ML15329A287

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PUR-1 Digital IC Upgrade - NRC Phase 0 Meeting - November 6 2015
ML15329A287
Person / Time
Site: Purdue University
Issue date: 11/06/2015
From:
Purdue University
To:
Division of Policy and Rulemaking
Montgomery C
Shared Package
ML15300A587 List:
References
Download: ML15329A287 (33)


Text

PUR1 - Instrumentation and Control Upgrade November 6, 2015

Current I&C Overview Four channels make up the reactor monitoring equipment Fission Chamber Compensated Ionization Chamber Uncompensated Ionization Chamber Two channels excluding the safety channel must be on-scale at all times Low Power - Startup Channel, Linear Channel High Power - Log-N, Linear Channel 2

Current I&C Overview 3

Current I&C Overview 4

Current I&C Overview 5

Current I&C Overview 6

General Outline Console Upgrade Desire to go to a digital system Reactor Reliability Implementation time Improved data acquisition Interface with future applications Currently exploring vendors Expected final contract on an hour-by-hour basis 7

Approach to Regulatory Implementation

10 CFR 50.90 vs 10 CFR 50.59

  • A licensee should obtain a license amendment pursuant to 10 CFR 50.90 if the change would result in an increase in the likelihood or consequence of an accident or introduce a previously unanalyzed accident. - ISG for NUREG 1537 Part I
  • Result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the final safety analysis report (as updated) - 10 CFR 50.59 (c)(2)(i)
  • Result in a departure from a method of evaluation described in the FSAR (as updated) used in establishing the design bases or in the safety analyses. - 10 CFR 50.59 (c)(2)(viii) 9

Review of PUR1 Tech Specs

Review of PUR1 Tech Specs Safety Limits - Fuel Temperature The fuel and cladding temperatures shall not exceed 530 ° Change of Instrumentation and control will not affect this tech spec With 12 kW power uprate, expected maximum fuel temperature is around 45 ° 11

Review of PUR1 Tech Specs Limiting Safety System Setting Measured value of the power level scram shall be no higher than 12.0 kW Onset of Nucleate Boiling is calculated to be ~95 kW Change of I&C will not affect this tech spec 12

Review of PUR1 Tech Specs Limiting Condition for Operation - Reactivity Limits Shutdown margin of at least 0.01 /

No experiments with worth greater than 0.004% /

No moveable experiments with worth greater than 0.003% /

Change of I&C will not affect this tech spec 13

Review of PUR1 Tech Specs Reactor Safety System The time from the initiation of a scram condition in the scram circuit until the shim-safety rod reaches the rod lower limit switch shall not exceed one second.

Must be met by new control system 14

Review of PUR1 Tech Specs Reactor Safety System Scram and Setback Setpoints New system must be shown to perform at an acceptable frequency of success 15

Review of PUR1 Tech Specs Primary Coolant Conditions Primary coolant pH shall be maintained at an average over one year of 5.5 +/- 1.0 Primary coolant resistivity shall be maintained at a value greater than 330 Primary Coolant shall be at least 13 feet above core New I&C will support this surveillance through digital interface 16

Review of PUR1 Tech Specs Confinement Negative Pressure of at least 0.05 in of water All doors shall remain closed except as needed for access All inlet and exhaust ducts shall contain a HEPA filter Dampers in ventilation capable of being closed New I&C will support this through digital interface 17

Review of PUR1 Tech Specs Experimental Reactivity Limits Various requirements on experimental reactivity limits and temperatures Experiments will not be affected by new I&C 18

Review of PUR1 Tech Specs Surveillance Requirements Rod worth to be measured every 2.5 years Calibration of reactor safety channels at least every 15 months Calibration of radiation monitoring every 15 months Verification of Rod Drop Times Will not be affected by new I&C 19

Safety Analysis Report (SAR) Update

  • Expect to have several months of operation at this level before completion of digital upgrade
  • All License Amendment Requests will be submitted off of this SAR 20

