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Category:Report
MONTHYEARML23346A2392024-01-17017 January 2024
Seismic Hazard Report by the Office of Nuclear Reactor Regulation
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Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022
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RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
ML20329A3452020-11-24024 November 2020
Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of Analyses
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Verbal Relief for Penetration Nozzle
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Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
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Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic
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Final Report PBAPS Thermal Study
ML18354B0662018-12-20020 December 2018
Summary of Monitoring Well Installation Details
RS-18-113, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...2018-09-28028 September 2018
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...
RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to 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 ...2018-08-28028 August 2018
Seismic Probabilistic Risk Assessment Report, Response to 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 ...
ML18093A3822018-03-30030 March 2018
Decommissioning Status Report - 2017
RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-01-0505 January 2018
Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
ML17093A6972017-03-30030 March 2017
Decommissioning Status Report - 2016
ML19064B2232017-02-24024 February 2017
Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station
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ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16
ML16342B6212016-12-0707 December 2016
Results of Visual Inspections of Replacement Steam Dryer
RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
ML16048A4412016-02-17017 February 2016
Transmittal of Extended Power Uprate: Results of Replacement Steam Dryer Power Ascension Testing
ML19064B2162015-12-31031 December 2015
Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2015
ML15275A1682015-10-0202 October 2015
Attachment 2, LTR-BWR-ENG-15-076-NP, Revision 1, Replacement Steam Dryer Report at Predicted EPU Conditions (Non-Proprietary) and Attachment 3, Affidavit
ML15233A0952015-08-20020 August 2015
Revision 0 to LTR-BWR-ENG-15-076-NP, Replacement Steam Dryer Report at Predicted EPU Conditions
ML15219A6182015-08-0707 August 2015
Extended Power Uprate: Results of Unit 2 Replacement Steam Dryer Power Ascension Testing
ML15051A2622015-04-20020 April 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 Related to Recommendation 2.1
ML15097A0762015-04-0606 April 2015
Soarca Peach Bottom 2005 Site File
ML15096A0082015-04-0505 April 2015
Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information
ML15026A4692015-02-12012 February 2015
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to EA-13-109 (Severe Accident Capable Hardened Vents)
ML15029A6402015-01-29029 January 2015
Mellla+ License Amendment Request Supplement 1 Supplemental Reload Licensing Report
ML15028A3812015-01-28028 January 2015
Independent Spent Fuel Storage Installation (ISFSI) - Biennial 10 CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2013 Through 12/31/2014 and Annual Commitment Revision Report for Period 1/1/14 - 12/31/14
ML19064B2142014-12-31031 December 2014
Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2014
RS-14-300, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to Nrg Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1..2014-12-19019 December 2014
Expedited Seismic Evaluation Process Report (CEUS Sites), Response to Nrg Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1..
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014
Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
ML14119A0572014-06-17017 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident (Tac Nos. MF0261 and MF0262)
ML14086A6242014-04-30030 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0157 and MF0158)
ML14105A3862014-04-11011 April 2014
Attachment 9: WCAP-17649-NP, Rev. 2, ASME Code Stress Report (Enclosure B.3)
ML14105A3852014-04-11011 April 2014
Attachment 8: WCAP-17635-NP, Rev. 3, Comprehensive Vibration Assessment Program
ML14105A3882014-04-11011 April 2014
Attachment 11: WCAP-17655-NP, Rev. 4, Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate
ML14105A3872014-04-11011 April 2014
Attachment 10: WCAP-17654-NP, Rev. 4, Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate
ML14072A0262014-03-31031 March 2014
WCAP-17655-NP, Rev 3,Peach Bottom Unit 3 Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate.
ML14072A0232014-03-31031 March 2014
WCAP-17635-NP, Rev 2, Peach Bottom Atomic Power Station Unit 2 and Unit 3 Replacement Steam Dryer Comprehensive Vibration Assessment Program.
ML14072A0242014-03-31031 March 2014
WCAP-17609-NP, Rev 2, Peach Bottom Units 2 and 3 Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads.
ML14072A0252014-03-31031 March 2014
WCAP-17654-NP, Rev 3, Peach Bottom Unit 2 Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate.
ML19007A3282014-02-28028 February 2014
Final Report for the Thermal Study to Support a 316(a) Demonstration
ML14070A1462014-02-28028 February 2014
WCAP-17639-NP, Revision 3, Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer.
ML14070A1452014-02-28028 February 2014
WCAP-17626-NP, Revision 1, Processing of Peach Bottom Unit 2 and Unit 3 MSL Strain Gauge Data and Computation of Predicted EPU Signature.
ML14070A1442014-02-28028 February 2014
WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report.
ML14070A1432014-02-28028 February 2014
WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition.
