ML20133F399
| ML20133F399 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/03/1985 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20133F359 | List: |
| References | |
| 13587-2-L01-100, 13587-2-L1-100, NUDOCS 8508080270 | |
| Download: ML20133F399 (38) | |
Text
h ATTACHMENT 2 Design Criteria 13587-2-L01-100 kM,
'(4410-85-L-0159) 6d 38 Pages GPU SERVICE CORPORATION
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THREE MILE ISLAND - UNIT 2 RECOVERY FACILITIES DESIGN CRITERIA DOCUMENTS COVER SHEET General Section JOB NO:
13587 DISCIPLINE:
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JOB NO.
13587 REV.
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DESIGN CRITERIA DOCUMENTS DISCIPLINE g
j General j
-4g REVISION STATUS SHEET 6
PAGE 1 of 1
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Design Criteria 13587-2-L01-100 TABLE OF CONTENTS PAGE 1.0 GENERAL 1
1.1 Introduction 1
- 1. 2 Project Objectives 1
- 1. 3 Project Concerns 2
2.0 DEFINITIONS 2
2.1 Safe Shutdown Earthquake (SSE) 2 2.2 Operating Basis Earthquake (0BE) 2
- 2. 3 Seismic Category I/Non-Seismic Category I 2
2.4 Design Bases 3
- 2. 5 Safety Related 3
2.6 Important to Safety (ITS) 3 3.0 LICENSING 3
3.1 Introduction 3
3.2 Basic Criteria 4
3.3 Design Conditions 5
3.4 Regulatory Requirements 7
3.5 Industry Codes and Standards 8
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3.6 Safety Assessment 9
4.0 ALARA DESIGN CRITERIA AND CONSIDERATIONS 9
Table 1 Regulatory Guides 10 Table 2 ALARA Items 15 Table 3 Typical Radioactive Piping Classification and Routing 34 Table 4 Radiation Zones 35 i
Rev. 6
Dasign Criteria 13587-2-L01-100 1.0 GENERAL
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1.1 INTRODUCTION
4 1.1.1 This design criteria is applicable only to those facilities and activities for which Bechtel has design responsibility.
1.1. 2 This section of the General Project Design Criteria contains information common to all disciplines.
1.1. 3 The General P.roject Design Criteria is applicable to facilities designed by Bechtel for the TMI-2 recovery effort.
The criteria presented herein are not applicable to the rebuilding of the unit for power genera-tion.
The General Project Design Criteria is to be applied to each facility by reference in each facility's specific design criteria document.
Any conflicts between the general and specific criteria must be identi-fied in the specific design criteria document.
1.1.4 Existing plant systems interfacing recovery systems need not be upgraded to current codes and standards applicable to the recovery systems and associated tie-ins.
1.1.5 Recovery project designs pertaining to systems, structures, and components classified as safety related or important to safety shall incorporate pertinent requiremer.ts from applicable NRC Regulatory Guides listed in the Project Nuclear Quality Assurance Manual.
Systems, struc-tures, and components to which the Project Nuclear Quality Assurance
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List (QCL).
The QCL is presented in GPUN Procedure 4000-ENG-7313.01 and 6
Program applies are identified in the TMI-2 Recovery Quality Classification the Project use of the QCL is described in Project Procedure EDPI 4.28-14.
1.2 PROJECT OBJECTIVES 1.2.1 There are four main objectives of the TMI-2 recovery. These objectives are:
- 1) Decontaminate the reactor building and equipment contained therein
- 2) Remove and store the reactor core
- 3) Decontaminate the Reactor Coolant System f
- 4) Process radioactive waste 1.2.2 In order to achieve these objectives additional facilities and systems will be required.
Some of these facilities will be permanent in nature; others will only be for the recovery of the unit and will be removed prior to the unit returning to service.
1.2.3 In addition to the facilities and systems to be provided, there will be plans developed for many of the activities required to achieve i
the project objectives.
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Page 1 i
Rev. 6 l
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1 Design Criteria 13587-2-L01-100 1.3 PROJECT CONCERNS 4
1.3.1 There are two major concerns that directly influence the design of the facilities and the operations required for the cleanup of TMI-2.
These concerns are:
- 1) Public health and safety
- 2) Occupational health and safety 2.0 DEFINITIONS l
2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)
The safe shutdown earthquake is that earthquake which is based upon an evaluation of the maximum earthquake potential considering the regional and local geology and seismology and specific characteristics of local subsurface material.
It is that earthquake which produces the maximum vibratory ground motion for which certain structures, systems, and j
components are designed to remain functional.
2.2 OPERATING BASIS EARTHQUAKE (OBE)
The operating basis earthquake is that earthquake which, considering the regional and local geology and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant; it is that earthquake i(
which produces the vibratory ground motion for which those features of
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the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain i
functional.
2.3 SEISMIC CATEGORY I/NON-SEISMIC CATEGORY I Seismic Category I structures, systems, and components for seismic design purposes are defined as those structures, systems, and components important to safety that are designed to remain functional in the event of a safe shutdown earthquake.
Items that are both Seismic Category I and important to safety are those structures, systems, and components:
a.
that are permanent plant components necessary to ensure the integrity of the reactor coolant pressure boundary, i
b.
that are necessary to ensure the capability to shut down the reactor or to maintain the reactor in a safe shutdown condition 2
(i.e., maintain subcriticality and decay heat removal), or to i
prevent a condition or event that could result in a return to nuclear criticality of fuel inside or outside the reactor vessel, or c.
whose failure could result in potential offsite exposures comparable to the guideline values of 10 CFR Part 100.
(Note:
for the purpose of TMI-2 recovery only, no events or accidents
- {
have been postulated which could result in such offsite l
Page 2 Rev. 2
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Design Critoria 13587-2-L01-100 exposures.
Therefore, it is not expected that the guideline
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values of 10 CFR Part 100 will be invoked for design or operational-related activities during TMI Unit 2 recovery.)
Non-Seismic Category I structures, systems, and components are those whose failure would not result in the release of radioactivity,in excess of 10 CFR 100 limits nor prevent reactor safe shutdown.
2.4 DESIGN BASES Design bases are postulated events / conditions or combinations of events /
conditions which establish the function and structural requirements of a structui-e, system, or component.
