ML20188A038

Revised Table of Contents for Psu Breazeale Reactor Technical Specifications Pending Approval of Ventilation System Upgrade

ML20188A038
Person / Time
Site:	Breazeale Nuclear Reactor
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 65 The Pennsylvania State University College of Engineering College of Engineering Radiation Science and Engineering Center Phone: 814-865-6351 Breazeale Nuclear Reactor Fax: 814-863-4840 RADIATION SCIENCE & University Park, PA 16802-2301 ENGINEERING CENTER BREA ZEALE Nuclear Reactor US NRC ATTN: Document Control Desk Washington, DC 20555-0001 3 July 2020

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 INTRODUCTION

1 I.I Definitions 1 2.0 SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING 8 2.1 Safety Limit - Fuel Element Temperature 8 2.2 Limiting Safety System Setting (LSSS) 9 3.0 LIMITING CONDITIONS FOR OPERATION 10 3.1 Reactor Core Parameters 10 3.1.1 Non-Pulse Mode Operation 10 3.1 .2 Reactivity Limitation 11 3.1.3 Shutdown Margin 12 3.1.4 Pulse Mode Operation 13 3.1.5 Core Configuration Limitation 14 3.1.6 TRIGA Fuel Elements 15 3.2 Reactor Control and Reactor Safety System 16 3.2.1 Reactor Control Rods 16 3.2.2 Manual Control and Automatic Control 17 3.2.3 Reactor Contro l System 18 3.2.4 Reactor Safety System and Reactor Interlocks 19 3.2.5 Core Loading and Unloading Operation 21 3.2.6 SCRAM Time 21 3.3 Coolant System 22 3.3.1 Coolant Level Limits 22 3.3 .2 Detection of Leak or Loss of Coolant 23 3.3.3 Fission Product Activity 23 3.3.4 Pool Water Supply for Leak Protection 24 3.3 .5 Coolant Conductivity Limits 24 3.3.6 Coolant Temperature Limits 25 3.4 Confinement 25 3.5 Engineered Safety Features -Ventilation Systems 26 3.6 Radiation Monitoring System 27 3.6.1 Radiation Monitoring Information 27 3.6.2 Evacuation Alarm 28 3.6 .3 Argon-41 Discharge Limit 28 3.6.4 As Low As Reasonably Achievable (ALARA) 29 3.7 Limitations of Experiments 29

- I -

TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)

FACILITY LICENSE NO . R-2 4.0 SURVEILLANCE REQUIREMENTS 32 4.1 Reactor Parameters 32 4.1 . 1 Reactor Power Calibration 32 4.1.2 Reactor Excess Reactivity 32 4.1.3 TRIGA Fuel Elements 33 4.2 Reactor Control and Safety System 34 4.2. 1 Reactivity Worth 34 4.2.2 Reactivity Insertion Rate 34 4.2.3 Reactor Safety System 35 4.2.4 Reactor Interlocks 36 4.2.5 Overpower SCRAM 37 4.2.6 Transient Rod Test 37 4.3 Coolant System 38 4.3 . 1 Fire Hose Inspection 38 4.3 .2 Pool Water Temperature 39 4.3.3 Pool Water Conductivity 39 4.3.4 Pool Water Level Alarm 40 4.4 Confinement 40 4.5 Ventilation Systems 41 4.6 Radiation Monitoring System and Effluents 41 4.6. 1 Radiation Monitoring System and Evacuation Alarm 41 4.6.2 Argon-41 42 4.6.3 ALARA 42 4.7 Experiments 43 5.0 DESIGN FEATURES 44 5.1 Reactor Fuel 44 5.2 Reactor Core 44 5.3 Control Rods 45 5.4 Fuel Storage 45 5.5 Reactor Bay and Exhaust Systems 46 5.6 Reactor Pool Water Systems 46

- II -

TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)

FACILITY LICENSE NO. R-2 6.0 ADMINISTRATIVE CONTROLS 47 6.1 Organization 47

6. l.l Structure 47 6.1.2 Responsibility 47 6.1.3 Staffing 49 6.1.4 Selection and Training of Personnel 49 6.2 Review and Audit so 6.2.1 Safeguards Committee Composition 50 6.2.2 Charter and Rules 50 6.2.3 Review Function 51 6.2.4 Audit 51 6.3 Operating Procedures 52 6.4 Review and Approval of Experiments 53 6.5 Required Action 53 6.5 .1 Action to be Taken in the Event the Safety Limit is Exceeded 53 6.5.2 Action to be Taken in the Event of a Reportable Occurrence 54 6.6 Reports 54 6.6.1 Operating Reports 54 6.6.2 Special Reports 55 6.7 Records 56 6.7.1 Records to be Retained for at Least Five Years 56 6.7.2 Records to be Retained for at Least One Training Cycle 56 6.7.3 Records to be Retained for the Life of the Reactor Facility 56

