ML20039C734
| ML20039C734 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/21/1981 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML20039C723 | List: |
| References | |
| 13587-2-M01-100, 13587-2-M1-100, NUDOCS 8112300093 | |
| Download: ML20039C734 (27) | |
Text
{{#Wiki_filter:_ Design Criteria 13587-2-M01-100 gl' / s GPU SERVICE CORPORATION THREE MILE ISLAND - UNIT 2 REC 0VERY FACILITIES DESIGN CRITERIA DOCUMENTS COVER SHEET -13s87 DISCIPLINE: Plant Design and Mechanical { JOB NO: O V P* 1 Up PU App ova (,0 5'% Issued for Use Upon GPUSC Approval f[. = w e, esc 3 ORIGINATO, REVISION DESCRIPfl0N h N O. DATE a 8112300093 811222 DRADOCK05000g
LATEST LATEST LATEST LATEST LATEST LATEST LATEST SHEET REV. SHEET C EV. SHEET REV. SHEET REV. SHEET REV. SHEET REV. SHEET REV. i 1 ii 0 1 0 2 0 3 1 4 0 5 0 6 0 7 1 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 1 (,. 17 0 18 1 19 1 20 0 A-1 0 B-1 0 B-2 0 Joe No. 13587 ggy ? j DESIGN CRITERI A DOCUMENTS DISCIPl INE Plant Design / Mech. f REVISION STATUS SHEET y PAGE 1 of 1 b
Design Criteria 13587-2-M01-100 ( PLANT DESIGN AND MECHANICAL DESIGN CRITERIA TABLE OF CONTENTS P,,ag
1.0 INTRODUCTION
1
1.1 Purpose and Scope
1 2.0 CODES, STANDARDS, AND GUIDES 2 2.1 Qualifying Statement 2 2.2 State and Local Codes and Standards 2 2.3 All Other Codes, Standards, and Guides 2 2.4 Inspections 7 l1 3.0 MAJOR PLANT PARAMETERS 8 ~ 3.1 Nuclear Steam Supply System 8 3.2 Plant External Facilities 8 ({} 4.0 GENERAL PLANT CRITERIA FOR DESIGN 9 4.1 Air Quality (Plant Discharge Air) 9 4.2 River Water Qualities 9 4.3 Reactor Coolant Analysis 9 4.4 Quality and Concentrations of Principal Nuclices 9 Contained in Reactor Building Sump Water 4.5 Minimum Water Chemistry Specifications During 9 the Pre-Defueling Period 4.6 Ambient Design Conditions 9 4.7 Waste Water Quantity 10 4.8 Liquid Radwaste Systems Release 10 4.9 Noise Control 10 4.10 Valve Criteria 10 4.11 Piping Criteria 12 4.12 Pipe Support Design Criteria 13 4.13 Fire Protection Criteria 15 k. 1 Rev. 1
Design Criteria 13587-2-M01-100 O ({ TABLES TABLE 4-1 River Water Qualities TABLE 4-2 Quality and Concentrations of Principal Nuclides Contained in Reactor Building Sump Water TABLE 4-3 Minimum Water Chemistry Specifications During the Pre-Defueling Period TABLE 4-4 Inside Ambient Design Conditions for Existing Areas APPENDICES Appendix A - Design References Appendix B - Velocity vs. Pipe Diameter 4 C ii Rev. 0 ~
Design' Criteria 13587-2-M01-100 PLANT DESIGN AND MECHANICAL {: DESIGN CRITERIA
1.0 INTRODUCTION
1.1 PURPOSE AND SCOPE The Plant Design and Mechanical Design Criteria for the project applies to the systems for which Bechtel has design responsibility. The design criteria form the technical basis for the system design and equipment selection. This is based on specific client and site conditions, code requirements, environmental and licensing requirements, and existir;g power plant design experiences and technology. This document pertains only to structures and systems designed for the cleanup of the containment and subsequent defueling following the March 28, 1979 accident at Three Mile Island Unit 2. It does not address the tasks of reconstruction and requalification of the plant. The purpose of this document is to provide a basis for design of new systems or modifications to existing systems which may be required to support containment entry and decontamination with the objective of placing the containment in a configuration where reacter vessel head ~ removal can begin and fuel may be removed from the reactor and either shipped or stored. The project's Plant Design and Mechanical engineering work is governed by several project design reference documents listed in Appendix A. Of these, the Plant Design and Mechanical Design Criteria shall be the basic design document, and any deviation from it, with the exception of those criteria specifically identified as guidelines, shall be registered (. with the project's Plant Design / Mechanical Group Supervisor before proceeding with the work. Page 1 Rev. 0 f...
