|
|---|
Category:Report
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022
Pressure and Temperature Limits Report Revision
L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022
Steam Generator Inspection Report- Fall 2021 Refueling Outage
IR 05000334/20210052021-09-0101 September 2021
Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005)
ML21131A0242021-05-17017 May 2021
Review of Reactor Pressure Vessel Capsule Y Analysis Report
ML21055A0582021-03-10010 March 2021
Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports
L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021
Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks
ML21026A3372021-01-26026 January 2021
Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage
L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020
Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic
ML21127A1652020-07-17017 July 2020
ODCM: Index, Matrix and History of ODCM Changes
L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020
ODCM: Liquid Effluents
ML21127A1482020-07-17017 July 2020
ODCM: Controls for RETS and REMP Programs
L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020
CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency
ML19280A0382019-10-22022 October 2019
Ti 2515-191 Summary of Findings
ML21127A1562019-07-17017 July 2019
ODCM: Gaseous Effluents
ML19051A1092019-02-20020 February 2019
LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019
Emergency Response Data System Data Point Library Update
L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018
Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.
ML21127A1592018-01-22022 January 2018
ODCM: Radiological Environmental Monitoring Program
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017
Pressure and Temperature Limits Reports, Revisions 8 and 9
L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017
Mitigating Strategies Assessment (MSA) for Flooding
ML17213A0162017-05-11011 May 2017
Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1
ML17213A0172017-05-11011 May 2017
Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1
ML17024A0362016-12-31031 December 2016
Operating Data Report for 2016
ML16312A3112016-11-0707 November 2016
Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review...
L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016
Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair
L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016
Report of Facility Changes, Tests and Experiments
L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016
Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016
Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information
L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016
Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time
L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015
Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..
ML16277A1142015-10-28028 October 2015
ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels.
ML15274A3072015-10-0505 October 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review
L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015
Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
ML15132A4962015-05-22022 May 2015
Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620)
ML16277A1222015-04-20020 April 2015
ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points.
ML15119A1042015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4
L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4
ML21127A1582015-02-11011 February 2015
ODCM: Bases for ODCM Controls
ML16277A1152015-01-30030 January 2015
ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints.
ML15027A2352015-01-28028 January 2015
Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302)
L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014
First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In
L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014
Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
ML21127A1442014-10-0707 October 2014
ODCM: Information Related to 40 CFR 190
L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014
Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML14224A5772014-07-31031 July 2014
SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report.
ML14224A5762014-07-31031 July 2014
SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions.
ML14224A5752014-06-25025 June 2014
R17 Steam Generator F* (F Star) Report
ML14009A0892014-02-10010 February 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident
2023-08-07
[Table view]
Category:Technical
MONTHYEARL-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022
Pressure and Temperature Limits Report Revision
L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022
Steam Generator Inspection Report- Fall 2021 Refueling Outage
ML21026A3372021-01-26026 January 2021
Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage
L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020
ODCM: Liquid Effluents
ML21127A1652020-07-17017 July 2020
ODCM: Index, Matrix and History of ODCM Changes
ML21127A1482020-07-17017 July 2020
ODCM: Controls for RETS and REMP Programs
L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020
CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency
ML21127A1562019-07-17017 July 2019
ODCM: Gaseous Effluents
ML19051A1092019-02-20020 February 2019
LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
ML21127A1592018-01-22022 January 2018
ODCM: Radiological Environmental Monitoring Program
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017
Pressure and Temperature Limits Reports, Revisions 8 and 9
L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017
Mitigating Strategies Assessment (MSA) for Flooding
ML17213A0172017-05-11011 May 2017
Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1
ML17213A0162017-05-11011 May 2017
Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1
L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016
Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair
ML16277A1142015-10-28028 October 2015
ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels.
ML16277A1222015-04-20020 April 2015
ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points.
ML15119A1042015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4
L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4
ML21127A1582015-02-11011 February 2015
ODCM: Bases for ODCM Controls
ML16277A1152015-01-30030 January 2015
ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints.
ML21127A1442014-10-0707 October 2014
ODCM: Information Related to 40 CFR 190
ML14224A5772014-07-31031 July 2014
SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report.
ML14224A5762014-07-31031 July 2014
SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions.
