ML20188A038
| ML20188A038 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 07/03/2020 |
| From: | Geuther J Pennsylvania State Univ, University Park, PA |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EPID: L-2019-LLA-0089 | |
| Download: ML20188A038 (7) | |
Text
PennState College of Engineering RADIATION SCIENCE &
ENGINEERING CENTER US NRC ATTN: Document Control Desk Washington, DC 20555-0001 3 July 2020 The Pennsylvania State University College of Engineering Radiation Science and Engineering Center Breazeale Nuclear Reactor University Park, PA 16802-2301 Phone: 814-865-6351 Fax:
814-863-4840 65 BREA ZEALE Nuclear Reactor
SUBJECT:
Revised table of contents for PSU Breazeale Reactor Technical Specifications pending approval of ventilation system upgrade (EPID No. L-2019-LLA-0089)
To Whom It May Concern:
The proposed revisions to the PSU Breazeale Reactor Technical Specifications include changes to two section titles. The Table of Contents has been amended to reflect those changes. Specifically, Section 3.5 has been changed from "Engineered Safety Features - Facility Exhaust System and Emergency Exhaust System "to "Engineered Safety Features - Ventilation Systems," and Section 4.5 has been changed from "Facility Exhaust System and Emergency Exhaust System" to "Ventilation Systems."
The clean and mark-up copies of the revised Table of Contents are attached. Please contact me with any questions you may have about these documents.
Sincerely, Ire~
Associate Director for Operations Radiation Science and Engineering Center Pennsylvania State University Cc:
X. Yin (NRC)
K. Onlii (PSU)
Attachments:
Revised table of contents for proposed Technical Specifications, clean copy Revised table of contents for proposed Technical Specifications, markup copy College of Engineering An Equal Opportunity University
TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)
FACILITY LICENSE NO. R-2 1.0 I.I 2.0 2.1 2.2 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.2.5 3.2.6 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.4 3.5 3.6 3.6.1 3.6.2 3.6.3 3.6.4
3.7 INTRODUCTION
Definitions SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING Safety Limit - Fuel Element Temperature Limiting Safety System Setting (LSSS)
LIMITING CONDITIONS FOR OPERATION Reactor Core Parameters Non-Pulse Mode Operation Reactivity Limitation Shutdown Margin Pulse Mode Operation Core Configuration Limitation TRIGA Fuel Elements Reactor Control and Reactor Safety System Reactor Control Rods Manual Control and Automatic Control Reactor Control System Reactor Safety System and Reactor Interlocks Core Loading and Unloading Operation SCRAM Time Coolant System Coolant Level Limits Detection of Leak or Loss of Coolant Fission Product Activity Pool Water Supply for Leak Protection Coolant Conductivity Limits Coolant Temperature Limits Confinement Engineered Safety Features -Ventilation Systems Radiation Monitoring System Radiation Monitoring Information Evacuation Alarm Argon-41 Discharge Limit As Low As Reasonably Achievable (ALARA)
Limitations of Experiments
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9 10 10 10 11 12 13 14 15 16 16 17 18 19 2 1 21 22 22 23 23 24 24 25 25 26 27 27 28 28 29 29
TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)
FACILITY LICENSE NO. R-2 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Parameters 4.1.1 Reactor Power Calibration 4.1.2 Reactor Excess Reactivity 4.1.3 TRIGA Fuel Elements 4.2 Reactor Control and Safety System 4.2.1 Reactivity Worth 4.2.2 Reactivity Insertion Rate 4.2.3 Reactor Safety System 4.2.4 Reactor Interlocks 4.2.5 Overpower SCRAM 4.2.6 Transient Rod Test 4.3 Coolant System 4.3.1 Fire Hose Inspection 4.3.2 Pool Water Temperature 4.3.3 Pool Water Conductivity 4.3.4 Pool Water Level Alarm 4.4 Confinement 4.5 Ventilation Systems 4.6 Radiation Monitoring System and Effluents 4.6.1 Radiation Monitoring System and Evacuation Alarm 4.6.2 Argon-41 4.6.3 ALARA 4.7 Experiments 5.0 DESIGN FEATURES 5.1 Reactor Fuel 5.2 Reactor Core 5.3 Control Rods 5.4 Fuel Storage 5.5 Reactor Bay and Exhaust Systems 5.6 Reactor Pool Water Systems
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TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)