DIsign Crit:ria 13587-2-M01-100 (- 2.0 CODES, STANDARDS, AND GUIDES 2.1 QUALIFYING STATEMENT-The latest issue of the governing codes and standards in effect at the time of issue of the purchase order shall be used for all specifica-tions. Design work shall use the latest issue in effect at the time a drawing or document is issued for construction. t 2.2 STATE AND LOCAL CODES AND STANDARDS a. The Pennsylvania State Code, Fire and Panic Regulatior.s by Department of Labor and Industry b. " Clean Stream Laws," Commonwealth of Pennsylvania. 2.3 ALL OTHER CODES, STANDARDS, AND GUIDES a. ASME Boiler and Pressure Vessel Code 1) Section II, Material Specifications 2) Section III, Nuclear Power Plant Components, Div. 1 3) Section V, Non-destructive Examination 4) Section VIII, Unfired Pressure Vessels, Div. 1 C 5) Section IX, Welding and Brazing Qualifications 6) Section X, Fiberglass-Reinforced Plastic Pressure Vessels 7) Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components b. ASME Power Test Codes c. Associated Air Balance Council National Standard for Field Measurement and Instrumentation Total System Balance, Vol. 2, No. 12173 d. Air Conditioning and Refrigeration Institute 1) Standard 430 for Central Station Air Handling Units 2) Standard 550 for Centrifugal Water - Chilling Packages 3) Standard 280 for Central Forced Air Electrical Heating i Equipment 4) Standard 210 for Unitary Air Conditioning Equipment C. Page 2 Rev. 0
Design Criteria 13587-2-M01-100 ( e. Anti-Friction Bearing Manufacturers Association (AFBMA) 1 Standards as applicable f. American Gear Manufacturers Association (AGMA) Standards as applicable g. Air Movement and Control Association (AMCA) 1 1) Standard 210, Test Code for Air Moving Devices 2) Standard 211, certified Rating for Air Moving Devices 3) Standard 500, Test Method for Louvers, Dampers, and Shutters h. American Concrete Institute (ACI) ACI 318 Building Code Requirements for Reinforced Concrete (Note: ACI code applies only as a supplemental code for embedded pipe) ~ 1. American Institute of Steel Construction (AISC) Manual of Steel Construction, 7th Edition j. American National Standards Institute (ANSI) 1) B2.1, Pipe Threads 2) B16.1, Cast Iron Pipe Flanges and Flanged Fitting, ?$. 125, 250 and 800 LB. 3) B16.5, Steel Pipe Flanges and Flanged Fittings 4) B16.9, Wrought Steel Butt Welding Fittings 5) B16.10, Face-to-Face and End-to-End Dimensions of Ferrous Valves 6) B16.11, Forged Steel Fittings, Socket-Welding, and Threaded 7) B16.25, Butt Welding Ends 8) B16.34, Steel Valves 9) S30.2.0, Safety Code for Overhead and Gantry Cranes 10) B30.10, Hooks { 11) B31.1, Power Piping Page 3 Rev. 1
Dasign Criteria 13587-2-M01-100 h 12) B36.10 Wrought Steel and Wrotight Iron Pipe 13) 836.19, Stainless Steel Pipe 14) N45.2.2, Packing, Shipping, Receiving, Storage and Handling of Items f r Nuclear Power Plants 15) N509, Nuclear Power Plant Air Cleaning Units and Com-B ponents 16) N510, Testing of Nuclear Air-Cleaning Systems 17) 51.13, Methods for the Measurement of Sound Pressure Levels 18) 55.1, CAGI-PNEUROP, Test Code for the Measurement of Sound from Pneumatic Equipment 19) Z86.1, Commodity Specification for Air k. American Petroleum Institute (API) 1) Standard 605 Large Diameter Carbon Steel Flanges 2) Standard 620 Design and Construction of Large, Welded, Low pressure Storage Tanks , (-- ' American Society of Heating, Refrigerating and Air Condi-1. tioning Engineers, Inc. (ASHRAE) Standards as applicable American Society of Mechanical Engineers (ASME) m. Standards as applicable American Society of Non-destructive Testing (ACNT) n. SNT-TC-1A, Recommended Practice for Non-destructive Testing, Personnel Qualification and Certification American Society for Testing Materials (ASTM) o. Standards as applicable p. American Welding Society (AWS) Standards as applicable American Water Works Association (AWWA) q. 1) D-100, Standard for Welded Steel Elevated Tanks, Stand- -{ pipes, and Reservoirs for Water Storage Page 4 Rev. 0