ML14224A5752014-06-25025 June 2014
R17 Steam Generator F* (F Star) Report
ML13364A1662014-01-29029 January 2014
Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14029A0212014-01-28028 January 2014
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Beaver Valley Power Station, Units 1 and 2, TAC Nos.: MF0841 and MF0842 (Revision 2)
ML14030A1352014-01-27027 January 2014
WCAP-17790-NP, Revision 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals.
ML14030A1342014-01-27027 January 2014
WCAP-17789-NP, Rev. 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals.
L-13-387, Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Page 284 Through Page T-422013-11-30030 November 2013
Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Page 284 Through Page T-42
ML14002A0902013-11-30030 November 2013
Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Cover Through Page 283
ML13126A0422013-04-15015 April 2013
RTL A9.630F, 2012 Annual Environmental Operating Report, (Non-Radiological)
ML13126A0392013-04-12012 April 2013
RTL A9.690E, 2012 Radioactive Effluent Release Report and 2012 Annual Radiological Environmental Operating Report, Enclosure 1, Cover Through Enclosure 2, Attachment 3
ML13028A4712013-01-14014 January 2013
SG-SGMP-13-2, Rev. 1, Beaver Valley Unit 2, End-of-Cycle 16 Voltage-Based Repair Criteria 90-Day Report.
ML13008A0482012-10-31031 October 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-by Checklists, Sheet 79 of 123 Through End
ML13008A0472012-10-31031 October 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-by Checklists, Page C-1 Through Sheet 78 of 123
ML16277A1162012-04-26026 April 2012
ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors.
ML16277A1232012-04-26026 April 2012
ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors.
ML13151A0602011-09-30030 September 2011
Enclosure C, WCAP-16527-NP, Analysis of Capsule X from Firstenergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program, Supplement 1, Revision 1, Dated September 2011
ML13151A0592011-09-30030 September 2011
Enclosure B, WCAP-15571, Analysis of Capsule Y from Beaver Valley, Unit 1 Reactor Vessel Radiation Surveillance Program, Supplement 1, Revision 2, Dated September 2011
ML16277A1242011-08-10010 August 2011
ERS-SFL-88-027, Rev. 3, Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B.
ML16277A1172011-08-0909 August 2011
ERS-JTL-99-005, Rev. 3, Unit 1 Letdown Radiation Monitor (RM-1CH-101) Alarm Setpoint Calculation and Emergency Action Level (EAL) ERS-JTL-99-005 21 Value Determination.
ML16277A1272011-08-0707 August 2011
ERS-SMM-11-002, Containment Radiation Monitor Readings Following Clad Damage (FC2 Loss, FC7 Loss, RC2 Loss and CT2 Potential Loss).
ML16277A1182011-08-0707 August 2011
ERS-SMM-11-002, Containment Radiation Monitor Readings Following Clad Damage (FC2 Loss, FC7 Loss, RC2 Loss and CT2 Potential Loss).
L-11-024, Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack2011-02-18018 February 2011
Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack
ML1029404582010-10-18018 October 2010
Holtec Report No: HI-2084175, Licensing Report for Beaver Valley, Unit 2, Rerack.
ML0912102632009-04-0909 April 2009
HI-2084175, Revision 3, Holtec Licensing Report for Beaver Valley, Unit 2 Rerack, Enclosure C
ML0900203862008-12-30030 December 2008
WCAP-16144-NP, Revision 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Beaver Valley Unit 2
ML0829002092008-08-31031 August 2008
WCAP-16158-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Beaver Valley Unit 2
ML0821900132008-08-0707 August 2008
Monthly Operating Reports Second Quarter 2008
2022-07-06
[Table view] |
Text
Letter L-04-153 Enclosure 2 Attachment E Westinghouse Document Number ITS2898, Revision 0 Time Response Failure Analysis (for the Westinghouse 7300 5NRA Card)
Note: The attached document is Westinghouse non-proprietary
Westinghouse Non-Proprietary Class 3 7300 NRA 6D30262 TIME RESPONSE FAILURE ANALYSIS 1TS2898 Revision 0 January 2004 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 0 2004 Westinghouse Electric Company LIC All Rights Reserved ITS2898
TABLE OF CONTENTS 1.0 Introduction and Purpose 4 2.0 References 4 3.0 Component Analysis Method 4 4.0 Component Analysis Results 5 5.0 Detailed Analysis and Results 6 6.0 Conclusion 7 MTS289M
7300 Series RTD AMPLIFIER CARD (6D30262) NRA 1.0 Introduction and Purpose There are sev'eral nuclear control and protection systems built using the 7300 series PC cards. During normal system maintenance, a portion of the system is taken offline and calibrated using a DC calibration method, and then a subsystem time response test Is performed.