Description of Proposed System

Description of Proposed System Overview Digital Neutron Flux Monitoring System covering all ranges of operation, Startup, Intermediate, Power and Wide Range New detectors included in upgrade RTP 3000 TAS Platform R*TIME Server and Viewer Software 22

Description of Proposed System Overview Startup and Intermediate Range Monitoring Using CIC Power Range Monitoring Using UIC Wide Range Monitoring Using FC RTP 3000 TAS System 23

Description of Proposed System Overview Drive Assembly Interface Electronics RMS Systems Interface HVAC System Interface Makeup Water Interface Water Chemistry Sensors 24

Description of Proposed System Reused Items Reused Equipment Racks Console and Hallway Scram Buttons Operator Console Keylock Switch 25

Description of Proposed System System Interface Main Interface between system and operator will be a digital screen using R*TIME Layout and Final Design to be determined following vendor decision Design lockdown early 2016 for LAR submission 26

Functional and Safety Analysis

Functional and Safety Analysis Failure Modes of New System Old reactor control system allowed for a Scram on any of the active channels Same to be true for new design No requirement for 2/3 or 2/4 logic 28

Functional and Safety Analysis Time Dependencies Current requirement is for full rod insertion in less than one second Design, analysis, and testing will ensure this requirement is met 29

Functional and Safety Analysis Operator Emergency Shutdown Identical circuitry with console and hallway scrams to be used Loss of power in any system also will initiate scram Removal of operator key to remove magnet power 30

Schedule For Submitting License Amendment Request (LAR)

Schedule for Submitting LAR Proposed Vendor Timeline Project Item Date of Completion Phase 0 Meeting NRC November 6 Final Contract In Place November 9 Chosen Vendor Visit November 16 System Functional Requirements Document Finalized December 23 Hardware Design Finalized January 30 Final hardware and software design package complete February 28 License Amendment Request Sent to NRC March 18 Software Ready for Integration May 1 Factory Acceptance Testing Complete June 30 Delivery of all Hardware and Software (excluding detectors) July 30 License Amendment Request Approved by NRC September Startup and Acceptance Testing September/October 32

PUR1 - Instrumentation and Control Upgrade November 6, 2015

PUR1 - Instrumentation and Control Upgrade November 6, 2015

Current I&C Overview Four channels make up the reactor monitoring equipment Fission Chamber Compensated Ionization Chamber Uncompensated Ionization Chamber Two channels excluding the safety channel must be on-scale at all times Low Power - Startup Channel, Linear Channel High Power - Log-N, Linear Channel 2

Current I&C Overview 3

Current I&C Overview 4

Current I&C Overview 5

Current I&C Overview 6

General Outline Console Upgrade Desire to go to a digital system Reactor Reliability Implementation time Improved data acquisition Interface with future applications Currently exploring vendors Expected final contract on an hour-by-hour basis 7

Approach to Regulatory Implementation

10 CFR 50.90 vs 10 CFR 50.59

  • A licensee should obtain a license amendment pursuant to 10 CFR 50.90 if the change would result in an increase in the likelihood or consequence of an accident or introduce a previously unanalyzed accident. - ISG for NUREG 1537 Part I
  • Result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the final safety analysis report (as updated) - 10 CFR 50.59 (c)(2)(i)
  • Result in a departure from a method of evaluation described in the FSAR (as updated) used in establishing the design bases or in the safety analyses. - 10 CFR 50.59 (c)(2)(viii) 9

Review of PUR1 Tech Specs

Review of PUR1 Tech Specs Safety Limits - Fuel Temperature The fuel and cladding temperatures shall not exceed 530 ° Change of Instrumentation and control will not affect this tech spec With 12 kW power uprate, expected maximum fuel temperature is around 45 ° 11

Review of PUR1 Tech Specs Limiting Safety System Setting Measured value of the power level scram shall be no higher than 12.0 kW Onset of Nucleate Boiling is calculated to be ~95 kW Change of I&C will not affect this tech spec 12

Review of PUR1 Tech Specs Limiting Condition for Operation - Reactivity Limits Shutdown margin of at least 0.01 /

No experiments with worth greater than 0.004% /

No moveable experiments with worth greater than 0.003% /

Change of I&C will not affect this tech spec 13

Review of PUR1 Tech Specs Reactor Safety System The time from the initiation of a scram condition in the scram circuit until the shim-safety rod reaches the rod lower limit switch shall not exceed one second.