0: sign Criteria 13587-2-M01-100 ( 2) C203 Coal-Tar Enamel Protective Coatings for Steel Water Pipe j 3) C209 Cold-Applied Tape Coatings for Special Sections, Connections and Fittings for Steel Water Pipe r. Building Officials and Code Administrators International (B0CA) 1) Basic Building Code 2) Basic Mechanical Code 3) Basic Plumbing Code s. Compressed Gas Association (CGA) 1) G-1 Acetylene 2) G-1.3 Acetylene Transmission for Chemical Synthesis 3) G-7 Compressed Air for Human Respiration 4) G-7.1 Commodity Specification for Air t. Crane Manufacturers Association of America (CMAA) { CMAA70, Electric Overhead Traveling Cranes u. Canadian Standards Association (CSA) Z180.1, Compressed Breathing Air v. Heat Exchange Institute (HEI) Standards as applicable w. Hydraulic Institute (HI) Standards of the Hydraulic Institute x. Manufacturers Standardization Society of the Valve and Fittings Industry (MSS) 1) MSS-SP-25, Standard Marking System for Valves, Fittings, Flanges, and Unions 2) MSS-SP-43, Wrought Stainless Steel Butt-Welded Fittings 3) MSS-SP-44, Steel Pipe Line Flanges 4) MSS-SP-55, Quality Standard for Steel Castings - Visual Method b Page 5 Rev. O n.
Design Criteria 13587-2-M01-100 (" 5) MSS-SP-58, Pipe Hanger and Supports - Materials, Design, Manufacture 6) MSS-SP-61, Hydrostatic Testing of Steel Valves 7) MSS-SP-66 Pressure-Temperature Ratings for Steel Butt-Welding End Valves 8) MSS-SP-67, Butterfly Valves 9) MSS-SP-69, Pipe Hangers and Supports - Selection and Application 4 10) MSS-SP-72, Ball Valves with Flanged or Butt Welding Ends for General Service 11) MSS-SP-73, Silver Brazing Joints for Solder Joint Fittings 12) MSS-SP-80, Bronze Gate, Globe, Angle and Check Valves 13) MSS-SP-84, Steel Valves--Socket-Welding and Threaded 14) MSS-SP-89 Pipe Hangers and Supports - Fabrication and Installation Practices y National Fire Protection Association (NFPA) (.- 1) NFPA-10, Pertable Fire Extinguishers 2 2) NFPA-12A Halon 1301 Systems 3) NFPA-13, Sprinkler Systems, Installation 4) NFPA-14, Standpipe and Hose Systems 5) NFPA-15 Water Spray Fixed Systems 6) NFPA-20 Centrifugal Fire Pumps 7) NFPA-24, Outside Protection 8) NFPA-26 Supervision of Valves 9) NFPA-45, Fire Protection for Laboratories Using Chemicals 10) NFPA-72D Proprietary Signaling Systems 11) NFPA-72E Automatic Fire Detectors 12) NFPA-80 Fire Doors and Windows 13) NFPA-90A Air Conditioning and Ventilating Systems Page 6 Rev. 0 'L,
n.- 03 sign Criteria 13587-2-M01-100 ( 14) NFPA-90B Warm Air Heating and Air Conditioning 15) NFPA-194 Fire Hose Connections 16) NFPA-196 Fire Hose 17) NFPA-30 Flammable and Combustible Liquids Code 1 2. Pipe Fabrication Institute (PFI) 1) PFI-ES-3, Fabrication Tolerances 2) PFI-ES-5, Cleaning Fabricated Piping 3) PFI-ES-24. Pipe Bending Tolerances 4) PFI-ES-26, Welded Load Bearing Attachments to Pressure Retaining Piping Materials aa. Sheet Metal and Air Conditioning Contractors' National Association (SMACNA) 1) High Pressure Duct Construction Standards 2) Low Pressure Duct Construction Standards { bb. Tubular Exchanger Manufacturers Association (TEMA) Standards of Tubular Exchanger Manufacturers Association cc. Bechtel Power Corporation, Procedures, Standards, and Guides dd. Stee: Structures Painting Council (SSFC) 1) SP-6, Commercial Blast Cleaning 2) SP-10, Near White Blast Cleaning 3) PA-1, Shop, Field, and Maintenance Painting 2.4 INSPECTIONS Inspections performed on Section III, VIII, and X stamped components, by authorized Code inspectors not registered in the State of Pennsylvania, will require inspection by the state upon receipt of the component on site. {. Page 7 Rev. 1
D2 sign Critsrie 13587-2-M01-100 3.0 MAJOR PLANT PARAMETERS ((. 3.1 NUCLEAR STEAM SUPPLY SYSTEM Nuclear Steam Supply System data is given in the TMI-2 FSAR. 3.2 PLANT EXTERNAL FACILITIES a Water Source The plant makeup water is from the Unit 1 water treatment system which draws from the Susquehanna River. Spent Fuel Removal The spent fuel is removed by over-the-road truck. Radioactive Solid Waste Removal Solid radioactive wastes that will be generated during the recovery operations will be packaged in approved containers for offsite disposal. An interim solid waste staging facility (ISWSF) will be provided as a temporary storage area for these wastes (approximately six months' storage capacity for both units will be provided). Later permanent low-level and high/ medium-level storage facilities will be provided for storage of recovery and normal operations-related wastes prior to off- {? site disposal. (. Page 8 Rev. 0