2024-01-17
[Table view]
Category:Miscellaneous
MONTHYEARML23334A2502023-11-30030 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022
(Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
ML18093A3822018-03-30030 March 2018
Decommissioning Status Report - 2017
ML17093A6972017-03-30030 March 2017
Decommissioning Status Report - 2016
ML19064B2232017-02-24024 February 2017
Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station
ML17027A0152017-01-27027 January 2017
ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16
ML16342B6212016-12-0707 December 2016
Results of Visual Inspections of Replacement Steam Dryer
RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
ML19064B2162015-12-31031 December 2015
Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2015
ML15051A2622015-04-20020 April 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 Related to Recommendation 2.1
ML15097A0762015-04-0606 April 2015
Soarca Peach Bottom 2005 Site File
ML15096A0082015-04-0505 April 2015
Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information
ML15026A4692015-02-12012 February 2015
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to EA-13-109 (Severe Accident Capable Hardened Vents)
ML15028A3812015-01-28028 January 2015
Independent Spent Fuel Storage Installation (ISFSI) - Biennial 10 CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2013 Through 12/31/2014 and Annual Commitment Revision Report for Period 1/1/14 - 12/31/14
ML14119A0572014-06-17017 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident (Tac Nos. MF0261 and MF0262)
ML14086A6242014-04-30030 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0157 and MF0158)
ML19064B2202014-02-28028 February 2014
Final Report for the Thermal Study to Support a 316(a) Demonstration: Peach Bottom Atomic Power Station Part 1 of 2
ML14070A1462014-02-28028 February 2014
WCAP-17639-NP, Revision 3, Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer.
ML14070A1452014-02-28028 February 2014
WCAP-17626-NP, Revision 1, Processing of Peach Bottom Unit 2 and Unit 3 MSL Strain Gauge Data and Computation of Predicted EPU Signature.
ML14070A1442014-02-28028 February 2014
WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report.
ML14070A1432014-02-28028 February 2014
WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition.
ML19064B2332013-12-0606 December 2013
Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2013
RS-13-085, Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency...2013-04-30030 April 2013
Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency...
ML13109A0522013-04-18018 April 2013
Revised Gnf Response to NRC RAI 44 for License Amendment Request for Use of Neutron Absorbing Spent Fuel Pool Rack Inserts, Attachment 3, Enclosures 2, 3 and 4
ML19064B2372013-02-25025 February 2013
Entrainment Characterization Study 2012
IR 05000456/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000272/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000289/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
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U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000454/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000461/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000237/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000373/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000352/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000219/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000277/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000254/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
NEI 99-04, Peach Bottom, Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - Biennial 10CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2011 Through 12/31/2012 and Annual Commitment Revision Report for the Period 1/1/12 Through 122013-01-28028 January 2013
Peach Bottom, Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - Biennial 10CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2011 Through 12/31/2012 and Annual Commitment Revision Report for the Period 1/1/12 Through 12/
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Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2012
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Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-1 Through Page C-76
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Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-104
ML13003A0282012-11-16016 November 2012
Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-77 Through Page C-156
ML13003A0292012-11-16016 November 2012
Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-157 Through Page C-249
ML13003A0302012-11-16016 November 2012
Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-250 Through Page C-333
ML13003A0312012-11-16016 November 2012
Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-334 Through Page C-399
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Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-400 Through End
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ML13003A0342012-11-16016 November 2012
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2023-11-30
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Text
Attachment 11 Peach Bottom Atomic Power Station Units 2 and 3 NRC Docket Nos. 50-277 and 50-278 WCAP-17639, Rev 3. Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer
Westinghouse Non-Proprietary Class 3 WCAP-17639-NP Febr uary 2014 Revision 3 Enclosure B.7 Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer
) Westinghouse
WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-17639-NP Revision 3 Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer Author Kristen Kahsar*
Reviewed by David A. Suddaby*
February 2014 Approved: David R. Forsyth*, Manager BWR Plant & Stress Analysis
- Electronically approved records are authenticated in the electronic document management system.
Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA
© 2014 Westinghouse Electric Company LLC All Rights Reserved
WESTINGHOUSE NON-PROPRIETARY CLASS 3 ii RECORD OF REVISIONS Revision Description Completed 0 Original issue 08/17/2012 1 Revised in accordance with customer audit. Due to the extent of revisions, change bars 8/27/2012 are not used.