Must be met by new control system 14

Review of PUR1 Tech Specs Reactor Safety System Scram and Setback Setpoints New system must be shown to perform at an acceptable frequency of success 15

Review of PUR1 Tech Specs Primary Coolant Conditions Primary coolant pH shall be maintained at an average over one year of 5.5 +/- 1.0 Primary coolant resistivity shall be maintained at a value greater than 330 Primary Coolant shall be at least 13 feet above core New I&C will support this surveillance through digital interface 16

Review of PUR1 Tech Specs Confinement Negative Pressure of at least 0.05 in of water All doors shall remain closed except as needed for access All inlet and exhaust ducts shall contain a HEPA filter Dampers in ventilation capable of being closed New I&C will support this through digital interface 17

Review of PUR1 Tech Specs Experimental Reactivity Limits Various requirements on experimental reactivity limits and temperatures Experiments will not be affected by new I&C 18

Review of PUR1 Tech Specs Surveillance Requirements Rod worth to be measured every 2.5 years Calibration of reactor safety channels at least every 15 months Calibration of radiation monitoring every 15 months Verification of Rod Drop Times Will not be affected by new I&C 19

Safety Analysis Report (SAR) Update

  • Expect to have several months of operation at this level before completion of digital upgrade
  • All License Amendment Requests will be submitted off of this SAR 20

Description of Proposed System

Description of Proposed System Overview Digital Neutron Flux Monitoring System covering all ranges of operation, Startup, Intermediate, Power and Wide Range New detectors included in upgrade RTP 3000 TAS Platform R*TIME Server and Viewer Software 22

Description of Proposed System Overview Startup and Intermediate Range Monitoring Using CIC Power Range Monitoring Using UIC Wide Range Monitoring Using FC RTP 3000 TAS System 23

Description of Proposed System Overview Drive Assembly Interface Electronics RMS Systems Interface HVAC System Interface Makeup Water Interface Water Chemistry Sensors 24

Description of Proposed System Reused Items Reused Equipment Racks Console and Hallway Scram Buttons Operator Console Keylock Switch 25

Description of Proposed System System Interface Main Interface between system and operator will be a digital screen using R*TIME Layout and Final Design to be determined following vendor decision Design lockdown early 2016 for LAR submission 26

Functional and Safety Analysis

Functional and Safety Analysis Failure Modes of New System Old reactor control system allowed for a Scram on any of the active channels Same to be true for new design No requirement for 2/3 or 2/4 logic 28

Functional and Safety Analysis Time Dependencies Current requirement is for full rod insertion in less than one second Design, analysis, and testing will ensure this requirement is met 29

Functional and Safety Analysis Operator Emergency Shutdown Identical circuitry with console and hallway scrams to be used Loss of power in any system also will initiate scram Removal of operator key to remove magnet power 30

Schedule For Submitting License Amendment Request (LAR)

Schedule for Submitting LAR Proposed Vendor Timeline Project Item Date of Completion Phase 0 Meeting NRC November 6 Final Contract In Place November 9 Chosen Vendor Visit November 16 System Functional Requirements Document Finalized December 23 Hardware Design Finalized January 30 Final hardware and software design package complete February 28 License Amendment Request Sent to NRC March 18 Software Ready for Integration May 1 Factory Acceptance Testing Complete June 30 Delivery of all Hardware and Software (excluding detectors) July 30 License Amendment Request Approved by NRC September Startup and Acceptance Testing September/October 32

PUR1 - Instrumentation and Control Upgrade November 6, 2015