Design Criteria 13587-2-M01-100 4.0 GENERAL PLANT CRITERIA FOR DESIGN { 4.1 AIR QUALITY (Plant Discharge Air) The plant shall employ the following design features or practices in furtherance of this requirement: New plant modifications shall be designed and constructed in accor-dance with federally promulgated New Source Performance Standards and the Department of Environmental Quality Rules of Pennsylvania in effect at the time of the change. 4.2 RIVER WATER QUALITIES The water quality design values of the Susquehanna River are as shown in Table 4-1. 4.3 REACTOR COOLANT ANALYSIS The post-accident reactor coolant quality for design will be as shown in the latest issue of B&W Compilation of Chemistry Results for THI-2 Reactor Coolant System. 4.4 QUALITY AND CONCENTRATIONS OF PRINCIPAL NUCLIDES CONTAINED IN REACTOR BUILDING SUMP WATER Data taken in August 1979 is presented in Table 4-2. The data may be J subject to change, depending on the system conditions encountered as the recovery effort proceeds. 4.5 MINIMUM WATER CHEMISTRY SPECIFICATIONS DURING THE PRE-DEFUELING PERIOD Table 4-3 lists the Babcock & Wilcox Company's required and recommended " minimum water quality requirements" for the THI-2 Recovery Effort. The time period of the document is designed to be in effect from the time issued to the initial core defueling. The specifications listed may be subject to change depending on the system conditions encountered as the recovery effort proceeds. 4.6 AMBIENT DESIGN CONDITIONS Table 4-4 lists inside design temperatures and humidities for existing areas. Inside design conditions for new facilities will be addressed in the specific design criteria for each facility. HVAC systems will be designed for the following outside conditions: Summer 94 F DB, 75 F W.B. Winter 7 F DB i Data from ASHRAE Handbook of Fundamentals, 1977 edition, 1 percent values for Harrisburg, Pennsylvania airport. Page 9 Rev. 0
Design Criteria 13587-2-M01-100 O ( 4.7 WASTE WATER QUANTITY New liquid processing systems containing radioective material shall be designed to produce an effluent which conforms to 10 CFR 50, Appendix I guidelines, as interpreted by the THI-2 technical specifications. Tankage shall be designed to retain the processed liquid such that although it is suitable for release from the plant site, releases need not be made. 4.8 LIQUID RADWASTE SYSTEMS RELEASE Should it be necessary to discharge potentially radioactive liquid wastes to the environment, such wastes shall be sampled and analyzed prior to release and shall contain radionuclide concentrations that are in accordance with the Plant Technical Specifications. 4.9 NOISE CONTROL In order to provide the means for evaluating new equipment liable to emit noise which would result in levels in excess of 90dBA, procurement documents shall require proposed and final sound pressure levels for the equipment proposed. Specific noise levels shall not be specified in the procurement document. 4.10 VALVE CRITERIA 4.10.1 All process piping vents shall be 3/4 inch in diameter and have {' 3/4 inch (min.) globe valves, and all process piping drains shall be 1 inch in diameter and have 1 inch (min.) wye pattern globe valves except air / gas systems which shall use ball or plug valves. All vents and drains will have screwed caps. 4.10.2 Double valving shall be used on vents and drains on piping based on the following criteria: Nuclear and safeguard systems above 250 F and/or 200 psig a. b. All balance of plant systems other than item a above 250 F and/or 500 psig; this will prevent leakage due to seat damage from throttling of the first valve, since the second valve is used for shutoff only, not throttling. All sampling connections, since frequent usage would result in c. seat wear. d. Systems containing radioactive fluid where leakage would be hazardous to personnel. Caps or flanges after a single valve, in lieu of a second e. valve, are not to be used. Removal of a cap or blind flange, if there has been leakage, could result in personnel injury due to release of pressure buildup. f. All radioactive tank drains. Page 10 Rev. 0 c.