2.5 SAFETY RELATED As used in 10 CFR 100, Appendix A, this term refers to those structures, systems, or components designed to remain functional for the safe shutdown earthquake (SSE) necessary to ensure required safety functions, i.e.:
a.
The integrity of the reactor coolant pressure boundary b.
The capability to shut down the reactor and maintain it in a safe shutdown condition; or c.
The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures 5
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comparable to the guideline exposures of 10 CFR 100.
Safety Related is a subset of Important to Safety, 2.6 IMPORTANT TO SAFETY (ITS)
A special classification or category of those structures, systems, components, and activities that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.
It encompasses the broad class of plant features covered (not necessarily explicitly) in the General Design Criteria (10 CFR 50 Appendix A) that contributes in important ways to the safe operation and protection of the public in all phases and aspects of facility operation (i.e., normal operation and tFinsient control as well as accident mitigation).
It includes " Safety Related" as a subset.
3.0 LICENSING
3.1 INTRODUCTION
Recovery operations, activities, and work tasks will be performed within the existing TMI-2 Technical Specifications and in accordance with applicable NRC Regulatory Guides.
Specific design criteria shall identify applicable Technical Specifications and Regulatory Guide requirements.
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Page 3 Rev. 5
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Design Criteria 13587-2-L01-100 l
3.2 BASIC CRITERIA
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3.2.1 Facilities and systems constructed to support the recovery shall j
not be designed to requirements based on the hypothesis of accidents at i
power.
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3.2.2 Facilities and systems constructed to support the recovery and 6
i designated to remain as part of the permanent plant shall be designed to l
the applicable requirements specified in Chapter 3 of the TMI-2 FSAR in 1
addition to any special requirements necessary for the recovery effort.
l6 3.2.3 To the extenf. practicable, facilities and services constructed for the recovery effort will be separate from existing facilities and services.
Where it is not practicable to separate the facilities and services constructed for the recovery effort from existing facilities and ser-vices, design requirements will be imposed as necessary in order not to compromise the original design bases of the existing facilities and services.
These requirements shall be identified in the specific design criteria for the facility and service to be provided.
The following will serve as guidelines:
a.
Where piping and cables to be left in place when the unit is returned to service are routed through buildings containing seismic Category I piping and cables, the failure of the non-seismic Category I components shall not result in the failure of
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the seismic Category I components as a result of a seismic event.
b.
Where services to support recovery must tie into existing plant services, isolation provisions commensurate with tre design requirements of the existing plant service shall be provided.
c.
Where piping to be left in place when the unit is returned to service is routed through buildings contsfring safety-related equipment, the requirements for high energy line break and pipe whip specified in the TMI-2 FSAR shall be satisfied as applicable, d.
Where cables to be left in place when the unit is returned to service are routed through buildings containing safety-related equipment, the requirements for separation and fire protection specified in the TMI-2 FSAR and TMI-2 Fire Protection Reevalua-tion shall be satisfied as applicable.
3.2.4 Facilities and systems constructed to support the recovery effort shall not have as part of their design basis the severe natural phenomena for which the plant was originally designed.
However, facilities and systems constructed to support the recovery shall be evaluated to ensure 6
that there will be no loss of the required safety function of existing safety-related structures, equipment, or systems needed during the recovery should these events occur. Where there would be a loss of Page 4 Rev. 6
_ _= __._ - - -
Design Criteria 13587-2-L01-100 safety function, the facility or system shall have as part of its design
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basis the severe natural phenomena to the extent that the safety function can be maintained.
Included under " severe natural phenomena" are:
a.
b.
Tornado and tornado missile c.
Maximum flood 3.2.5 Facilities constructed to support the recovery shall not be designed for man-mad'e events not resulting from recovery activities.
Included under " man-made events not resulting from recovery activities" are:
a.
Transportation accidents occurring offsite b.
Airplane crashes c.
Release of toxic chemicals.
The facilities will be designed to ensure that there will be no loss of required function of existing adjacent safety-related structures, equip-ment, or systems should these events occur.
3.2.6 Environmental analyses will be performed in accordance with the methodology permitted by the Three Mile Island Nuclear Generating
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Station Offsite Dose Calculation Manual (ODCM).
The site meteorology used for these analyses will be based on that contained in the ODCM.
3.2.7 For purposes of design evolution, the river characteristics specified in Chapter 2 of the TMI-2 FSAR shall be used.
River water quality data is that specified in the Plant Design and Mechanical Design i
Criteria, 13587-2-M01-100.
3.3 DESIGN CONDITIONS This section defines the spectra of operating conditions to which the activities required for the recovery shall be designed. Also provided are the general design requirements for these operating conditions.
3.3.1 Condition I - Normal Operation i
Condition I occurrences are those that can reasonably be expected to occur during the recovery activities.
Examples of Condition I occur-rences are:
a.
Those that are normally expected to occur during the recovery including contaminatfor./ decontamination resulting from routine activities.
b.
Operations with equipment out of service or undergoing tests within operational limitations.
k Page 5 Rev. 6 4
....c.
Design Criteria 13587-2-LO1-100 Condition I occurrences shall be accommodated with only routine action
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required to prevent an unplanned release of radioactive materials in effluents to unrestricted areas.
3.3.2 Condition II - Incidents of Moderate Frequency Condition II occurrences are those any one of which may reasonably be expected to occur during a calendar year and which could result in a release of radioactive material requiring additional support personnel and/or equipment to control.
Examples of Condition II occurrences are:
a.
Loss of electrical power i
b.
Minor leakage from systems installed to support the recovery c.
Inadvertent actuation of a single active component in a system installed to support the recovery d.
Single error by an operator engaged in a recovery activity e.
Single active failure of a component (taken as the initiating event) in a system installed to support the recovery Condition II occurrences shall be accommodated with, at most, a cessa-tion of activities with the capability of resuming the activities after corrective action. Any release of radioactive materials in effluents to unrestricted areas shall be in conformance with Paragraph 20.1 of 10 CFR Part 20, " Standards for Protection Against Radiation."
3.3.3 Condition III - Infrequent Incidents Condition III occurrences are those which are not expected to occur but are assumed to occur during the lifetime of the recovery effort and could result in a significant release of radioactive material.