This report has two purposes. One purpose is to determine the component failures on the NRA card which could affect the system or card time response, and which are undetectable by the system DC calibration procedure. The second purp6se is t6 provide a summary of the results from the test procedure Ila Cand to compare those results with the previous NRA card [ 3a, which are referenced in [ ]ac. The new NRA card will be shown in this analysis to have a quicker time response than the previous NRA card.
2.0 References
- 1. [ .. c
- 2. [.c
- 3. Ia c 3.0 Component Analysis Method To identify failures that will result in an increase in the time response of the card, a Failure Modes and Effect Analysis (FMEA) was performed. For each component on the circuit card, failure modes and their associated effects were identified. From now on in this document the term failure Is used to describe a component that is shorted, open or changed in value. The types of failures that were analyzed are listed for the following components that are used in 7300 cards.
Resistor- A resistor can fail [ ]PC.
Diode - A diode can fail [ alc Zener Diode - A zener diode can falll Transistor- Transistors can fail { Ia.
Op Amp or other linear IC -The Input stage of op amps and other linear devices can [
apc 1S2898
the output losses part of its drive capability. They can also have a failure [
3axc Digital IC - A digital IC can fail to [ Ja.c Capacitor - A capacitor can fail I la.c Inductor- An inductor can fail [ ]a.c 4.0 Component Analysis Results Components are in one of three categories. The first category Is components that could fail or change in value and [ ]8C the time response of the card without being [
] If a component falls into this category, then the [ rc. The second category is components that could fail and have 1 Ja.
Category two [ la c in the calculations of total time response because if the component fails there is still [ la on the time response. The third category is components that could fail and have an [
]2c the time response. Category three [ ]3.C in the calculations of total time response because if the component fails then the [ la c will be changed by so much that the card will not be able to be [
]anc.
Category 1:
Components that could fail and [ la3c the card time response and are not
[ ]~
Capacitors: [ aC.
Resistors: a'c Category 2:
As previously mentioned, there are many components that [
]I.C the time response of the circuit.
The [ ]azc the time response of this card because they are [ ]a.C of the output. If a component is
[ Jac¢ signal then there can [
ra ¢. There could be a loss of [
la but there will [
The following Is a list of components that are Included in this category.
Capacitors: 1 Jac Resistors: [ ]a c Diodes: [ ]atc Inductors: [ jazc IC: [ C Transistor. ]3.c ITS2893
The following is a list of components that [ jayc in other parts of the NRA circuit:
Capacitors: [
r3c Resistors: 1 Inductors: [ ]apc Category 3:
All other components are in this category. Ifthese components fail [
Jarc. Therefore these components will [
1a¢. These components will [
Iac card.
The following is a list of components that affect the 1 Ialc:
]a,c Resistors:
Ia.c IC: [
Transistors: [ Iac Diodes: I Ia.c 5.0 Detailed Analysis & Results I
1T32898
a,c ac Figure 1 - NRA Card [ Iac ITS289S
la-c Figure 2 - NRA Card [ Iac
-.c Figure 3 - NRA Card [ ac 1TS2898
- ;c Figure 4 - NRA Card [
Figure 5 - NRA Card [ Iae ITS2898
-- Ia-.c a,c Figure 6 - NRA Card [
Figure 7 - NRA Card [ Ia,c ITS2S
ac Figure 8 - NRA Card [ I3,c Figure 9 - NRA Card [ Iac I1S=
Sac Figure 10- NRA Card [ ]ac
- a. c Figure 11 - NRA Card [ Ia~c ITS2898
-I a,c Figure 12- NRA Card [ Ia,c I a,c Figure 13 - NRA Card [
a,c Figure 14-NRACard[ ]a,c a1.