Design Criteria 13587-2-M01-100 f 4.10.3 Systems which contain, collect, store, or transport radioactive material will use valves which minimize radiation exposure to operating personnel (both direct due to internal crud buildup and inhalation due to external leakage). Straight-through valve configurations or weir type diaphragm valves are preferred to those containing crevices and discontinuities. Diaphragm valves will have radiation-resistant diaphragms. I Valves 2-1/2 inches and larger will have double packing and lantern ring leakoffs, where specified. 4.10.4 Top trim material for boric acid system valves shall be austenitic stainless steel to prevent corrosion due to stem leakage. 4.10.5 To prevent liquid entrapmer.t, double-seated valves (split wedge, flexible wedge, or multiple disc parallel seat) mounted in a horizontal run of pipe will be installed with stem in a vertical position. 4.10.6 Safety and relief valves and cast iron or bronze valves will be flanged. All other valves 2-1/2 inches and larger in a steel piping system will have butt-welding ends. Valves 2 inches and smaller will have socket welding ends except where temperature transients exceed one degree F per minute, buttwald ends are required. 4.10.7 Threaded bonnets for steel gate and globe valves will be seal Ca welded. 4.10.8 Butterfly valves will only be used in lines 6 inches or greater. Application of butterfly valv1s is limited to low temperature pressure and negligible radioactivity services. Flangeless valves will not be used where adjacent pipe or components may be removed while part of the system is in operation. 4.10.9 Torque and Limit Switch Functions for Electric Motor Operated Valves a. All electric motor-actuated valves and gear-actuated valves, 10-inch and larger, 150 lb. and 8-inch and larger, 300 lb., shall be provided with power wrench operation for inter-mediate fast travel between seated and full open positions. i b. Gate, Globe, and Stop Check Valves: Open: Valve travel to the fully open and backseated posi-tion will be controlled by a limit switch. Adjust-ment will be accomplished by cutting off power to the motor before final backseating. Moving inertia through the gear train will then effect final back-seating. Page 11 Rev. O s
Design Critoria 13587-2-M01-100 0 The torque switch will provide protection if mechan-(. ical obstruction prevents opening of the valve, or if the opening limit switch fails to operate. Close: Valve travel to fully close the valve will be con-trolled by the torque switch preset to the required torque to assure valve closure, without damage to the valve or actuator parts. c. Butterfly and Ball Valves Open and Close: Valve travel to the fully open and fully closed positions will be controlled by the limit switch. Adjustments will be accomp-lished by cutting off power to the motor before final seating. Moving inertia through the gear train will then effect final seating. The torque switch will provide protection if mechanical obstruction prevents the valve from opening or closing, or if the limit switch fails to operate. 4.11 PIPING CRITERIA 4.11.1 The standard pipe sizes shall be 1/8, 1/4, 3/8, 1/2, 3/4, 1, 1-1/2, 2, 2-1/2, 3, 4, 6, 8, 10, 12, 14, 16, 18, 20, and 24 inches. h Deviations from these standards will be only for special fabricated piping. 4.11.2 Seal water, lube water, and miscellaneous oil piping around equipment will be installed with flanges or unions for normal maintenance. 4.11.3 A stress analysis in accordance with ASME Section III or ANSI B31.1 will be performed on all seismic Categcry I piping 2-1/2 inches and larger. Non-seismic piping systems containing fluid at 150 F or higher will also be analyzed for thermal expansion. However, a rigorous stress analysis will be performed as the situation may require. Sefsmic II/I will be analyzed as required by the General Section, 13587-? 401-100. 4.11.4 Piping line specification change will normally be shown to change at the valve ends on the Piping and Instrument Diagrams and isometrics (piping plans). However, the more stringent stress anal-ysis requirement will hold to the first anchor beyond the valve. 4.11.5 In general, welded piping joints will be used throughout the plant. Process lines 2-1/2-inch nominal pipe size or above will be butt welded (no backing rings will be used on resin or evaporator bottoms ' lines). Process lines two inches or smaller will be socket welded except where temperature transients exceed 1 F per minute, stress, or other conditions require butt welds. Instrumentation lines (downstream of the first root valve) are not considered process lines, and screwed ' connections may be used. I ~ Page 12 j Rev. O %=