Examples of Condition III occurrences are:
a.
Rupture of any tank utilized for the recovery effort b.
Pipe break in a system installed to support the recovery c.
Fire in an area where recovery activities occur d.
An operating basis earthquake (OBE).
e.
Fuel handling accident in the reactor building (Note 2).
Note 2:
The source term for the postulated occurrence is based on ass 0 ming the assembly with the peak inventory of radioactive material in the TMI-2 core is intact.
The burnup is based on exact power history.
Credit is taken for a decay period of two years or more.
Page 6 Rev. 6 l6
Design Criteria 13587-2-L01-100 Condition III occurrences may result in damage to recovery facilities
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sufficient to preclude resumption of recovery activities for a consider-able time.
The release of radioactive material in effluents to unre-stricted areas may exceed the guidelines of 10 CFR Part 20, " Standards for Protection Against Radiation," but shall not be sufficient to inter-rupt or restrict public use of those areas beyond the exclusion radius.
3.4 REGULATORY REQUIREMENTS 3.4.1 Code of Federal Regulations The facilities and &ctivities associated with the recovery shall satisfy all applicable requirements of Title 10 of the Code of Federal Regulations 6
unless a specific exemption has been granted.
Listed below are specific sections which are likely to be more frequently applicable:
a.
10 CFR Part 20, Paragraph 20.103, Exposure of Individuals to Concentrations of Radioactive Materials in Air in Restricted 1
Areas b.
10 CFR Part 20, Paragraph 20.105, Permissible Levels of Radia-tion in Unrestricted Areas c.
10 CFR Part 20, Paragraph 20.106, Radioactivity in Effluents to Unrestricted Areas d.
10 CFR Part 50, Paragraph 50.34a, Design Objectives for Equip-ment to Control Releases of Radioactive Material in Effluents -
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Nuclear Power Reactors e.
10 CFR Part 50, Paragraph 50.36a, Technical Specifications'on Effluents from Nuclear Power Reactors f.
10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants g.
10 CFR Part 50, Appendix I, Numerical Guides for Design Objec-tives and Limiting Conditions for Operations to Meet the Criterion "As Low As Is Reasonably Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents, as specified by Appendix R of the Final Programmatic Environ-mental Impact Statement and incorporated into the TMI-2 operating license by Amendment No. 16 h.
10 CFR Part 100, Reactor Site Criteria 1.
29 CFR Part 1910, Occupational Safety and Health Standards (Department of Labor Regulations) j.
40 CFR Part 190, Uranium Fuel Cycle Standard (Environmental Protection Agency Regulations) k.
49 CFR Part 173 Shippers-General Requirements for Shipments and Packagings (Department of Transportation Regulations)
Page 7 Rev. 6
Design Criteria 13587-2-L01-100 1.
10 CFR Part 50, Appendix R, Fire Protection Program for Nuclear
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Power Facilities Operating Prior to January 1,1979.
An exemp-tion to Sections III.G and III.0 has been granted by the NRC (NRC letter Snyder to Kanga, May 18, 1984).
An exemption to 6
Section III.J has been requested (GPUNC letter 4400-82-L-0102, dated June 15, 1982, J. J. Barton to Dr. B. J. Snyder).
~
m.
40 CFR Parts 260 through 265, Hazardous Waste Regulations (Environmental Protection Agency Regulations) 3.4.2 Regulatory Guides Table 1 lists many of the regulatory guides which may be applicable to individual facility or system design. This table and other regulatory guides shall be reviewed and any regulatory guides to be implemented shall be included as part of the specific design criteria for the associ-ated facility or system.
3.4.3 Standard Review Plans (SRPs)
The following SRPs and Branch Technical Positions shall be reviewed and the guidance provided used as applicable in designing the facilities and activities to support the recovery.
a.
SRP 11.2, Liquid Waste Management Systems, Rev. I b.
SRP 11.3, Gaseous Waste Management Systems, Rev. 1
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c.
SRP 11.4, Solid Waste Management Systems, Rev. 1 d.
SRP 15.7.3, Postulated Radioactive Releases Due to Liquid Containing Tank Failures, Rev. 1 e.
Appendix A to Branch Technical Position APCSB 9.5-1, Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976 (August 23, 1976) f.
Branch Technical Position ETSB 11-3, Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Plants, Rev. 1 3.4.4 State Regulations The facilities and activities associated with the recovery shall satisfy the following:
Title 25, Environmental Resources; Chapter 75, Solid Waste Management (Pennsylvania Department of Environmental Resources Regulat,fons) 3.5 INDUSTRY CODES AND STANDARDS Applicable industry codes and standards are identified in the individual discipline design criteria along with the effective date statement for
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the listed codes and standards.
6 Page 8 Rev. 6
Design Criteria 13587-2-L01-100 3.6 SAFETY ASSESSMENT
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A safety assessment will be performed for each facility and activity to be provided.
This assessment shall include a review of the final design to ensure that the safety criteria have been satisfied. When the assess-ment reveals that the final design does not satisfy the safety criteria, design changes shall be made or administrative controls imposed.
4.0 ALARA DESI'GN CRITERIA AND CONSIDERATIONS The items listed in Table 2 form the basis for the THI-2 Recovery Project ALARA program.
During the design process, the applicable items shall be considered and incorporated into the design as appropriate.
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Page 9 Rev. 6 l6
Design Criteria 13587-2-L01-100 TABLE 1 REGULATORY GUIDES 1.
Reg. Guide 1.21 Measuring, Evaluating, and Reporting Radio-activity in Solid Wastes and Releases of Radioactive Materials in Liquids and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants (Rev. 1, June 1974)
Discussion This guide is applicable to the design of radiation monitoring systems in liquid and gaseous effluent paths and in the design of means for determining the total curie quantity and radionuclide composition of solid wastes shipped offsite with the following clarification.
(1) (Ref: Appendix A, Paragraph C) To preclude unnecessary radia-tion exposure to personnel, the curie and radionuclide determi-nations for solid radioactive waste shipped offsite will be performed to the extent and level required by Department of Transportation Regulations and 10 CFR Part 71, " Packaging of Radioactive Material." Additional sampling and analysis is not required.
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2.