- iii -

TECHNICAL SPECIFICATIONS: PENN STATE BREAZEALE REACTOR (PSBR)

FACILITY LICENSE NO. R-2

1.0 INTRODUCTION

1 1.1 Definitions 2.0 SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING 8 2.1 Safety Limit - Fuel Element Temperature 8 2.2 Limiting Safety System Setting (LSSS) 9 3.0 LIMITING CONDITIONS FOR OPERATION 10 3.1 Reactor Core Parameters 10 3.1.1 Non-Pulse Mode Operation IO 3.1.2 Reactivity Limitation II 3.1.3 Shutdown Margin 12 3.1.4 Pulse Mode Operation 13 3.1.5 Core Configuration Limitation 14 3.1.6 TRIGA Fuel Elements 15 3.2 Reactor Control and Reactor Safety System 16 3.2.1 Reactor Control Rods 16 3.2.2 Manual Control and Automatic Control 17 3.2.3 Reactor Control System 18 3.2.4 Reactor Safety System and Reactor Interlocks 19 3.2.5 Core Loading and Unloading Operation 21 3.2.6 SCRAM Time 21 3.3 Coolant System 22 3.3.1 Coolant Level Limits 22 3.3.2 Detection of Leak or Loss of Coolant 23 3.3.3 Fission Product Activity 23 3.3.4 Pool Water Supply for Leak Protection 24 3.3 .5 Coolant Conductivity Limits 24 3.3 .6 Coolant Temperature Limits 25 3.4 Confinement 25 3.5 Engineered Safety Features Faeility E:thaust S)*stem and Emergeeey Exhaust System Ventilation Systems 26 3.6 Radiation Monitoring System 27 3.6.1 Radiation Monitoring Information 27 3.6.2 Evacuation Alarm 28 3.6.3 Argon-41 Discharge Limit 28 3.6.4 As Low As Reasonably Achievable (ALARA) 29 3.7 Limitations of Experiments 29

- I -

TECHNICAL SPECIFICATIONS: PENN STA TE BREAZEALE REACTOR (PSBR)

FACILITY LICENSE NO . R-2 4.0 SURVEILLANCE REQUIREMENTS 32 4.1 Reactor Parameters 32 4.1.1 Reactor Power Calibration 32 4.1.2 Reactor Excess Reactivity 32 4.1.3 TRJGA Fuel Elements 33 4.2 Reactor Control and Safety System 34 4.2.1 Reactivity Worth 34 4.2.2 Reactivity Insettion Rate 34 4.2.3 Reactor Safety System 35 4.2.4 Reactor Interlocks 36 4.2.5 Overpower SCRAM 37 4.2 .6 Transient Rod Test 37 4.3 Coolant System 38 4.3 . 1 Fire Hose Inspection 38 4.3 .2 Pool Water Temperature 39 4.3 .3 Pool Water Conductivity 39 4.3.4 Pool Water Level Alarm 40 4.4 Confinement 40 4.5 Faeility Exhaust Systent and Emet"geney Exhaust System Ventilation Systems 41 4.6 Radiation Monitoring System and Effluents 41 4.6.1 Radiation Monitoring System and Evacuation Alarm 41 4.6.2 Argon-41 42 4.6.3 ALARA 42 4.7 Experiments 43 5.0 DESIGN FEATURES 44 5.1 Reacto1* Fuel 44 5.2 Reactor Core 44 5.3 Control Rods 45 5.4 Fuel Storage 45 5.5 Reactor Bay and Exhaust Systems 46 5.6 Reactor Pool Water Systems 46

- II -

TECHNICAL SPECIFICATIONS : PENN STATE BREAZEALE REACTOR (PSBR)

FACILITY LICENSE NO. R-2 6.0 ADMINISTRATIVE CONTROLS 47 6.1 Organization 47

6. l.l Structure 47 6.1.2 Responsibility 47 6.1.3 Staffing 49 6.1.4 Selection and Training of Personnel 49 6.2 Review and Audit 50 6.2.1 Safeguards Committee Composition 50 6.2.2 Charter and Rules 50 6.2.3 Review Function 51 6.2.4 Audit 51 6.3 Operating Procedures 52 6.4 Review and Approval of Experiments 53 6.5 Required Action 53 6.5.1 Action to be Taken in the Event the Safety Limit is Exceeded 53 6.5 .2 Action to be Taken in the Event of a Reportable Occurrence 54 6.6 Reports 54 6.6.1 Operating Reports 54 6.6.2 Special Reports 55 6.7 Records 56 6.7.1 Records to be Retained for at Least Five Years 56 6.7.2 Records to be Retained for at Least One Training Cycle 56 6.7.3 Records to be Retained for the Life of the Reactor Facility 56

- 111 -