A Dasign Criteria 13587-2-M01-100 3 f_ Flanges will be used with the following: x-a. Rubber-seated butterfly valves b. Cast-iron pumps - - c. Control valves (3 inches and larger) d. ' Safety and relief valves i e. Equipment normally provided with flanges for the temperature and pressure at which it operates and does not create a hazard to plant personnel ,. f. Startup strainers, orifice plates, drainage systems, etc. a 4.11.6 Schedule 40 or 40S pipe will be used for 2-inch and smaller lines requiring volumetric inservice inspection rather than Schedule 10 or 105. ,4.11.7 All stainless steel pipe used for safety-related piping will be > Type "L" (low carbon), as recommended by Regulatory Guide 1.44. In addition non-safety-related stainless steel piping will also be Type "L", l r< unless otherwise noted. 1 o 4.11.8 Appendix B indicates the acceptable guideline velocity limits for various fluids and pipe sizes. A 4.12 PIPE SUPPORT DESIGN CRITERIA y. i \\ 4.12.1 General I 4.12.1.1 Structural Steel Supports shall be designed in accordance with ~ the rules of ASME Section III, Appendix XVII, Design of Linear Type Supports by Linear Elastic and Plastic Analysis. L 4.12.1.2 The supports will be adequate to restrain any additional loads due to various test conditions unless provisions are made for temporary l support during the testing period. = i 4.12.1.3 Pipe supports will not be welded to elbows, tees, or other fittings unless approved by the Project Stress Group. ' 4.12.1.4 Temperatures used to calculate thermal movements (if any) js shall be the' temperatures of all normal operating modes. Spring sup- ' ports will be. selected so that there is sufficient overtravel to accom-l - modate seismic piping displacener* GGI and SSE) without causing the ,. spring to bottom / top out. (, f, 4.12.1.5 All supports wi'l e+ reans of vertical adjustment in the .}' vicinity of equipment and / d t.... removable parts, if required, to avoid interference during luintenanc6, T Page 13 t-L Rev. O 3 l l x
Design Criteria 13587-2-M01-100 0 4.12.2 Materials 4.12.2.1 All materials used in the construction of pipe supports will be in accordance with the referenced codes and standards. All welded piping attachments shall be the same material as the piping to which they are attached. Other materials shall not be used unless approved by the project engineer. 4.12.2.2 Commercially available component standard supports will be i utilized to the fullest extent possible provided they conform with the specification. 4.12.2.3 Component standard supports shall be MSS-SP-69 or approved equal. 4.12.3 Design 4.12.3.1 Support Spacing Support spacing will be as determined by a formal thermal and weight analysis. Where a formal stress analysis is not performed, the code recommended spacing shall be used unless justified by calculations. 4.12.3.2 Loading Conditions The most severe conditions of coincident pressure, weight, temperature and any other fluid dynamic events shall be considered in the design of C, pipe supports. In addition to the above loading conditions, piping routed outside the power block shall be designed for wind and snow loads when applicable. 4.12.3.3 Riser Supports Rigid riser supports on critical piping systems shall be designed for 75% of the total hydro load of the entire riser. All rigid riser supports will be designeri so that the total piping load can be carried by one side of the clamp and one rod in the event of a load shift. 4.12.3.4 Minimum Material Yield Strength shall be as specified in the appropriate table in ASME Section III Appendix I and reduced propor-tionately consistent with the normal operating temperature of the struc-ture. 4.12.3.5 All local stresses in structural steel members shall meet the requirements of ASME Section III Appendix XVII. 4.12.3.6 All welds shall be proportioned in accordance with ASME Sec-tion III, Appendix XVII, Paragraph 2452 and Table XVII-2452.1-1 Piping attachments shall be in accordance with PFI-ES-26. C-Page 14 Rev. O p.