Reg. Guide 1.25 Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Rev. O, March 1972)
Discussion The assumptions of'the guide may be used with the following excep-tions or clarifications, in the analysis of the potential radio-logical consequences of a fuel handling accident.
(1) [Ref:
Paragraph C.3.b(2)] Whole-body gamma doses and beta-skin doses are presented separately, as the dose from beta radiation of the whole body is negligible.
The total dose to the skin is the sum of the beta-skin dose and the whole-body gamma dose.
(2) [Ref:
Paragraph C.3.b(3)] Dose conversion factors are taken from Reg. Guide 1.109.
(3) (Ref:
Paragraph C.1) The source term for the postulated fuel handling accident is based on assuming the assembly with the peak inventory of radiaoctive material in the TMI-2 core is intact.
The burnup is based on exact power history.
Credit is taken.for a decay period of two years or more.
Page 10 2
Rev. 2 1
f e
Design Criteria 13587-2-L01-100 TABLE 1 (Continued) 3.
Deleted 2
l 4.
Deleted 5.
Reg. Guid 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants (Rev. 1, December 1973)
Discussion This guide is applicable to facilities housing radioactive waste management systems and subject to and as invoked by Reg. Guide 1.143.
4 6.
Reg. Guide 1.61 Damping Values for Seismic Design of Nuclear l
Power Plants (Rev. O, October 1973)
Discussion This guide is applicable to facilities housing radioactive waste management systems and subject to and as invoked by Reg. Guide 1.143.
7.
Deleted 12 8.
Reg. Guide 1.92 Combining Modal Responses and Spatial Components in Seismic Response Analysis (Rev. 1, February
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1976)
I Discussion This guide is applicable to facilities housing radioactive waste management systems and subject to and as invoked by Reg. Guide 1.143.
t 9.
Reg. Guide 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10'CFR Part 50, Appendix I (Rev. 1, October 1977)
Discussion i
The assumptions of Regulatory Guide 1.109 are followed in the (2
l analysis of annual doses to man from routine releases.
1 10.
Deleted l2 l
11.
Reg. Guide 1.112 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-i Cooled Power Reactors (Rev. O, April 1976)
Discussion i
The applicable methods described in this guide may be used in
,(
calculating estimated releases from liquid waste processing systems.
Page 11 l
Rev. 2
Design Criteria 13587-2-L01-100 TABLE 1 (Continued) 12.
Reg. Guide 1.113 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I (Rev. 1, April 1977) t Discussion The applicable, methods described in this guide may be used in estimating aquatic dispersion of effluents.
13.
Reg. Guide 1.132 Site Investigations for Foundations of Nuclear l
Power Plants (Rev. 1, March 1979)
Discussion Recognizing the site-sensitive aspects, the guidance provided by this guide may be used in the development of site investigation studies for foundations of facilities to be provided.
14.
Reg. Guide 1.138 Laboratory Investigations of Soils for Engi-neering Analysis and Design of Nuclear Power Plants (Rev. O, April 1976)
Discussion
(
Recognizing the site sensitive aspects, the guidance provided by this guide may be used in the laboratory investigations of soils required by Reg. Guide 1.132.
i 15.
Reg. Guide 1.140 - Design, Testing, and Maintenance Criteria for l
Normal Ventilation Exhaust System Air Filtra-l tion and Adsorption Units lof Light-Water-Cooled I
Nuclear Power Plants (Rev. 1, October 1979)
Discussion The detailed project position is under development.
However, this guide is applicable to atmosphere cleanup systems and, in general, the guidance provided may be followed.
16.
Reg. Guide 1.143 Design Guidance for Radioactive Waste Manage-ment Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (Rev. 1, October 1979)
Page 12 l2 Rev. 2
DQsign Crit @ria 13587-2-L01-100 TABLE 1 (Continued)
Discussion This guide is applicable to systems and facilities that are as-sociated with the control and management of liquid, gaseous, and solid radioactive waste.
(Note:
radioactive waste means those liquids, gases, or solids containing radioactive materials that by design or operating practice will be processed prior to final disposition.).
l2 17.
- Information Relevant to Ensuring That Occupa-tional Radiation Exposure at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable (Rev. 3, June 1978)
Discussion The design considerations, personnel qualifications, and plans and procedures for ensuring that occupational radiation exposures will be as low as is reasonably achievable are in accordance with Regula-tory Guide 8.8 subject to the following clarifications or excep-tions:
(1) (Ref:
Paragraph C.2) The design features discussed in this paragraph are described in general terms which may permit
(
several acceptable alternative designs for a particular appli-cation, e.g., different types or amounts of shielding.
(2) (Ref:
Paragraph C.2.g) Airborne monitoring equipment will be provided in areas to which personnel normally have access and in which there is a potential for airborne radioactivity.
In addition, area radiation monitors will be provided in areas to which personnel normally have access and where there is a potential for personnel unknowingly receiving high levels of radiation exposure (e.g., in excess of 10 CFR 20 limits) in a short period of time because of system failure or improper personnel action.
Note:
For guidance on the following Regulatory Guides, consult the Bechtel Nuclear Quality Assurance Manual (NQAM).
1.26 QA Classifications and Standards for Water Stream and Radio-l active Waste Containing Components of Nuclear Power Plants, Rev. 3, February 1976 2
1.29 Sejsmic Design Classification, Rev. 3, September 1978.
1.30 QA Requirements for the Installation, Inspection and Testing of Instrumentation and Electrical Equipment, August 11, 1972.
l 1.31 Control of Ferrite Content in Stainless Steel Weld Metal,
(
Rev. 3, April 1978.
Page 13 Rev. 2
0 sign Critoria 13587-2-L01-100 TABLE 1 (Continued) 1.37 QA Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants, March 16, 1973.
1.38 QA Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water Cooled Nuclear Power Plants, Rev. 2, May 1977.
1.39 Housekeep,ing Requirements for Water Cooled Nuclear Power Plants, Rev. 2, September 1977.
1.54 QA Requirements for Protective Coatings Applied to Water Cooled Nuclear Power Plants, June 1973.
4 1.94 QA Requirements for Installation, Inspection and Testing of Structural Steel and Concrete during the Construction Phase of Nuclear Power Plants, Rev. 1, April 1976.