FACILITY LICENSE NO. R-2 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization
- 6. l.l Structure 6.1.2 Responsibility 6.1.3 Staffing 6.1.4 Selection and Training of Personnel 6.2 Review and Audit 6.2.1 Safeguards Committee Composition 6.2.2 Charter and Rules 6.2.3 Review Function 6.2.4 Audit 6.3 Operating Procedures 6.4 Review and Approval of Experiments 6.5 Required Action 6.5.1 Action to be Taken in the Event the Safety Limit is Exceeded 6.5.2 Action to be Taken in the Event of a Reportable Occurrence 6.6 Reports 6.6.1 Operating Reports 6.6.2 Special Reports 6.7 Records 6.7.1 Records to be Retained for at Least Five Years 6.7.2 Records to be Retained for at Least One Training Cycle 6.7.3 Records to be Retained for the Life of the Reactor Facility
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TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)
FACILITY LICENSE NO. R-2 1.0 1.1 2.0 2.1 2.2 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.2.5 3.2.6 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6
3.4 INTRODUCTION
Definitions SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING Safety Limit - Fuel Element Temperature Limiting Safety System Setting (LSSS)
LIMITING CONDITIONS FOR OPERATION Reactor Core Parameters Non-Pulse Mode Operation Reactivity Limitation Shutdown Margin Pulse Mode Operation Core Configuration Limitation TRIGA Fuel Elements Reactor Control and Reactor Safety System Reactor Control Rods Manual Control and Automatic Control Reactor Control System Reactor Safety System and Reactor Interlocks Core Loading and Unloading Operation SCRAM Time Coolant System Coolant Level Limits Detection of Leak or Loss of Coolant Fission Product Activity Pool Water Supply for Leak Protection Coolant Conductivity Limits Coolant Temperature Limits Confinement 3.5 Engineered Safety Features Faeility E:thaust S)*stem and Emergeeey Exhaust System Ventilation Systems 26 Radiation Monitoring System Radiation Monitoring Information Evacuation Alarm Argon-41 Discharge Limit 3.6 3.6.1 3.6.2 3.6.3 3.6.4 As Low As Reasonably Achievable (ALARA) 3.7 Limitations of Experiments
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8 9
10 10 IO II 12 13 14 15 16 16 17 18 19 21 21 22 22 23 23 24 24 25 25 27 27 28 28 29 29
TECHNICAL SPECIFICATIONS: PENN ST A TE BREAZEALE REACTOR (PSBR)
FACILITY LICENSE NO. R-2 4.0 4.1 4.1.1 4.1.2 4.1.3 4.2 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 4.2.6 4.3 4.3.1 4.3.2 4.3.3 4.3.4 4.4 4.5 4.6 4.6.1 4.6.2 4.6.3 4.7 5.0 5.1 5.2 5.3 5.4 5.5 5.6 SURVEILLANCE REQUIREMENTS Reactor Parameters Reactor Power Calibration Reactor Excess Reactivity TRJGA Fuel Elements Reactor Control and Safety System Reactivity Worth Reactivity Insettion Rate Reactor Safety System Reactor Interlocks Overpower SCRAM Transient Rod Test Coolant System Fire Hose Inspection Pool Water Temperature Pool Water Conductivity Pool Water Level Alarm Confinement Faeility Exhaust Systent and Emet"geney Exhaust System Ventilation Systems Radiation Monitoring System and Effluents Radiation Monitoring System and Evacuation Alarm Argon-41 ALARA Experiments DESIGN FEATURES Reacto1* Fuel Reactor Core Control Rods Fuel Storage Reactor Bay and Exhaust Systems Reactor Pool Water Systems
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TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)
FACILITY LICENSE NO. R-2 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization
- 6. l.l Structure 6.1.2 Responsibility 6.1.3 Staffing 6.1.4 Selection and Training of Personnel 6.2 Review and Audit 6.2.1 Safeguards Committee Composition 6.2.2 Charter and Rules 6.2.3 Review Function 6.2.4 Audit 6.3 Operating Procedures 6.4 Review and Approval of Experiments 6.5 Required Action 6.5.1 Action to be Taken in the Event the Safety Limit is Exceeded 6.5.2 Action to be Taken in the Event of a Reportable Occurrence 6.6 Reports 6.6.1 Operating Reports 6.6.2 Special Reports 6.7 Records 6.7.1 Records to be Retained for at Least Five Years 6.7.2 Records to be Retained for at Least One Training Cycle 6.7.3 Records to be Retained for the Life of the Reactor Facility
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