D:: sign Criteria 13587-2-M01-100 (1 4.12.3.7 All holted connections and baseplates shall be designed in accordance with Gaithersburg Power Division Hanger Engineering Stan-dards. Concrete anchor bolts will be wedge-type only and designed with a minimum safety factor of 4 and shall be proportioned to satisfy shear-tension interactfon equation: VT PT + 5 1.0 g g Locking devices shall be used on right-hand threaded or bolted parts to prevent loosening or disengagement from vibration. 4.12.3.8 Friction Force A friction force of.3 times the normal operating load shall be applied to all sliding supports which do not use devices which minimize friction. 4.13 FIRE PROTECTION CRITERIA The selection of detection and extinguishment systems will be determined from a fire hazards analysis. Protection will be provided in accordance with NFPA Codes listed in Section 2.3.y of this document, and the Penn-sylvania State Code, Fire and Panic Regulations. h i l Page 15 ~ Rev. O L
Design Criteria 13587-2-M01-100 l (; TABLE 4-1 RIVER WATER QUALITIES Item Units Value iurbidity JTU 3.3-24 Total hardness ppm 60-242 Suspended solids ppm 2-416 TDS ppm 70-301 ~ pH 7.4-8.8 Sulphates ppm 25-126 Chlorides ppm 7-32 Nitrates ppm 3-13 Minimum daily flow CFS 1,700 .C aver se aa# i aisca rse ces 34.000 The above data is obtained from an ecological study of Susquehanna River near TMI, annual report 1979, compiled by Ichthyological Associates, l1 Inc. Page 16 Rev. 1 c' ~ ~ ~ ____________:_-_-~ ~~ ~~
Design Criteria 13587-2-M01-100 (i TABLE 4-2 QUALITY AND CONCENTRATIONS OF PRINCIPAL NUCLIDES CONTAINED IN REACTOR BUILDING SUMP WATER (a) Radionuclide Content Reactor Containment Bufiding 8 pCi/ml Top Middle Bottom 137 176 179 174 Cs 134 40 40 40 Cs 90 3 3 3 Sr 89 43 41 42 5r 131 0.01 0.01 0.01 7 129 0.08 0.08 0.08 7pgj,) 0.09 0.08 0.14 140Ba/140La 3 1.0 1.1 1.0 H Gross a dpm/mi 3.4 1 1.6 1.2 1 1.3 5.4 1 2.0 'I Element ppm Top Middle Bottom B 1950 2200 1900 C1 10 15 8 Na 1080 1200 1200 pH 8.1 8.1 8.1 a) Data taken from Oak Ridge National Laboratory analysis performed August 28, 1979. C Page 17 Rev. O c
n n e Design Critr.rie 13587-2-M01-100 TABLE 4-3 MINIMJM WATER CHEMISTRY SPECIFICATIONS DURING THE PRE-DEFUELING PERIOD Conduc-Cat. Diss. Total Susp. Dis. Morphn-tivity Cond. C1 F 0 B Na NH NH H Fe Solids Solids line 24 3 Systes pH paho/cm paho/cm ppe ppe ppe _ pge ppe pg pgsg cc/kg g ppe ppe ppe t I. Primary Water !I A. RCS - MU (1)
- 1. 0 1.0 0.1 3000-4500(11) (1)
(7) B. RCS - Flush 6-8 2.5
- 1. 0 1.0 1.0 C.
RC8HT - Flush 6-8 2.5 1.0 1.0 1.0 3000-4500((III 1.0 g D. BWST - MU 1.0 1.0 3000-4500(11) 1.0 E. SFP 1.0 1.0 11} F. RCS/DHR 27.5 (6) (6) (6) 3000-4500 5-15 II. Pres. ' Volume 4 Control l A. BVBT 7000 (nom) 2900 (nos) B. CWST (2) (1) 1.0 1.0 0.1 3000-4000 (1) (7) i C. Surge Tks. (2) (1)
- 1. 0 1.0 0.1 3000-4000 (1)
(7) III. Secondary Water A. FW - Steaming 9.3-10.5
- 1. 0 0.1 0.1
) (Min) B. OTSG - Steaming 9.5-10.5 10 1.0 0.1 2.0 C. FW - Layup 9.5-10.5 (8) 1.0 50-200 2-20 D. OTSG - Layup 9.5-10.5 10 1.0 2.0 50-200 2-20 E. Heater Shells 9.5-10.5 (8) 1.0 50-200 2-20 Layup F. CST (3) 6-8 1.0 0.1 G. Heater Tubes - 9.5-10.5 (8) 1.0 50-200 2-20 Layup Nisc. A. R8 Cleanup & 5.5-8.0 25 10 5.0 Flush H O (9) 2 B. RB Detonized 5.5-8.0 2.5
- 1. 0 1.0 Water Flush C.