1.116 QA Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems, Rev. 0-R, May 1977.
Page 14 Rev. 4
Design Criteria 13587-2-L01-100 1
TABLE 2 h
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ALARA ITEMS Item No.
Description Responsibilities Note Sec. A FACILITY ARRANGEMENT 1.0 Facility Layout 1.1 Check that equipment with contact N
radiation levels of Zone III (see Table 4) or greater is separated from Zone II and lower areas by shielding or distance plus access barriers.
- 1. 2 Check-that major equipment which by N
design accumulates or concentrates radioactivity with Zone III or greater contact radiation levels is shielded or separated from adjacent active and passive equipment to meet the appli-cable radiation shielding criteria for adjacent areas.
(.
1.3 Check that equipment compartments are N
arranged such that radiation zone differences between adjacent areas are minimized.
1.4 Check that personnel access control A, N, PD and traffic patterns are considered to minimize spread of contamination during all facility operating modes.
1.5 Check that active components in clean N
(nonradioactive) services are not located in Radiation Zone III or greater.
1.6 Check that equipment subject to removal PD or replacement has adequate aisles or area access and built-in provisions (such as monorails, jib cranes, etc.)
for removal.
1.7 Check that access to components PD requiring frequent maintenance, in-service inspection, adjustment, etc. is from the lowest practicable radiation zone and not via a Zone V.
Page 15 Rev. 1
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Design Criteria 13587-2-L01-100 1
h TABLE 2 (Continued)
Item No.
Description Responsibilities Note 1.8 Check that adequate space and A
facilities are provided for clothing change stations out-side contaminated areas.
1.9 Check that all corridors and N, A normal traffic areas are Zone I or II.
2.0 Equipment Location 2.1 Check that adequate space is provided PD, CS around equipment to allow ease of maintenance.
2.2 Check that equipment maintenance PD envelopes include estimated size of rigging requirements and temporary shielding, if required.
2.3 Check that laydown area requirements PD for equipment are available.
2.4 Check that equipment which requires PD, CS routine maintenance, service, testing, or inspection, such as instruments, sample stations, or rotating components, are located to provide maximum direct access.
2.5 Check that the clear space for door-A, PD ways is a minimum of 3 feet by 7 feet and that there is adequate access for personnel, tools, and component removal.
2.6 Check that equipment manways are PD readily accessible.
2.7 Check that high radiation equipment PD is located such that interconnecting high radiation piping is minimized.
3.0 Spiecific Component Layout 3.1 Filters Check that adequate space is PD
{
provided for semi-remote Page 16 Rev. 1
DQsign Criteria 13587-2-L01-100 1
TABLE 2 (Continued)
Item No.
Description Responsibilities Note removal, cask loading, and trans-porting spent radioactive filter cartridges to the solid radwaste area.
3.2 Pumps 3.2.1 Check that small pumps are oriented PD in a manner that allows easy removal from the area.
3.2.2 Check that adequate access is provided PD for pump seal replacement.
3.3 Tanks 3.3.1 Check that direct access and removal PD space is provided for motors of tank agitators.
3.3.2 Check that direct access to active PD components or manways is provided into the upper levels of tank rooms
(
as well as the lower elevations.
3.3.3 Check that adequate space is provided PD for tank internals cleaning operations.
3.4 Evaporators 3.4.1 Check that concentrates and PD distillate components are adequately separated.
3.4.2 Check that components which accumulate PD, N radioactivity or crud, such as heating tubes, are separated from active com-ponents such as valves.
3.4.3 Check that adequate space is provided PD to allow uncomplicated removal of i
heating tube bundles.
3.5 Sample Stations 3.5.1 Check that sample stations for PD, N, CS l
routine sampling of process fluids are separated by shielding or distance
(
from other radioactive components to Zone II.
Page 17 Rev. 1
Dosign Critoria 13587-2-L01-100 h
TABLE 2 (Continued)
(
Item No.
Description Responsibilities Note 3.5.2 Check that local ventilation (e.g.,
PD, N, CS a hood) is provided at sample stations containing radioactive materials.
3.6 Ventilation System Components 3.6.1 Check that ventilation fans and PD filters are provided with adequate access space to permit servicing.
3.6.2 Check that outside air supply and PD building exhaust system components are in areas no greater than Zone II.
3.6.3 Check that general ventilation flow is PD from areas of potential (or actual) low contamination to areas of potential (or actual) high contamination.
3.7 Instruments,
3.7.1 Check that instruments which require CS
(
periodic attention are located in Zone II (or lower) areas whenever possible.
3.7.2 If instruments must be located in PD, CS Zone III or greater, check that they are mounted so that they are readily accessible for maintenance and calibration and are easily removable to a lower radiation zone for extended servicing or calibration.
3.7.3 If control valves must be located in PD, CS Zone IV or greater, check that appur-tenances such as E/P converters, airsets, and solenoid valves are not mounted on the control valve but are located in a lower radiation zone.
3.8 Sumps Check that sumps capable of PD l
accumulating radioactive wastes are located in zones compatible with radiation levels due to the contained i
activity.
Page 18 Rev. 1 i
l
DIsign Critaria 13587-2-L01-100 1
TABLE 2 (Continued)
Item No.
Description Responsibilities Note Sec. B SHIELDING
- 1. 0 Bulk Shielding 1.1 Check that shielding or separation N
is provided between radiation zone areas to meet the radiation level criteria for adjacent areas.
1.2 Check that shielding design is based N
on conservative or measured radiation source term, component design, and plant layout assumptions.
1.3 Check that poured concrete density N, C specifications are consistent with shielding design basis minimum densities.
1.4 Check that concrete block density N, A specifications are consistent with shielding design basis minimum densities.
1.5 Check that concrete block wall designs N, A meet or exceed the minimum shielding requirements.
1.6 Check that removable or temporary N
shielding is designed consistent with applicable radiation shielding criteria for adjacent areas.
2.0 Penetration and Discontinuity Shielding 2.1 Check that penetrations, such as H&V N, PD, E, CS ducts and piping, are either located with an offset between radiation sources and accessible areas or are appropriately shielded.
2.2 Check that penetrations are located as N, PD, E, CS far as possible above the accessible floor elevation.
2.3 Check that penetration shielding is N
provided as necessary to meet the radiation shielding criteria in adjacent accessible areas.