c
]a,c Figure 15 - NRA Card [
IT2S92
IaC Figure 16 - NRA Card [ ]agc Below is a summary of the time response of each figure above. The longest time response will only be looked at when comparing [
Iac Component Total Time Response Time Response due to the component change I
]a,c ITS2B9S
6.0 Conclusion I
lac 12898
Letter L-04-153 Enclosure 2 Attachment F Westinghouse Document Number 1TS2899, Revision 0 NRA Card Time Response Test Procedure (for the Westinghouse 7300 5NRA Card)
I , " . I UIi i , ' -' -'" z Note: The attached document is Westinghouse non-proprietary
Westinghouse Non-Proprietary Class 3 7Tme Response Tesf Procedure 6D30262 7300 NRA 6D30262 NRA Card Time Response Test Procedure 1TS2899 Revision 0 January 2004 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 0 2004 Westingbouse Electric Company LLC All Rights Reserved 1TS2899 I
Time Response Test Ptocedure 6D00262 Revision History:
1/2004 Initial Issue Daniel Shubert 1TS2899 2
lime Response Test Procedure 6D30262 7300 Series RTD AMPLIFIER CARD (6D30262) NRA 1.0 Test Objectives This test procedure will provide numerical results on the time response for the 7300 Series RTD Amplifier (NRA) Card. it will evaluate the time response when [
rt. The l
]ac in the value of the component. Time response results will be determined by
[ jS.C and viewed by an oscilloscope. The [ a will then be compared to measure how long it takes 2.0 References
- 1. 1 c
- 2. 1
]a~
- 3. l ]awt 3.0 Test Equipment 3.1 The following test instrumentation, equipment and fixture are required in order to perform this test procedure:
-7300 universal test box
-Multichannel oscilloscope (capable of storing traces)
-Fluke Digital Multimeter or other high precision multimeter (with 4-112 digits and accuracy specified to /l 0.01% of span.
-Capacitance Meter
-Resistance RTD Decade Box
-All other equipment used In the [ rfor the NRA card 1TS2899 3
Time Response Test Procedure 6D30262 4.0 Functional Test 4.1 Perform functional test procedure, I rc 4.2 After completing the functional test procedure [
PC I
Make the following connections to the universal test box pins:
P8~C 4.3 I3rc 4.4 Iaxc 4.5 1 lawI 4.6 1
'C 4.7 1 r
4.8 [
ITS2899 4
T7me Response Best Procedure 6D30262 JA.c 4.9 1 I8.c 4.10 [
4.11 l
)a.c 4.12 1 Ialc 1TS2899 5
Time Response Test Procedure 6D30262 5.0 Data Sheet 4.1 Passed - Failed _
4.4 Time Response of NRA Card (+ step input) _ _ms 4.5 Time Response of NRA Card (- step input) ----- ms 4.6 [ lx' yes_ no Time Response of NRA Card (+ step input) _ _ms Time Response of NRA Card (- step input) ___ms 4.7 [ )ac yes no Time Response of NRA Card (+ step input) _ _ms Time Response of NRA Card (- step input) ___-ms 4.8 [ ]' yes _ no Time Response of NRA Card (+ step input) ___--ms Time Response of NRA Card (- step input) _ _ms 4.9 1 I" yes _ no_
Time Response of NRA Card (+ step input) _ _ms Time Response of NRA Card (- step input) ------_ms 4.10 ] c yes_ no Time Response of NRA Card (+ step input) _-----ms Time Response of NRA Card (- step input) ms 4.11 [ ]" yes - no Time Response of NRA Card (+ step input) _ _ms Time Response of NRA Card (- step Input) _ _ms 4.12 [ loC yes _ no _
Time Response of NRA Card (+ step input) _ _ms Time Response of NRA Card (-step input) _ _ms 1TS2899 6
Letter L-04-153 Enclosure 2 Attachment G Westinghouse Drawing 6D30262, Revision 0 (for the Westinghouse 7300 5NRA Card) 2W Note: The attached document is Westinghouse non-proprietary
Letter L-04-153 Enclosure 2 Attachment H Westinghouse Drawing 6D30262, Revision 1 (for the Westinghouse 7300 6NRA Card)
Note: The attached document is Westinghouse non-proprietary