ISS-41, respectively.
5 Anion samples for SGIA and SGIB are taken from 1FI-4251C and IFI-4253C, respectively.
-,...i' Page 7 of 12 REFERENCE USE
POINT BEACH NUCLEAR PLANT CAMP 701 CHEMISTRY ANALYTICAL METHODS & PROCEDURES NNSR Revision 17 SECONDARY SYSTEM AND WATER TREATMENT May 7, 2002 PLANT SAMPLE POINTS ATTACHMENT B TABLE OF COMMON GRAB SAMPLES FOR SECONDARY SYSTEM Sample Valve Number Location Min. Purge Volume (ml)
"A" Condensate Storage Tank AF-13B 26' Turbine Hall 100 "B" Condensate Storage Tank AF-14B 26' Turbine Hall 100 Heating Boiler Feed/Condensate AF-68B 8' U2 Turbine Hall 300 (SW corner)
"A" House Heating Boiler HV-757 26' U2 Turbine Hall 600 "B" House Heating Boiler HV-771 26' U2 Turbine Hall 1000 1P29 Auxiliary Feed Pump Suction 1AF25 8' Level Turbine Hall 100 IP29 Auxiliary Feed Pump Leakoff Local 8' Level Turbine Hall 900g P38A Auxiliary Feed Pump Suction AF38 8' Level Turbine Hall 100 P38A Auxiliary Feed Pump-Leakoff Local 8' Level Turbine Hall 900' P38B Auxiliary Feed Pump Suction AF51 8' Level Turbine Hall - 100 P38B Auxiliary Feed Pump Leakoff Local 8' Level Turbine Hall 1500' 2P29 Auxiliary Feed Pump Suction 2AF63 8' Level Turbine Hall 100 2P29 Auxiliary Feed Pump Leakoff Local 8' Level Turbine Hall 900g Unit 1 Service Water Overboard SW-146H 8' Level Ul Control Side 5007 Unit 2 Service Water Overboard SW-104H 8' Level Turbine Hall 500W St I Samples that have a continuous drip or flow.
2 Minimum purge volume when service water return header pump is running (minimum purge volume when NOT running is 3000 ml).
3 Minimum purge volume when service water return header pump is running (minimum purge volume when NOT running is 9800 ml).
C Page 9 of 12 REFERENCE USE
CAMP 701 POINT BEACH NUCLEAR PLANT NNSR CHEMISTRY ANALYTICAL METHODS & PROCEDURES Revision 17 May 7, 2002 SECONDARY SYSTEM AND WATER TREATMENT PT ANT SAMPLE:: POINTS
- 1.-
ATTACHMENT C WATER TREATMENT GRAB SAMPLES (continued)
Sample Valve Number Location Root Min. Purge Valve Volume(ml)
"C" Reverse Osmosis Feedwater WT-651C U2 TH 8'/U17C WT-650C 100 WT-654C U2 TH 8'/U17C WT-650C 200 "C" Manual Feedwater SDI Sample WT-665C U2 TH 8'/U17C WT-650C 100 F-225C First Stage "A" Membrane Outlet WT-666C U2 TH 8"/UI7C WT-650C 100 F-226C First Stage "B" Membrane Outlet F-227C First Stage "C" Membrane Outlet WT-667C U2 TH 8'IUI7C WT-650C 100 WT-668C U2TH 8'IU17C WT-650C 100 F-228C Second Stage "A" Membrane Outlet WT-669C U2 TH 8'/U17C WT-650C 100 F-229C Second Stage "B" Membrane Outlet WT-670C U2 TH 8'/U17C WT-650C 100 F-230C Third Stage "A" Membrane Outlet WT-671C U2 TH 8'1U17C WT-650C 100 F-231C Third Stage "B" Membrane Outlet WT-672C U2 TH 8'/UI7C WT-650C 100 F-232C Fourth Stage "A" Membrane Outlet WT-673C U2 TH 8'/U17C WT-650C 100 F-233C Fourth Stage "B" Membrane Outlet WT-662C U2 TH 8'/U 17C WT-650C 100 "C" Reverse Osmosis Product WT-660C U2 TH 8'IU17C WT-650C 100 "C" Reverse Osmosis Reject WT-303A U10A WT-300A 100 "A" Cation Inlet WT-303B U10B WT-300B 100 "B" Cation Inlet WT-303C U10C WT-300C 100 "C" Cation Inlet FI-9354A WT Sample Panel WT 312A 16000 "A" Cation Outlet FI-9354B WT Sample Panel WT 312B 14500 "B" Cation Outlet FI-9354C WT Sample Panel WT 312C 13000 "C' Cation Outlet Deaerator Outlet 2 WT 403A U14A WT 402A 600 "A" Anion Inlet WT403B U14B WT 402B 600 "B" Anion Inlet WT403C U14C WT 402C 600 "C" Anion Inlet FI-9363A WT Sample Panel WT 413A 15400 "A" Anion 2/3 FI-9363B WT Sample Panel WT413B 15100 "B" Anion 2/3 FI-9363C WT Sample Panel WT 413C 16500 "C" Anion 2/3 FI-9369A WT Sample Panel WT 412A 14200 "A" Anion Outlet FI-9369B WT Sample Panel WT 412B 13900 "B" Anion Outlet "C" Anion Outlet FI-9369C WT Sample Panel WT 412C 15300 FI-9378A WT Sample Panel WT512A 9200 "A" Mixed Bed Outlet FI-9378B WT Sampe Panel WT'512B 9200 "B" Mixed Bed Outlet WT-688 U2 TH 8' Sample WT-687 14000 Water Treatment Reverse Osmosis Reject Panel WT-58 WT Bench Sink WT-57 500 Neutralizing Tank Sample 2 Sample the deaerator outlet at the online anion inlet listed below.
Page I1I of 12 REFERENCE USE