Page 19 Rev. 1
Design Criteria 13587-2-L01-100 1
TABLE 2 (Continued)
(
Item No.
Description Responsibilities Note 2.4 Check that seismic gap shielding is N, C provided to maintain radiation levels in adjacent accessible areas within radiation shielding criteria limits.
3.0 Entryway Shielding 3.1 Check that there is no direct or N
near direct shine out of shielded cells.
3.2 Check that adequately shielded N
labyrinths or hatches are provided to limit direct and scattered radiation out of shielded areas.
Sec. C SYSTEM DESIGN 1.0 Decontamination Provisions 1.1 Check that radioactive systems with M, PD Zone V component radiation levels have provisions to flush the entire system.
Flushing capability should be
(
available even if the system pump is inoperable.
1.2 Check that major components of the M, PD primary coolant purification system where crud can collect up to Zone V radiation levels, such as filters, heat exchangers, etc. have provisions for chemical decontamination ~, including low point drains.
Check that means are available to take the decon solution to chemical waste area.
1.3 Check that seal flush water is provided M, PD to pumps with chemical or slurry wastes.
1.4 Check that all serviceable components M, PD, CS have isolating and draining capability.
1.5 Chbck that provisions are available to M, PD, CS flush potentially contaminated instrument lines.
k Page 20 Rev. 1 l
Design Critoria 13587-2-L01-100 1
TAB'E 2 (Continued)
Item No.
Description Responsibilities Note 1.6 Check that flush connections are M, PD located downstream of the component isolation valve on the inlet line and upstream of the isolation valve on the outlet line, and as close as possible to the inlet and outlet connections of the component.
1.7 Check that isolation valves are M, PD provided on the flush connections and are located as close as possible to the main pipe.
1.8 Check that all flush connections are M, PD equipped with quick connect / disconnect fittings.
2.0 Remote Operation and Instrumentation 2.1 Check that adequate process instrumen-CS tation and controls are available to allow system and component operation
(
from a low radiation zone.
2.2 Check that filters which accumulate PD high radioactivity are designed with the means either to backflush the filter remotely or to perform cartridge replacement with semi-remote tools.
2.3 Check that probe type instruments are CS used on highly radioactive tanks con-taining two phase materials.
3.0 Leakage Provisions 3.1 Check that tank overflow lines are PD directed to the waste collection system.
3.2 Check that sludge tanks and air mixing PD tanks which contain radioactive materials are vented to the respective building ventilation system or the.?nt collection system.
3.3 Check that strainers are included in PD vent lines from tanks containing spent
(
resins or sludge.
Page 21 Rev. 1
02 sign Criteria 13587-2-L01-100 1
TABLE 2 (Continued)
No.
Description Responsibilities Note 4.0 Demineralizers 4.1 Check'that demineralizers in radio-PD active systems and associated piping are designed with provisions for being flushed with demineralized water.
4.2 Check that strainers are located immed-PD iately downstream of ion exchangers.
4.3 Check that drains and downstream M, PD strainers are designed for full sys-tem pressure drop.
4.4 Check that strainers are included PD in vent lines from the demineralizer vessel.
4.5 Check that flush connections are PD provided at all critical locations (such as elbows, ties, valves) to
{
clear potential plugs.
4.6 Check that flow in piping is turbulent M
enough to maintain suspension of fines.
5.0 Floor Drains 5.1 Check that equipment drains are PD piped directly to a drainage collection system.
5.2 Check that provisions are made to PD remove plugging should it occur in drain lines.
5.3 Check that radioactive and potentially PD radioactive drains are separated from nonradioactive drains.
Sec. D PIPING AND VALVE DESIGN 1.0 Pipe Routina 1.1 Check that piping containing radio-PD active materials is routed through suitably zoned, controlled access
(
areas in accordance with piping Page 22 Rev. 1
Design Criteria 13587-2-L01-100 7
TABLE 2 (Continued)
Item No.
Responsibilities Note radiation classification as shown in Table 3.
1.2 Check that equipment compartments PD contain radioactive piping associated only with equipment within the compart-ment or that nonassociated piping is adequately separated.
1.3 Check that where it is necessary PD, N for radioactive piping to be routed through corridors or other radiation zone areas, shielded pipeways are provided to meet area radiation level requirements.
1.4 Check that long runs of exposed PD radioactive piping are minimized, particularly in active component areas such as valve galleries or pump cells.
- 1. 5 Check that radioactive piping is N, PD
(
routed to take credit for shielding effects of equipment or structures.
2.0 Valve Location 2.1 Check that valves are separated from N, PD components which accumulate or contain radioactivity by shielding or distance to meet the applicable radiation shielding criteria levels.
2.2 Check that valves are readily accessi-PD, CS ble from floors or permanent platforms.
2.3 Check that sufficient space is pro-PD, CS vided to facilitate valve and valve operator maintenance, operations, and testing.
2.4 Check that valves are not located in PD, CS radioactive pipeways.
2.5 Check that vent and drain isolation PD, CS and instrument root isolation valves are located as close as practical to process piping or components.
Page 23 Rev. 1
Design Criteria 13587-2-L01-100 TABLE 2 (Continued)
Item No.
Responsibilities Note
- 2. 6 Check that process valves are not PD locat.ed at low points in piping.
2.7 Check that reach rods or remote PD, N manipulators are provided for manually operated valves that are required in potentially high radi-ation areas (Zone V or greater).
3.0 Pipe Desian 3.1 Check that branch lines having little PD or no flow during normal operation are connected above the horizontal midplane of the main pipe.
3.2 Check that thermal expansion loops in PD radioactive systems are raised rather than dropped.
3.3 Check that orifices are located on PD, CS vertical piping runs if possible.
If
(
located in horizontal piping runs, use eccentric design of the orifice.
3.4 Check that reducers are installed not PD to form a stagnant pocket, i.e., use eccentric design with bottom flat, except at pumps.
3.5 Check that orifices located in hori-PD, CS zontal runs use an eccentric design only if suspended solids are present 2
in the process fluid.