2 Revised in accordance with customer audit. Due to the extent of revisions, change bars 9/25/2012 are not used.
3 Revised to incorporate details on new instruments and additional pressure transducer See EDMS locations.
WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 iii TABLE OF CONTENTS R E C OR D OF RE V ISIO N S .......................................................................................................................... ii L IST O F TA B L E S ....................................................................................................................................... iv LIST O F F IG U RE S ...................................................................................................................................... V L IST O F AC R ON YM S ................................................................................................................................ vi 1 IN T R OD U C TIO N ........................................................................................................................ 1-1 2 INSTRUMENTATION OVERVIEW ........................................................................................... 2-1 3 DATA ACQUISITION AND REDUCTION SYSTEM ................................................................ 3-1 3.1 INSTRUMENT SPECIFICATIONS ................................................................................ 3-1 3.2 INSTRUMENT POSITIONS .......................................................................................... 3-1 3.3 ENSURING ACQUISITION OF QUALITY DATA ....................................................... 3-3 3.4 ONLINE DATA EVALUATION SYSTEM ..................................................................... 3-3 3.5 DETERMINING FREQUENCY, MODAL CONTENT, AND MAXIMUM VALUES. 3-4 3.6 BIAS ERRORS AND RANDOM UNCERTAINTIES .................................................... 3-4 4 REFERENCES ............................................................................................................................. 4-1 WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 iv LIST OF TABLES Tab le 3-1 ]a,c ................................................................................. 3-1 WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 v LIST OF FIGURES F igure I-1 [ ]a,c ............................................................... 1-1 WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 vi WESTINGHOUSE NON-PROPRIETARY CLASS 3 vi LIST OF ACRONYMS Acronym Definition DAS data acquisition system NRC U.S. Nuclear Regulatory Commission OEM original equipment manufacturer RAI request for additional information Trademark Note:
INCONEL is a registered trademark of the Special Metals Corporation group of companies.
WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-1 1 INTRODUCTION Exelon is replacing the original equipment manufacturer (OEM) steam dryers at its Peach Bottom site.
The Peach Bottom site has two reactors numbered Unit 2 and Unit 3 that will have their steam dryers replaced with Westinghouse-designed steam dryers.
This document describes the instrumentation to be installed on the Peach Bottom Unit 2 replacement steam dryer (shown in Figure 1-1). This dryer will be the first of the two installed. The Peach Bottom Unit 2 steam dryer will be considered a "Prototype" design consistent with the U.S. Nuclear Regulatory Commision (NRC) document Regulatory Guide 1.20, "Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing" (Reference 1).
]a,c a,c Figure 1-1 [ Ia,C WCAP-17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 2-1 2 INSTRUMENTATION OVERVIEW I
WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-1 3 DATA ACQUISITION AND REDUCTION SYSTEM Sections 3.1 through 3.6 address subitems (a) through (f) of Section 2.2, item 1, in Regulatory Guide 1.20 (Reference 1). The material is limited to description of direct steam dryer instrumentation.
3.1 INSTRUMENT SPECIFICATIONS Consistent with the guidance contained in RG 1.20 (Reference 1), this section describes the accelerometer, pressure transducer, and strain gauge being used to instrument the steam dryer. Table 3-1 summarizes the instruments.
Table 3-1 [ ]a,c I
]a.b,c
[ ]ab,.c 3.2 INSTRUMENT POSITIONS Regulatory Guide 1.20 requests details on the "transducer positions, which should be sufficient to monitor significant lateral, vertical, and torsional structural motions of major reactor internals components in shell, beam, and rigid body modes of vibration, as well as significant hydraulic responses and those parameters that can be used to confirm the input forcing function" (Reference 1). This section describes the criteria WCAP-17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-2 used to identify locations for the accelerometers, pressure transducers, and strain gauges installed on the steam dryer.
a,c WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-3
]a~c 3.3 ENSURING ACQUISITION OF QUALITY DATA Regulatory Guide 1.20 requests details on the "precautions being taken to ensure acquisition of quality data (e.g., optimization of signal-to-noise ratio, relationship of recording times to data reduction requirements, choice of instrumentation system)" (Reference 1).
]a.c 3.4 ONLINE DATA EVALUATION SYSTEM Regulatory Guide 1.20 requests details on the "online data evaluation system to provide immediate verification of general data quality" (Reference 1).
WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-4 ia,b,c 3.5 DETERMINING FREQUENCY, MODAL CONTENT, AND MAXIMUM VALUES Regulatory Guide 1.20 requests details on the "procedures for determining frequency, modal content, and maximum values of response" (Reference 1).
[ ]a~c 3.6 BIAS ERRORS AND RANDOM UNCERTAINTIES Regulatory Guide 1.20 requests details on "all bias errors (such as model underprediction) and random uncertainties (such as instrumentation error) associated with the instrumentation and data acquisition systems" (Reference 1).
[
]a, WCAP- 17639-NP February 2014 Revision 3
WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-1 4 REFERENCES
- 1. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20, Revision 3, "Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing," March 2007.
- 2. Deleted.
- 3. WCAP-17609-P, Revision 2, "Peach Bottom Units 2 and 3 Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads," February 2014. (Westinghouse Proprietary Class 2)
WCAP- 17639-NP February 2014 Revision 3