Processed H O 2 Star. Tk. (10) D. ICW (5) 8.5-9.5 1.0 1.0 0.1 10-15(5) 25 2-6 Page 18 Rev. 1 e e
D sign Crit 2ria 13587-2-M01-100 ( TABLE 4-3 FOOTNOTES AND KEY FOOTNOTES (1) Sufficient to keep RCS/DHR pH it7.5 59.5; using NaOH. (2) Assumed to be for RCS/DHR makeup. (3) Assumed to be non-treated makeup for OTSG, steam, or pre-boiler cycle. (4) Deleted (5) If water for CRD supply, Cu limited to <0.1 ppm. (6) Specification based on makeup water requirements. (7) 3 times Stoichiometric requirements to react with 0 - 2 (8) Recommended that cation conductivity not exceed 10 pmho/cm. (9) Water quality prior to addition of alkaline additive chemicals. Unless other alkaline chemicals are used, the water should be treated with 5-15 ppm sodium phosphates with a molar ratio of 2.6:1. { (10) Must meet' specifications for intended use, e.g., if for RCS-MU, must meet I-A specs. (11) Limits specified in Interim Recovery Technical Specifications. -l 1 KEY Quality for water used,to makeup to the system. MU = Quality for water used to flush systems. Flush = System w/o MU or flush notation = Quality of water in system. Numbers = Maximum spec unless otherwise identified or range if latter given. h. Page 19 Rev. 1 l f_
Design Criteria 13587-2-M01-100 (' TABLE 4-4 s. INSIDE AMBIENT DESIGN CONDITIONS FOR EXISTING AREAS Normal Operating Name of Building, Temperature Area, or Room Max / Min (F) Reactor Building 130 (Permanent Modifications)/ { 104 max (Temporary Modifications) l Auxiliary Building 110 Turbine Building 107/50 Control Building Area 104/60 Fuel Handling Building 104 Service Building 75/70 Control Room 75/70 I Page 20 Rev. O g
D2 sign Criteria 13587-2-M01-100 ( APPENDIX A DESIGN REFERENCES 1. GPUSC Procedure ES-005 for System Descriptions, latest revision 2. Burns and Roe Criteria Documents, TMI Unit 2, latest revision 3. Oak Ridge National Laboratory Analysis of TMI-2 Sump Water, latest revision 4. Babcock and Wilcox TMI-2 Water Chemistry Manual, latest revision 5. Burns and Roe Flow Diagrams for Three Mile Island Unit 2, latest revision per B & R Drawing Log 6. Burns and Roe System Descriptions for Three Mile Island Unit 2, latest revision per B & R System Description Log 7.. Burns and Roe Specifications for Three Mile Island Unit 2, latest revision per B & R Specification Log C A-1 Rev. 0 <s
D: sign Critsria 13587-2-M01-100 h-i j APPENDIX B Velocity Versus Pipe Diameter 1 The following graph presents guidelines for the selection of pipe sizes j-based on the velocity of the process fluid. I 1 t + i 1 )- J i i B-1 Rev. 0
Design Criteria 13587-2-M01.-100_ E II 1 SUPERHEATED STM 250 / p SATURATED STM '/ 25 PSIG 150 g SATURATED STM ( 25 PSIG s" l -/ r-80 EO 00 30 A[ " / ge Y i,0 B l f l g j# CIRC.WTR avh,e 0 S f~ / / 4 E .$r ( + r/
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= \\ $~ l 1 1 2 3 4 5 6 78910 2 30 40 50 00 INTERNAL PIPE DIAMETIR -INCHES psOTES: f' 1. THESE CURVES REPRESENT A GUIDELINE FOR THE SELECTION OF PIPE SIZES AND ARE (_ BASED ON ENGINEERING JUDGEMENT AND CURRENT PRACTICES. OTHER CRITERIA, SUCH AS ALLOWABLE LINE PRESSURE DROP, ECONOMICAL EVALUATION AND " FLASH-ING" CONSIDERATION, SHOULD BE CONSIDERED WHEN SIZING LINE. 2. SUCTION PIPE SIZES FOR SATURATED WATER SHOULD BE SIZED BASED ON THE PUMP'S NPSH REQUIREMENT,WITH 3 TO 5 FPS CONSIDERED TYPICAL B-2 Rev. 0 ~ -_}}