1.6 Check that lengths of radioactive pipe PD runs and number of bends are minimized.
3.7 Check that low points and dead legs in PD radioactive piping are minimized and are capable of being flushed.
3.8 Check that instrument and sensing PD, CS j
line connections are located in such a way as to avoid corrosion product and radioactive gas buildup.
i Page 24 Rev. 2
Design Criteria 13587-2-L01-100 1
TABLE 2 (Continued) h
(
Item No.
Responsibilities Note 3.9 Check that welded joints are used when-PD, CS ever possible to minimize crud traps in the mechanical joints.
4.0 Valve and Valve Operator Selection 4.1 Check that full ported valves are used M, PD, CS in systems expected to handle spent resins or slurries with radiation levels of 25 mr/hr or greater at con-tact with the surface of the pipe.
(See Table 3) 4.2 Check that valves 2-inches and M, PD, CS larger (except butterfly valves and plug valves) in lines carrying radioactive fluids with radiation levels of 25 m.-/hr or greater (con-tact dose rate) are diaphragm, pack-less, or have a cauble set of packing with lantern ring.
4.3
(
Check that all globe valves in drain M, PD lines (excluding instrument valves) 2 inches and smaller are Y pattern globe valves to facilitate rodding if plugging should occur.
4.4 Check that remote operators or M, PD, CS handwheels on reach rods are provided for all valves, which must be accessible during operation, in lines processing evaporator bottoms or spent resins.
4.5 Check that pressure relief valves M, PD have flange connections to facilitate removal for set pressure verification and calibration.
4.6 Check that valve operators are M, PD properly selected and meet the criteria in Table 3.
4.7 Check that valve types are properly M, PD selected for their intended ser-vice and environment.
(
Page 25 Rev. 1
Design Criteria 13587-2-L01-100 I
TABLE 2 (Continued)
Item No.
Responsibilities Note 4.8 Check that plug valves or equal are M, PD used on systems transporting resins and sludge, and on radwaste systems.
5.0 Spent Resin and Sludge Piping 5.1 Check that resin lines are continuously PD sloped in the direction of flow to avoid potential stagnant pockets.
5.2 Check that valves are located as close PD as possible to the spent resin tank room to minimize the length of the dead leg.
5.3 Check that flow control valves and M, CS orifices are not used in resin lines.
5.4 Check that long radius (1.5 times the PD pipe diameter or greater) bends and elbows are used at direction changes.
5.5 Check that directional changes in PD resin piping runs are minimized.
5.6 Check that fluid velocity is high PD enough to keep resins in suspension.
5.7 Check that system design permits flow PD to be continuous until resins are flushed from piping, or provision is made for flushing at a velocity high r
enough to pick up resins that have settled out during flow interruption.
Sec. E COMPONENT DESIGN (For components contain-ing radioactive fluids or located in high radiation areas) 1.0 Specifications 1.1 Check that material requisitions specify M, CS the radiation environmental requirements for the intended material application.
1.2 Check that equipment design features M, CS as presented in the remainder of this section are included in the appropriate equipment specification.
Page 26 Rev. 1
Design Critoria 13587-2-L01-100 1
TABLE 2 (Continued)
No.
Responsibilities Note 2.0 Heat Exchangers 2.1 Check ~that corrosion resistant tubes M
of stainless steel or other suitable material with welded tube-to-tube sheet joints art provided to minimize leakage.
2.2 Check that impact baffles are provided M
with tube side and shell side velocities limited to minimize erosiva effects.
2.3 Check that drains are provided on the M, PD lowest portion to ensure removal of contaminated fluids.
2.4 Check that where practical the contam-M inated side of the heat exchanger operates at a lower pressure than the clean side.
2.5 Check that the more radioactive stream M
is on the tube side.
3.0 Evaporators Check that chemical addition connec-M tions are provided to allow use of chemicals for descaling operations.
4.0 Pumps (Small) 4.1 Check that pump casings are provided M
with drain connections.
4.2 Check that pumps in radiation areas M
(Zone III or higher) are purchased with mechanical seals to reduce seal servicing time and leakage.
4.3 Check that pumps in radioactive M
systems are provided with flanged connections for ease in removal.
4.4 Check that electrical quick disconnects M, E are provided on pumps in high radiation zones (V or higher).
4.5 Check that painted surfaces of the M, A pump (if any) are painted with a
(
radiation-resistant and decontaminable coating.
Page 27 Rev. 1
l D2 sign Criteria 13587-2-L01-100 TABLE 2 (Continued)
No.
Responsibilities Note 4.6 Check that the pump has long-lived M
bearings and that lubrication is the permanent type.
4.7 Check that the pump selection has M
considered the use of low RPM designs.
5.0 Tanks 5.1 Check that tanks in radioactive M, C service are provided with sloped bottoms (min. 1 inch per foot of tank diameter) and bottom outlet connections.
Conical or dished bottom tanks with bottom connections are acceptable.
5.2 Check that adequate tank mixing is M
provided to prevent crud settling.
l 5.3 Check that each tank requiring a manway M, C is top fitted with one of at least
(
a 2-foot diameter.
(If a manway is l
located on the side of a tank, it should be clearly demonstrated that it is l
necessary.)
5.4 Check that side manways have M, C l
eccentrically hinged covers designed I
to easily clear fastening studs.
5.5 Check that outlet pipes have backflush-M PD ing capability into the tank to break up sediment.
Backflush capability should include air.
5.6 Check that tank linings (if any) are M,C,A suitable for the expected service.
12 l
5.7 Check that overflow lines are lower M, PD, C l
than vent lines to prevent fluid from contaminating vent lines, 5.8 Check that a permanent connection is M, PD, C provided for insertion of a hydrolaser unit for decontamination of tanks in Zone V areas.
Page 28 Rev. 2
Design Critoria 13587-2-L01-100 1
TABLE 2 (Continued)
No.
Responsibilities Note 5.9 Check that lap joints were not used in M, C tank construction.
~
5.10 Check that no backing strips were used M, C on tank welds.
5.11 Check that backing rings were not M, C used on nozzle welds.
5.12 Check that siphoning of liquid waste PD from tanks cannot occur.
5.13 Check that in-line filters with PD backflushing capability are provided for tanks with a sludge buildep potential.
5.14 Check to ensure that tanks with a M, PD potentially hazardous leakage conse-quence are located over catch pans or within curbs with drain lines leading to radioactive ifquid waste
(
storage tanks or to sumps capable of handling a potential spill.
6.0 Instruments 6.1 Check that chemical seals are CS provided on sensing lines on process piping that may contain high amounts of solids.
6.2 Check that primary instruments which, CS for functional reasons, are located in high radiation zones (V and greater) are designed for easy removal to a radiation Zone II or lower for calibra-tion.
6.3 Check that instruments are selected CS which contain minimal quantities of contaminated working fluids; e.g.,
pressure transducers rather than bellows-type pressure gauges.
Page 29 Rev. 1
02 sign Criteria 13587-2-L01-100 TABLE 2 (Continued)
[
Item No.
Responsibilities Note 7.0 Tools 7.1 Check that tool design has minimized M
cracks and crevices.
7.2 Check that corrosion-resistant M
materials have been used for tool construction (where applicable) and that the materials and surface finishes are conducive to decon-tamination.
7.3 Check that tool design allows for M
flushing of potentially contaminated surfaces (inside and out).
2 7.4 Check the design to ensure that tools M
can be easily assembled / disassembled with simple hand tools and that the design incorporates features to either minimized installation time or provide for remote installation.
7.5 Check that all flush connections M
(if applicable) have quick connect /
disconnect fittings.
7.6 Check that tool hangers and storage M
areas are accessible and serviceable.
Sec. F MISCELLANEOUS. FACILITY DESIGN
- 1. 0 Lighting 1.1 Check that multiple electric lights,
E are provided for each cell or room containing highly radioactive compo-nents (Zone V and greater) so that burnout of a single lamp will not re-quire entry.
1.2 Check that lighting in high radiation E
arpas (Zone V and greater) is actuated from outside the area in the lowest practical radiation zone.
Page 30 Rev. 2
r Design Criteria 13587-2-L01-100 TABLE 2 (Continued)
No.
Responsibilities Note 1.3 Check that sufficient lighting is E
provided in areas that contain remote viewing devices to allow their efficient use.
1.4 Check that plug-in, accessible, E
bracket hung, removable units are provided for easy removal and relamping outside high radiation areas.
(Lightweight units are preferable for ease of handling.)
1.5 Check that extension cord powered units E
stored on brackets and cord hangers outside the entrance are provided if permanent units are not practical, and the pre placed brackets are provided within the high radiation area to facilitate installation.
1.6 Check that long-life bulbs are provided E
in high radiation areas (Zone V).
- 2. 0 Contamination Control and Coatinos 2.1 Check the floor drains and properly M. PD, C sloped floors are provided for each room or cubicle containing serviceable components with radiation levels of a Zone III or higher.
2.2 Check that local gas traps or porous M, PD seals are not used on floor drains from radiation areas.
2.3 Check that gas traps are provided at M, PD the common sump or collection tank.
2.4 Check that concrete surfaces in N. A areas of potential contamination are covered with a smooth-surfaced coating for the floor and wainscot, which will allow easy decontamination.
2.5 Check that threshold curbs, cofferdams, PD, A, C or other means are provided to control radioactive leakage or spills, k
Page 31 2
Rev. 2
D: sign Critsria 13587-2-L01-100 TABLE 2 (Continued)
(
Item No.
Responsibilities Note 2.6 Check that protection from backflooding PD, C of fl,oor drains is provided.
3.0 Access Platforms 3.1 Check that equipment subject to routine PD, CS maintenance (defined as at least once per year) has permanent access platforms.
3.2 Check that direct access to active PD, CS components is provided from any working platform.
3.3 Check that ample space is provided on PD platforms for accommodating safe personnel movement during replacement of components (including the use of any necessary material handling equip-ment).
4.0 Remote Viewing Devices
(
Check that in high radiation areas M PD, CS (Zone V and greater) where routine visual surveillance inspections are required, remote viewing devices are provided.
5.0 Temporary Shielding Check that when shielding is required N, PD, C and permanent shielding is not feasible, sufficient space and supports for portable shielding are provided and the structure is capable of accepting the additional loading.
6.0 Insulation Check that piping and components PD requiring frequent (once per year or greater) access for maintenance, inspection, etc. utilize quick removal insulation wherever practical, k
Page 32 l2 Rev. 2
Design Criteria 13587-2-L01-100 TABLE 2 (Continued)
No.
Responsibilities Note 7.0 Plant Services Check that services such as electrical M, PD, E, N power, water, respirable air, and compressed air are available reasonably close to radiation work areas.
Legend Symbol Description PD Plant Design CS Control Systems A
Architectural E
Electrical C
Civil
{
M Mechanical N
Nuclear / Licensing Item to be completed prior to transmittal of general arrangement drawing to client for initial review.
Page 33 2
Rev. 2
Design Criteria 13587-2-L01-100 TABLE 3 i
TYPICAL RADI0 ACTIVE PIPING CLASSIFICATION AND ROUTING Exposure Rate at Acceptable Contact with Pipe Radioactivity Radiation Zone Surface (mR/hr)
Description Routina*
Nonradioactive I, II, III, IV, V 0.5 Slightly I, II, III, IV, V radioactive 2.5 Low radioactivity II, III, IV, V 25 Low to moderately III, IV, V radioactive 100 Moderately IV, V radioactive
>100 Highly radioactive V, VI, VII
- Routing of nonradioactive or low radioactivity piping in high radiation zones should be minimized.
(
(
Page 34 2
Rev. 2
r 0
Design Criteria 13587-2-L01-100 TABLE 4
(
RADIATION ZONES Design Dose Rate Zone (arem per hour)
Access Description I
50.5*
Uncontrolled, unlimited access II 0.5 to 2.5 Controlled, limited access 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week III 2.5 to 25 Controlled, limited access 4 to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week IV 25 to 100 Controlled, limited access 1 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week V
100 to 1000 Normally inaccessible except during emer-l6 gency VI 1000 to 3000 Normally inaccessible except during emer-l6 gency Locked barrier to zone VII it3000 Normally inaccessible except during emer-l6 gency Locked barrier to zone
- Design dose rates in office spaces and other Zone I areas which are continuously occupied 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per day, 5 days per week or more shall be less than 0.25 mrem /hr.
Corridors and other Zone I areas of a transient occupancy nature shall be below 0.5 mrem /hr.
Page 35 Rev. 6
-